e

.

OFFRATIriG DATA PEPOliT h .

DOCF.El IJo. 50-20a

DATE May 2, 1980

COMPLLTlD lli C. h. FAi

TELEPilOllE 414 27/ 2811OPLHAlll4G STAIUS

. . . . . . . . . . . . . . . . . . . . . . ..1. UillT liAML: Poll 41 I!EACll llUCLEAR PL ANT UtlIT 1 . tJOTLS2.htLFol11tlG PERIOD: APl< I L 1980

.

. .

3. LICFf:St () TilEl< MAL POhER (MWT): 1518. ..

4. IIAMLPLAlE RATIllG (LHOS". MhE): 523.8 ..

S. DESIGil I Le ClRICAl. DATIllG (l!ET Mhl): 497. ..

u. MAX IllUi t DEPl~llDAllLE CAPACITY ( GRO5!. MWE): 519. . .

7. MAXIMUti DEF:11DAl3LL CAPACITY (llET MWE): 495. . . . . . . . . . . . . . . . . . . . . . . . .8. IF CilAtlGLS OC4UP Ill CAPACITY R AT IllG5 (ITEMS tlUMiiER 3 Tilh00Gli 7) SINCE LAST REFoltTe GIVL l l. ASOll?>:

Il01 APILICADLE9. I Ob.f it LFVs i TO hilICll RESTI:IC~ LED, IF Ally (lJET Mhl): XXCiXXXHXXETOWLiKKX 390.0

10 bE A50t4!. FOlt PE51 R I C'l l Ol45 e (IF Alli) : IT3TXVilX.XKT044 TIKE Power restriction is the resul t of a sel f-imposedreduction in core average temperature in an attempt to inhibit corrosion of steam genarator tubes within thetubesheet crevice. TilIS MOllTil YR 10 DAIE CUML.LATIVE

1. IlOtIRS IN l(EPOI:TIl1G PtitIOD 719 2e903 83e13512. IluMi>LR OF lloURS |<EACTOh hAS CRITlCAL 609.8 2,154.5 68e671.0

M 13. REACTol< l LSI.bVL SilVTDOhli ilOURS 1.2 18.D 601.0d 14. IlOURS GEh! R ATOl< Oil L IltE S95.8 2e01).S 6J> e 4 0 b . 'i

15. lit IT PLSI kVL Silu1DOhll iloORS 4.9 ISt.S 753.9t e) . GROS * TilEDMAL I_lii.1 GY GLI E.RATLD (Mhll) 716e49S 2e413eJ09 95e165e904M 17. 0 R 05' LLa Cli IC AL Ett RGY i Lisi ItATI.D (MWill 235,470 787 540 31,421,29018. lit 1 11 I ClP I C AL Eth I<GY 01.lini:ATLD (Mbli) 2.'0,962 743eS7/ 29 e 93 '.e 75'i

6 ') 14 Il111 T SLb V ICL F AtTOh 62.9 69.3 79.9g 20. Ilh l1 AValLAltllIli FACTOP 83.5 ~ 74.5 00.0

21. UillT CAPACITY FACTOR (U51|lG 11DC hET) 62.1 St.7 74.0Q g) 2 '. UillI CAPnCITY FAClOR (USING DLR 11LTI 61.8 . 51.S 72.425. Uhll FOPCLD OI 1AGL DAlt 0.0 0.0 3.S-

F M 24. SilleIDublis * CilEDul.LD OVLH llEXT 6 !!OI11115 ( ~I i PE e DATEe AllD UURnTIOll OF EACill: 00Unit scheduled to shutdown on July 3, 1980, for ten days to perform steam generator leak testing and eddy Ocurrent inspection. o

b 2S. IF SiluTDOhli A1 Lills OF REPol:T l'ERIOD, LSTIMA11.D l' ATE OF 51AR' LOP: llOT SilirlDObli sg

'

Co

ODAl A ItEI'OI Ti.D Alla F ALTORS C AL CLil ATED AS REOUi STI I Ill f il<C t ET !I H DAlEh SI.Pli liDi | 2 'e 197/

el1

;

.

