Text

Monthly Operating Rept for Nov 1980
	ML19345D655
Person / Time
Site:	Point Beach
Issue date:	12/08/1980
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML19345D654	List: ML19345D653; ML19345D655;
References
	NUDOCS 8012160428
	Download: ML19345D655 (10)
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ObERATftlG DAT'A REl' oft DOCVET flo. 50-266 g

CD i O DATF DecemN r 8, 1980 COMPLFTla DY C. W'. FAY j '

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. _ . ,. . TFi i PilOilE 4 186 277 2811 ,

OPERATING STAltlS , , , , , , ,

i 13 litlIT N4ME: POINT DEACll (JllCLfAR N. ANT litlIT 1 IJOTFS ,'

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2,. RgPOl'* TING PERIOD: NOVFMDFR.1980, , ,. ,.

3. LICEUSED TilERh1AL POWER (MWT)i' 1518, , , -

4 NAMEPLATE PATING (GBOSS MWE): 523.8 , ,. ,. !

S, OFSIGN FLITCTRICAL RATING. (ilET MWIM : 497. . , , .

6,. M,AX{Mlla DEEFNO3DLF CAPACITY (GPOLS MWF): 5,19. , , , ,. , , , , , , , , , , , ..

7,PdAXIMLd5 DEPFNDAHLE CAPoCITY (NET,PWF):. 495. , . . . . . . . . . ... . . ... . . .. . . . . ,

P. IF CilANGES_OCrlIR IN CAPACITY PATillGS (ITFMF. IJllMDEP 3 TitPOltCil 7) SINCE LAST RFPORTe GIVF lil'AFOff.: ;

. . NOT APPLICADL.F ... . . . .

9, POWFP L FVi 1. TO WilICll,RESTRICTFD, IF ANY (!'FT. PWF) : 390.0 .

i

10. RFASONc. FOR RFSTieICTIONRe (IF AtlY): FFXXXXV44&lMF4FX4 Power restriction la the result of a self-imposed reduction in core average temperature in an attempt to inhibit corrosion of steam generator tubes within the !

tubesheet crevice. 7pgjS MONTil YR T'O D TE CI'MI l. AT iVE t

it, IfollRS IN .I<FPORTING PFRIOD . ,; 720, 8 e 04 0, 8:t e 272, 12p MilhlpFR OF llollRS itFACTOR WAS. CDITIC At. 634 6 6e860 4 73e376,.9 13 RFACTOR l'FSLl!VI SilllT00WN llOliRS 0,4 19, '> 602,1 !

i tt, l. LOURS GFNFif ATOli ON Lil1F '

. 63 % i 6e708,5 71,102,5 iM f 15, llNIT RESFitVE SilllTDOWN llot TIT 16, GROS'. TilFDMAl, ENfl*GY GFift bATr0 (t/ Wit) 738e200 0.0 a,069 e 2+)

152.8 759.2 U 17, GROS % Ft i CTilICAl FNFilGY GFIJERATID (MWil) 239e320 ?e621eP80a on e ti2: e 004 3 iePStie 03i, g

la, UFT FLt CT8IC AL,.FNI RGY GINI I! ATl O (61Will 2?Se716, P e 47S e 8189, 31 6'.Ser 3, M 19 l.INIT SEFYIFF. FACTOR.. . 8n 0 a3,4 80 S 20, l.INIT AyalleHitITY FACTOR. ,, 8H,0 85,3 81,4 @D. '

21,l.INIT CAPACITY FACTOR (I) SING MDC IfT) 63,1 62,2 73,6 g 2?p I,1 NIT CAPACITY. FACTOR _(llSING DFP ltiT) 63.1 ,

62,.0 72 ?

23,ilNTT FORCED OllTAGF RATF , , _ S.8 . 0.6 3. .i b g)

24. SilllTDOWits '.CilEDilLFO OVFR I1FXT 6 Mol!TilS ( ~i YPF e DATFe AND t!III' ATIo!' GF FACil) :

W 2 S'. Ilb SilllTDOWN AT FilD OF RFPOPT i=FT' l>De FSTiM'ATFD MATF OF E's Ala ll'15 i DFCFM01It 28e 1 9110 3D i b D T5 RFPoltTFD AND FACTORS C'ALClit ATFD AS I)FOl'I.110 ill lific L FT ii l- DA:iO SIPTlMitrit 22e 1977

t OEERAT5NG DAT REP 0llT ?

DOCVFT 110. 50-301 '

DATF December 8, 1980 ,

COMPLETtD DY C. W'. F Y e :

, TFL[PilONE 414 277 2811 l OhERATING SI/.luS .

J , . ... . . . . . . . . . . . . . . . . . . .

1,. UNIT NAMEt_ POINT DEACil NtlCLEAR PLANT lillIT 2 NOTES 2, REPORTING PER100 NOVEMDER.1980, . , ,

3,. L.TCEtJSF.D THERMAL, POWFR (MWT)i 1$ 8,. .

