Text

Monthly Operating Repts for Apr 1980
	ML19309H477
Person / Time
Site:	Point Beach
Issue date:	05/02/1980
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML19309H475	List: ML19309H474; ML19309H477;
References
	NUDOCS 8005130334
	Download: ML19309H477 (11)
	v • d • e

e OFFRATIriG DATA PEPOliT DOCF.El IJo.50-20a h .

DATE May 2, 1980 COMPLLTlD lli C. h. FAi TELEPilOllE 414 27/ 2811 OPLHAlll4G STAIUS

1. UillT liAML: Poll 41 I!EACll llUCLEAR PL ANT UtlIT 1 . tJOTLS .

2.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 APILICADLE

9. 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-imposed reduction in core average temperature in an attempt to inhibit corrosion of steam genarator tubes within the tubesheet crevice. TilIS MOllTil YR 10 DAIE CUML.LATIVE

1. IlOtIRS IN l(EPOI:TIl1G PtitIOD 719 2e903 83e135

12. IluMi>LR OF lloURS l<EACTOh hAS CRITlCAL 609.8 2,154.5 68e671.0 M 13. REACTol< l LSI.bVL SilVTDOhli ilOURS 1.2 18.D 601.0 d 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 753.9 t e) . GROS

TilEDMAL I_lii.1 GY GLI E.RATLD (Mhll) 716e49S 2e413eJ09 95e165e904 M 17. 0 R 05' LLa Cli IC AL Ett RGY i Lisi ItATI.D (MWill 235,470 787 540 31,421,290

18. 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 79.9 g 20. Ilh l1 AValLAltllIli FACTOP 83.5 ~ 74.5 00.0

21. UillT CAPACITY FACTOR (U51llG 11DC hET) 62.1 St.7 74.0 Q g) 2 '. UillI CAPnCITY FAClOR (USING DLR 11LTI 61.8 . 51.S 72.4

25. 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: 00 Unit scheduled to shutdown on July 3, 1980, for ten days to perform steam generator leak testing and eddy O current inspection. o b g 2S. IF SiluTDOhli A1 Lills OF REPol:T l'ERIOD, LSTIMA11.D l' ATE OF 51AR' LOP: llOT SilirlDObli s Co O

DAl 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 l 2 'e 197/

e

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/ 2811 OPEfe 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!LICAUIE

9. 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 ALIVE Y

g 1i. IlOURS 111 1 LPOPTIllG PEll100 719 2e903 67e920

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

15. U1111 RESI l.Vi: SiluTDOWil llOURS 2.0 3.1 109.5 W 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 27e360e010

18. 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:. 0

20. 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 78.2 2". UllII CAlAtITi FAC10R (I151i16 del < 111.1 ) 29.0 di . 3 7 i.1

23. 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 AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY 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 AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY 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 1 REPORT MONTil Ap ri l , 1980 DATE May 2, 1980 COMPLETED BY C. W. Pay TELEPilONE 414/277-2811 m

I4 C 44 tn o 4 o- c4 c -4o

,c v Ev c

-a ~1 m c eo en e e s< a oae a co ae No. Date g gg a jgy Licensee Event y g'g Cause and Corrective Action s :s :x: e v .c Report No, to EO To Prevent Recurrence Q* (4 e U1 c o E 3 0 o

O 1 800228 S 123.2 D 1 80-002/0lT CD ITEXCII As required by the Con fi rma tory Order of 11-30-79, the unit was taken off 1ine on 2-28-80 for the 60 effective full power day steam gen-e rator tes ting. 110we ve r , work did not start on Unit I until 3-10-80 because of a forced Unit 2 out, e.

An 800 psi secondary-to-primary ieak test of both generators was per-formed on 3-11-80 and an eddy cur-rent inspection was conducted. Also, three tubes were pulled during the outage. All tubes with indications and the pulled tube holes were plugged. Also, all tubes and plugs identified as leakers during hydro-sta tic leak testing were repaired.

The unit re turned to 1ine at 0312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months on 4-6-80.

1 F: Forced Reason: Method: 4 Exhibit G--Instruc-S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-B- Maintenance or Test 2- Manual Scram ation of Data Entry C- Refueling 3- Automatic Scram D- Regulatory Restriction Sheets for LER File 4- Other (explain) (NUREG-0161)

E- Operator Training & License Exam P- Administrative 5 AD-28B G- Operational Error (explain)

Exhibit I- Same (01-78) 11- Other (explain)

Source

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

UNIT NAME Point nea eli tin i t 2 DATE May 2. 1980 REPORT MONTil _ April, 1980 COMPLETED BY C. W. Pay TELEPIIONE 414/277-2811 m

4 '

c H tn o 0 e

.h au "co ooe 5t Pe a co En ae No. Date g gg g jgg Licensee Event gg o'g Cause and Corrective Action 8 c :r: o v .c Report No. m eu To Prevent Recurrence o- 54 emp o I 3 0 8

1 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 1

F: Forced Reason: Method: 4 Exhibit G-Instruc-S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-B- Maintenance or Test 2- Manual Scram ation of Data Entry C- Refueling 3- Automatic Scram D- Regulatory Restriction Sheets for LER File '

4- Other (explain) (NUREG-0161)

E- Operator Training & License Exam F- Administrative 5 AD-28B G- Operational Error (explain)

Exhibit I- Same (01-78) 11- Other (explain)

Source i

NARRATIVE SUyS_ARY OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date May 2, 1980 Completed By C. W. Fay Telephone 414-277-2811 Unit 1 was base loaded for 83% of the period after returning to line at 0312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months on April 6 following completion of the 60 effective full power day steam generator testing and inspection outage. The unit operated the remainder of the period with one load reduction. Load was reduced to 280 MWe net for four hours on April 14 for turbine stop valve testing.