OPER ATIlJG DAI A REPOf(T.

DOci"ET 110 50-301

UATE May 2, I r>80

COf1PLETLD DY C. W. IAY

TEll'.PilOllE 414 2T/ 2811OPEfe AlliaG S16:U5

. . . . . . . . . . . . . . . . . . . . . . . .1. 111111 11AME : POIllT I;LACil llUCLEAR PL Alal UllIT 2 110TES. .

2. RE:PoleT IllG l LR 1OD: Al'ItIL 1980 . .3. LICLil51 D Tilt.RMAL F Obl R (MWTI: 1518. . .

4. IJAMEPLATL RATIl1G (6HOS' MWL): 523.8 . .

S. DESIGli LLr.CTRICAL i< Al l tJG (l'ET Mhl): 497. . .

6. MAXIliUll DEPl tillAULI. CAPACITY (GROS' MWE): 519. . .

7. M AX IliUll DEP' ilOA!!LE C AP!sC11Y (IJLT MhE): 495. . . . . . . . . . . . . . . . . . . . . . . . .el . II- CilAIJGES OC UR Ill C APACITY RATIl1G5 (ITEMS tJu!4DLR 3 TilROUGli 7) sit 1CE LAST REPOliTe GIVE RtAbol15:

1101 AP!LICAUIE9. PO.WE R L E Vi 1. 10 billCil i<ESTi IClED, IF AN) (llET MhEl: 110T APPLICADI.E

10. i<l. A50f t. F OR l LSTRICTIOlibe (IF Alli): IlOT API LICAlli E

Tills MOllTil YR TO DATE CUNtil ALIVEYg 1i. IlOURS 111 1 LPOPTIllG PEll100 719 2e903 67e920

12. IlOM(IER OF IlOURS l'.EAClOR WAS CPITICAL 246.8 2,08%.2 60,985.1O 13. RE ACTOP i f.5. I<VI. GiluTDObla 110111< S 9.4 9.4 175.5W 14. liOURS GLill RATOl' of f LIllE 240.6 2e073.0 S9e80';.0

15. U1111 RESI l.Vi: SiluTDOWil llOURS 2.0 3.1 109.5W 16. Gl<05' 1ilERMAL Ell: RGY (E.ll; RATl D (Mbill 328e351 3e027e064 80e679e603

17. GROS' ELt CTRIC AL 1:il i:GY 6Eth I?ATLD *(MWil) 110e201 le0a4e670 27e360e01018. I1ET Lt CTRIC AL File itGY GLil"HATLD (Mbil) 103,713 956,893 26,032,0a0

g g 19 UlllT SEPVICI F AClOR JJ.S 71.4 8:. 020. Isill T AVnIL.ibli * 1Y FACTOR 3 i.7 71.S 8'; . 2

y 21. 01111 CAPnCITY FACTOR (USIllG MDC IILT ) 29.1 6'.i 78.22". UllII CAlAtITi FAC10R (I151i16 del < 111.1 ) 29.0 di . 3 7 i.123. UllIT FOHCLD OlsTAGI: RAll: 0.0 14.5 2.0

11 ' 24. SiluTij0hil5 ' CilLDULa.ls OVI R lil.XT 6 MOllllis (TYPEe DAlEe Allo 1 UR AT 10ll i+ E ACill :IiOhL

29. IF SiltilDObli Al El!l) OF REPol 1 l'Fl:IOD, LST IMATI.D l >All'. OF STAR'I UP: MAY 15, 1960

isAT:. f<f pol Tf D Allis F ACTol<5 C Al t OL Al FD AS REOts! LTf D Ill l'RC l.ET il l' DA'l Li> St.PTI.llili le 21, 197/

. _ _ ._.

.

DOCKET NO. 50-266

UNIT NAME Point Beacli Unit 1 .