4. NAMEPLATE RATING.(GROSS MWE)! S23.8 .. . .

S,. DESIGN ILFCTRICAL RATING,(UET MWil)3 497 , ,. ,

6. MAXIMuti DERENDADLE CADACITY (GRosh MWE)t S19 .. . . . . . . . . . . . . . . . .

7,. MAXIMpH DEPFNDADLE cal *6 CITY. (Nf!T MWE): . 495. . .. . , . , , . . .. , , . . , .... . .. . ... . ..

8. IF CilANCES_OC[t1B Ip CAPACITY RATINGS (ITEMS NilMBER 3 TilDOilGli 7) SINCE LAST RFPORTe G1VF UFASOtte! ,

. . NOT APPLICADt.E .

9 3 P.0WER LFVFL TO WilICH,RESTRJCTFDe .1F ANY (UET tiWE) 8 NOT APPLIC AHL E '

}0. RFASOt% FOR RESTRICTIONSe (IF AIW): NOT API'LICADtE g TiliS M'NTil O R T'O D T'E CIMI tt ATiVF

-. . . . .. .. . k-~9 '

11,. HQtJRS IN . REPORTING _PEllIOD . , . , 720 Se040 73 057, g 12, NilMDFR OF IlOtfRS ItEACTOR WAS.CitTT1' CAL 698 0 6s909,1 6Se806,0 13 RFACTOli, l'FSEl3VF SiltlTQOWN llOllRS 0,. 6 20,2

.14, 1,10(JRS GF Ni- R ATOR , ON t,1NF 684,.O 6e827,.S 186,3 g' g -

686 e S'.4,. H ,

16,. l)NTT RFSFRVE SilllTDOWN llOllRS . 2.2 17.S 123.9 , 50 16, QROSS TilFHMAl, ENGtGY GFNFPATFD (i!Wil) 989e299 10e02Pe778 87e675 314 17,. GROSS FLi'CTRICAL FNEliGY GFNER ATI-Q. (MWill 338e720 3 e 384 e 1011 29 e 7815 e 8: 8 0 18p t,lFT FLI CTI3TCAL_EtJFRGY OFNI RATFD (MWill 323e864, 3e23Se677, 28e30:1 e 004, 19pl.INIT SERVICF.F6CTOR,.. 95.0 84,.9 86,.4 p

20,t,1 NIT AVoILADILITY FACTOR, 21,1,1 NIT CAPACITY FACTOR (llSING MDC IfT) 95 3 8S 1- 84.5 cD 90..o 81 1 79,.0 [r--- >

22,1,1 NIT C APACITY . FACTOR., (tiSTNG DFR lif TI 90.5 80.7 7 /,. 9 23 LINIT FORCFD OpTAGF RATF , . 1,5 . . .

S.2 1.9

24. SiluTDOWils ?.CilEDt'LFO OVF R NL'XT 6 MOlrillS (TYPEe ',DATFe AtlD nitR ATION OF EACill:

Refueling shutdown April 17,/1981, expected to last approxianately five weeks. -

25. IF SilllTDOWN hT FilD OF RFPollT UFPiODe FSTiM TFD OATF OF MThP'll'I': ilOT' Silln DOWN D TA RFEORTFD AND F).CTOPS C LCt'll.hTFD AN RFOl'I'STI D iH llRC I FTTI'P .NiFO SIPTI'MDrR 2?e 197/

DOCKET NO. 50-266 UNIT NAME Poin t Heach Un i t 1 .,

DATE Decembe r 8, 1980

+

l ;

COMPLETED BY C. W. Fay I i

I TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL L

I i MONTH No ve mbe r , 1980 l

l ll AVERAGE. AVERAGE AVERAGE ,

', DAILY '

DAILY DAILY ,

i POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY hde NET DAY MWe NET ,

1 373 11 375 21 174 2 374 12 374 22 374 3 374 13 374 23 375

.i l( 4 375 14 374 24 374 5 372 15 373 25 375 6 373 16 374 26 111 7 375 17 373 27 - 15

{

. 8 372 18 376 28 - 12 t

I 9 376 19 371 29 -

7 l

10 361 2d 373 30 -

6 i

i 31 N/A e

I AD-28A

, (1-77)

DOCKET NO. 50-301 UNIT NAME Point Beach Iloit 2 *

, DATE December 8, 1980

! COMPLETED BY c. W. Pay ,

TELEPHONE 414/277-2811 j AVERAGE DAILY UNIT POWER LEVEL MONTH Nove mbe r , 1980 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET D%Y MWe NET DAY MWe NET 1 - 11 11 496 21 493 2 387 _

12 496 22 493 3 476 13 496 23 495 4 497 14 496 24 492____

5 494 15 492 25 494 i

6 496 16 496 26 492 7 496 17 494 27 492 _

8 494 18 157 28 491 9 497 19 203 29 492 10 494 2b 424 30 492 31 N/A AD-28A (1-77)

-l.