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

During post modification testing of the containment spray system, the "B" train activation relay 1CSB would not latch. The latching mechanism was adjusted and proper operation was verified. Licensee Event Report No. 80-003/03T was issued on this event during the period.

On April 9 the 4D emergency diesel generator failed to start during a routine surveillance test. A broken vane in the Start System .1 starting air motor was discovered. The air motor was replaced and operability of the diesel was verified. The redundant air start system would have started the diesel upon a loss of AC accident. The operability of the redundant 3D emergency diesel 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 at the juncture of the discharges from the two component cooling pumps was discovered under IE Bulletin 79-14 irspaction. Licensee Event Report No. 83-006/03L has been issued on this event and 4

a support to insure code conformance has been installed.

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

During safeguards testing on April 15 the RT-63 relay in the reactor trip circuitry failed to reset Efter testing. The relay failed conservatively. The relay was replaced the same day and an investigation to the failure of 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 piping systems, 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. 50-301 Unit Name Point Beach Unit 2 Date May 2, 1980 Completed By C. W. Fay Telephone 414-277-2811 Unit 2 was base loaded for 33% of the period with no load reductions other than the gradual reduction associated with stretch operation. Load decreased from 450 MNe net at the beginning of the period to 430 MWe net on April 11 when the unit was' taken off line for Refueling 6.

The unit was taken off line at 0037 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months on April 11, and after completion of end-of-life physics testing and training startups the unit was placed in cold shut-down for Refueling 6.

Tube R18C37 in the "A" steam generator was pulled for analysis. This tube shut the unit down in February 1980 with a 1,420 gallon per day leak and is the only tube with a deep crevice defect in Unit 2. The tube hole was weld-plugged following removal of the tube. The hot leg ends of two other tubes, which were considered as potential pulling candidates and left unplugged in March 1980, were also plugged at this time. A hydrostatic leak check of the "A" steam generator was performed on April 16 and was satisfactory. One plug (R15C32) was observed to be dripping

, at 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 located in an area where repair is extremely difficult. Water was also observed around the outside of tube R16C55. Water was leaking at less than one drop every ten minutes and appeared to be coming from what appected to be a cladding defect. A repair was not made at this time becc'tse of the small magnitude of the leak and the lack of a Westinghcuse repair procedure. This source of leakage is being discussed with Westinghouse.

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

Initial Final Removed Volume 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months on April 22 and was completed at 0559 hours0.00647 days 0.155 hours 9.242725e-4 weeks 2.126995e-4 months on April 24. A total of 268 steps were performed. Thirty-two (32) new assemblies were put into the core. The reactor internals have been replaced, the control rods latched, and the closure head installed.

All refueling inservice inspection work has been completed,. including a re-inspection of the steam generator feed no::les which were replaced in July 1979. No problems were identified.

The "A" reactor coolant pump seals were replaced during the period.

The unit low pressure turbines were dismantled and cleaned and an inspection of the rotor discs and the blade roots is being performed. The LPl examination resulted in a total of 39 indications in the L-4 and L-3 blade roots and disc steeples. All but one of the indications were removed through polishing techniques. The final indication was repaired.

Further work and invescigation is yet to be performed. The LP2 examination resulted in a total of nine indications in the L-4 and L-3 rows, five blade roots and four disc steeples. All indications have been removed with the polishing technique. The inspections of the low pressure shaft-to-disc keyway interface resulted in no indications present on the LP2 spindle. The inspection of the LPl spindle found a 0.120" crack depth at the keyway apex on the No. 3 disc governor end. A conservative calculated time to reach critical size with safety factors is 7.7 years on initial interpretation.

A visual inspection of the steam generator secondary side and the moisture separator reheater internals was performed during the period; no abnormalities were noted.

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

While testing pressurizer logic channels, pressuriser level Channel 427 sas momentarily failed low by I&C technicians.

The error was immediately recognized and corrected. Redundant pressurizer level channels were available and capable of performing their safety functions. Licensee Event Report No. 80-003/0lT l has been issued on this event. ,

1 A condition which exceeds code allowable limits at the juncture of. the discharges from the two component cooling pumps was discovered under the IE Bulletin 79-14 inspection.

A support which will insure code conformance will be added prior to returning the unit to service. Licensee Event Report No. 80-004/03L has been issued on this event.

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

No other major safety-related maintenance was performed during 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 / Staff 10 CFR 50.59 Review Completed: Unit 1: None anticipated Unit 2: None anticipated d) Scheduled Date for Submitting Supporting 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 l

ML19309H477

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