DATE May 2, 1980

COMPLETED BY C. W. Fay

TELEPilONE 414/277-2811

AVERAGE DAILY UNIT POWER LEVEL

MONTil April, 1980

AVERAGE AVERAGE AVERAGEDAILY DAILY DAILY

POWER LEVEL POWER LEVEL POWER LEVELDAY MWe NET DAY MWe NET DAY MWe NET

1 - 1 11 176 21 176

2 - 1 12 176 22 176

3 - 2 13 376 23 376

4 - 7 14 164 24 176

5 - 12 15 371 25 377

6 265 16 38] 26 375

7 369 17 372 27 376

8 370 18 375 28 376

9 373 19 174 29 376

10 373 20 375 30 37s

31 ---

AD-28A(1-77)

.

DOCKET NO. 50-301

UNIT NAME Point Beach Unit 2 *

DATE May 2, 1980

COMPLETED BY c. W. Fav

TELEPIlONE 414/277-2811

AVERAGE DAILY UNIT POWER LEVEL

MONTH April, 1980_

.

AVERAGE AVERAGE AVERAGEDAILY DAILY DAILY

POWER LEVEL POWER LEVEL POWER LEVELDAY MWe NET DAY MWe NET DAY MWe NET

1 450 11 -13 21 -2

2 448 12 -10 22 -2

3 446 13 -4 23 -2

'4 444 14 - 3 24 -2

5 438 15 -2 25 -2

6 440 16 - 2 26 -2

7 435 17 - 2 27 -2

8 433 18 -2 28 -2

9 4 31 19 - 2 29 -2

10 417 20 - 2 30 -3

31 ---

AD-28A(1-77)

_ _ _ _ _ _ - _ _ _ - _ _ _ - - . ._ _

.

UNIT S!!UTDOWNS AND POWER REDUCTIONS DOCKET 110. 50-266,

UNIT NAME Point Ileach Unit 1DATE May 2, 1980REPORT MONTil Ap ri l , 1980

COMPLETED BY C. W. PayTELEPilONE 414/277-2811

mI4

C 44 tn o 4o- c4 c ,c v Ev c-a ~1 m c -4o eo ene e s< a oae a co aeNo. Date g gg jgy Licensee Event y g'g Cause and Corrective Actiona

s :s :x: e v .c Report No, to EO To Prevent RecurrenceQ* (4 e U1 c o

E 3 0oO

1 800228 S 123.2 D 1 80-002/0lT CD ITEXCII As required by the Con fi rma toryOrder of 11-30-79, the unit wastaken off 1ine on 2-28-80 for the 60effective full power day steam gen-e rator tes ting. 110we ve r , work did

not start on Unit I until 3-10-80because of a forced Unit 2 out, e.An 800 psi secondary-to-primary ieaktest of both generators was per-formed on 3-11-80 and an eddy cur-rent inspection was conducted. Also,three tubes were pulled during theoutage. All tubes with indicationsand the pulled tube holes wereplugged. Also, all tubes and plugsidentified as leakers during hydro-sta tic leak testing were repaired.The unit re turned to 1ine at 0312hours on 4-6-80.

14F: Forced Reason: Method: Exhibit G--Instruc-S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-

B- Maintenance or Test 2- Manual Scram ation of Data EntryC- Refueling 3- Automatic Scram Sheets for LER FileD- Regulatory Restriction 4- Other (explain) (NUREG-0161)E- Operator Training & License ExamP- Administrative 5

AD-28B Exhibit I- SameG- Operational Error (explain) Source(01-78) 11- Other (explain)

- _ _ - _ _ _ _ _ - _ _ _ _ - - - _ _ _ - _ _ - -

- _ _ _ . . - . _ . ._

UllIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301 .

UNIT NAME Point nea eli tin i t 2DATE May 2. 1980REPORT MONTil _ April, 1980

COMPLETED BY C. W. PayTELEPIIONE 414/277-2811

_

m4 '

c H tn o 0

.h "c 5t Pe En-,e au o ooe a co aeNo. Date g gg g jgg Licensee Event gg o'g Cause and Corrective Action8 c :r: o v .c Report No. m eu To Prevent Recurrenceo- 54 emp o

I 3 0

81 800411 S 178.4 C 1 N/A N/A N/A Refueling outage details will be

provided following completion of. the outage.

i

3,

1

!

14F: Forced Reason: Method: Exhibit G-Instruc-S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-

B- Maintenance or Test 2- Manual Scram ation of Data EntryC- Refueling 3- Automatic Scram Sheets for LER File '

D- Regulatory Restriction 4- Other (explain) (NUREG-0161)E- Operator Training & License ExamF- Administrative 5

AD-28B Exhibit I- SameG- Operational Error (explain) Source 1(01-78) 11- Other (explain)

i

_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - -

-.

NARRATIVE SUyS_ARY OF OPERATING EXPERIENCE

Docket No. 50-266Unit Name Point Beach Unit 1Date May 2, 1980Completed By C. W. FayTelephone 414-277-2811

Unit 1 was base loaded for 83% of the period afterreturning to line at 0312 hours on April 6 following completionof the 60 effective full power day steam generator testingand inspection outage. The unit operated the remainder of theperiod with one load reduction. Load was reduced to 280 MWenet for four hours on April 14 for turbine stop valve testing.

Steam generator work which consisted of eddy currentinspection, explosive tube plugging, tube pulling, weld repair,and hydrostatic leak testing was completed on April 3. Theunit returned te line with the normally occurring small primary-to-secondary leak rate of less than 30 gallons per day. A totalexposure of 269 man-rem, as recorded by dosimeter, was accumulatedduring the outage while performing steam generator work.

During post modification testing of the containmentspray system, the "B" train activation relay 1CSB would notlatch. The latching mechanism was adjusted and proper operationwas verified. Licensee Event Report No. 80-003/03T was issued onthis event during the period.-

On April 9 the 4D emergency diesel generator failed tostart during a routine surveillance test. A broken vane in theStart System .1 starting air motor was discovered. The air motorwas replaced and operability of the diesel was verified. Theredundant air start system would have started the diesel upon a lossof AC accident. The operability of the redundant 3D emergencydiesel generator was verified when the 4D failed to start.Licensee Event Report No. 80-004/03L has been issued on this event.

A condition which exceeds code allowable limits atthe juncture of the discharges from the two component coolingpumps was discovered under IE Bulletin 79-14 irspaction. LicenseeEvent Report No. 83-006/03L has been issued on this event anda support to insure code conformance has been installed.

4

Leak testing of the moisture separator ruheaters wasperformed during the period. Sixteen (16) tubes in the "A"moisture separator reheater and one tube in the "D" moistureseparator reheater required plugging, and five plugs in the"D" moisture separater reheater required repair. The sealsof the feed pump seal pump were replaced during the period.

.

-1-

_

-.

,

-2-;

During safeguards testing on April 15 the RT-63'

relay in the reactor trip circuitry failed to reset Eftertesting. The relay failed conservatively. The relay wasreplaced the same day and an investigation to the failureof the relay has been started.

Work on IE Bulletins 79-02, anchor bolt inspecF. ion,and 79-14, seismic analysis for as-built safety-related pipingsystems, has shifted to the Unit 2 containment.

No other major safety-related maintenance was; performed during the period.,1

i

!

l!

f

I

I

<

f

3

e .s- 1 , , . -# w - - -- w

. __

*.

NARPATIVE SUMM.ARY OF OPEPATING EXPERIENCE

Docket No. 50-301Unit Name Point Beach Unit 2Date May 2, 1980Completed By C. W. FayTelephone 414-277-2811-

Unit 2 was base loaded for 33% of the period with noload reductions other than the gradual reduction associatedwith stretch operation. Load decreased from 450 MNe net atthe beginning of the period to 430 MWe net on April 11 whenthe unit was' taken off line for Refueling 6.

The unit was taken off line at 0037 hours on April 11,and after completion of end-of-life physics testing and trainingstartups the unit was placed in cold shut-down for Refueling 6.

Tube R18C37 in the "A" steam generator was pulled foranalysis. This tube shut the unit down in February 1980 with a1,420 gallon per day leak and is the only tube with a deep crevicedefect in Unit 2. The tube hole was weld-plugged followingremoval of the tube. The hot leg ends of two other tubes, whichwere considered as potential pulling candidates and left unpluggedin March 1980, were also plugged at this time. A hydrostaticleak check of the "A" steam generator was performed on April 16and was satisfactory. One plug (R15C32) was observed to be drippingat a very slow rate and was not repaired because it has a history i,

of weepage; the tube was not a leaker when plugged and it is locatedin an area where repair is extremely difficult. Water was alsoobserved around the outside of tube R16C55. Water was leakingat less than one drop every ten minutes and appeared to be comingfrom what appected to be a cladding defect. A repair was not madeat this time becc'tse of the small magnitude of the leak and thelack of a Westinghcuse repair procedure. This source of leakageis being discussed with Westinghouse.

Sludge lancing of both steam generators was completedon April 22. The following is a summary of sludge removal:

Initial Final RemovedVolume Volume Volume

"A" Steam Generator 62 gal. 6 gal. 56 gal."B" Steam Generator 91 gal. 4 gal. 87 gal.

Fuel movement started at.0004 hours on April 22 andwas completed at 0559 hours on April 24. A total of 268 stepswere performed. Thirty-two (32) new assemblies were put into thecore. The reactor internals have been replaced, the controlrods latched, and the closure head installed.

-1-

. .-

-2-

All refueling inservice inspection work has beencompleted,. including a re-inspection of the steam generatorfeed no::les which were replaced in July 1979. No problemswere identified.

The "A" reactor coolant pump seals were replaced duringthe period.

The unit low pressure turbines were dismantled andcleaned and an inspection of the rotor discs and the bladeroots is being performed. The LPl examination resulted in atotal of 39 indications in the L-4 and L-3 blade roots anddisc steeples. All but one of the indications were removedthrough polishing techniques. The final indication was repaired.Further work and invescigation is yet to be performed. The LP2examination resulted in a total of nine indications in the L-4and L-3 rows, five blade roots and four disc steeples. Allindications have been removed with the polishing technique. Theinspections of the low pressure shaft-to-disc keyway interfaceresulted in no indications present on the LP2 spindle. Theinspection of the LPl spindle found a 0.120" crack depth at thekeyway apex on the No. 3 disc governor end. A conservativecalculated time to reach critical size with safety factors is7.7 years on initial interpretation.

A visual inspection of the steam generator secondaryside and the moisture separator reheater internals wasperformed during the period; no abnormalities were noted.

A leak check of the condenser waterbox tubes identifiedeight tubes in the No. 1 condenser waterbox and 12 tubes in theNo. 3 condenser waterbox that required plugging.

While testing pressurizer logic channels, pressuriserlevel Channel 427 sas momentarily failed low by I&C technicians.The error was immediately recognized and corrected. Redundantpressurizer level channels were available and capable of performingtheir safety functions. Licensee Event Report No. 80-003/0lT |

has been issued on this event. ,

1

A condition which exceeds code allowable limits atthe juncture of. the discharges from the two component coolingpumps was discovered under the IE Bulletin 79-14 inspection.A support which will insure code conformance will be addedprior to returning the unit to service. Licensee Event ReportNo. 80-004/03L has been issued on this event.

Work on IE Bulletins 79-02, anchor bolt inspection, and79-14, seismic analysis for as-built safety-related piping systems,has been shifted to the Unit 2 containment.

No other major safety-related maintenance was performedduring the period.

.

. .-

SUPPLEMENT TO MONTHLY REPORT FOR April 1980

REFUELING INFORMATION REQUEST

In accordance with our letter dated February 21, 1978, which provided certain

refueling information, we are providing the following update to that refueling

information : (NC = No Change).

a) Next Scheduled Refueling Shutdown: Unit 1: 11/7/80

Unit E: 3/20/81

b) Scheduled Date for Restart: Unit 1: 12/12/80

Unit 2: 4/24/81

c) License Amendment Required / Staff10 CFR 50.59 Review Completed: Unit 1: None anticipated

Unit 2: None anticipated

d) Scheduled Date for SubmittingSupporting Information: Unit 1: September 1980

Unit 2: January 1981

e) Important Licensing Considerations: Unit 1: None

Unit 2: None,

1

f) Number of Fuel Assentlies in Storage Pool: 276

g) Other:

4

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