UNIT SilUTDOWNS AND POWER REDUCT) ONS

DOCKET NO. 50-266 i~

UNIT NAME Point Beach Unit 1 l REPORT MONTil November, 1980 COMPLETED . L'a y TELEPilONE 414/277-2811 i

~

m c H tn O 42 e

32 42 u "ao St u 42 e Pe 42 o L

ce No. Date g gg g jgy Licuasee Event y o 'g Cause and Corrective Action fi :s m e 1 42 .c Report No. m no To Prevent Recurrence c- M gmg g 8

5 801126 F 6.6 A 3 N/A Illi r.Z Z Z Z Z Excessive vibrations in the feed-water system caused a broken air line to the "A" main feed regulator valve. The closure of.the' valve resulted.in a low steam generator level and a steam flow / feed flow mismatch which caused the unit trip.

The line was repaired and the unit brought back to service.

6 801126 F 32.1 A 3 N/A lill ',Z Z Z Z Z Unit tripped as in (S) above.

Investigations are underway to determine causes at this time.

7 801129 S 48 C 4 N/A ZZ iZZZZZ Unit remained off line following (6)

, above for scheduled refueling outage. . Unit scheduled to go back on line December 28, 1980.

1 F: Forced Reason: Methods 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 Sheets for LER File D- Regulatory Restriction 4- Other (explain) (NUREG-0161)

E- Operator Training & License Exam F- Administrative 5 AD-28B'

Exhibit.I- Same G- Operational Error (explain) Source (01-78) 11- Other (explain)

t t

i UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET !!O. 50-301 *

i UNIT NAMI: Point Beach Unit 2!

REPORT MONTil November, 1980 DAYE December 8, 1980 COMPLETED BY C. W. Pay TELEPIIONE 414/277-2811 ;

~

m 44 c H tn o _ 42 oa ca o C 43 r8v c

-e e

ee a a o ooe vi o Ee en ,

4) 54 42 o ae No. gg jyy Licensee Event y t

Date g g o'g Cause and Corrective Action E4 :s ::: e 44 .c Report No. un g3 O To Prevent Recurrence Q* W. e U3 C o ,

E; lE O i i b 801101

~

6 S 25.9 B l N/A 11 0 XXXXX) Unit 2 was shut down to perTorm '

numerous secondary system repairs to !

ensure continued operation during the upcoming Unit I refueling.

7 801118 P 10.1 D .' 80-010/03L-0 SP PUMPX> The unit was shut down to meet Technical Specification require-ments for having one safety injec-tion pump out-of-service for a

. period greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The safety injection pump, 2PlST, was found to have broken keys holding the coupling on both the motor and pump.. The pump was repaired and the unit was brought back to cervice.

8 801119 F 0 D 4 N/A ZZ ZZZZZi The unit was held at 50% power due to delta flux consideration following the startup from the safety injection pump outage.

I.

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

E- Operator Training & License Exam (NUREG-0161)

F- Administrative Exhibit I- Same AD-28B G- Operational Error (explain)

(01-78) 11- Other (explain)

Source

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-266 Unit Name Point Beach Unit 1 Date December 8, 1980 Completed By C. W. Fay Telephone 414/277-2811 Unit 1 operated at 375 MWe net throughout the period with one load reduction, two uait trips and a shutdown for the annual refueling outage. Load was reduced to 297 MWe net for three hours on November 10, 1980, to perform turbine stop valve testing.

At 0434 hours0.00502 days 0.121 hours 7.175926e-4 weeks 1.65137e-4 months on November 26, 1980, Unit 1 tripped because of the closure of the "A" steam generator main feed regulator valve, resulting in "A" steam generator low-level coincident with steam flow / feed flow mismatch. Vibrations in the feed system are assumed to have caused a broken air supply fitting on the valve positioner causing the valve closure. Red phone notification was made to the NRC reporting the trip. The fitting was repaired and the unit was returned to line at 1109 hours0.0128 days 0.308 hours 0.00183 weeks 4.219745e-4 months on November 26, 1980.

At 1542 hours0.0178 days 0.428 hours 0.00255 weeks 5.86731e-4 months on November 26, 1980, Unit i reactor tripped again due to "A" steam generator low-level coincident with steam flow / feed flow mismatcl. The trip was preceded by substantial vibration in the feedwater system. It is believed the trip was due to the malfunction of the main feed regulator valve. At the time of the writing of this report an investigation of the feedwater system and regulator valve is being conducted. Red phone notification was made to the NRC reporting the trip.

Due to the refueling outage which was scheduled to begin on November 29, 1980, the unit was not returned to the line and preparations for refueling were begun.

One 30-day licensee event report was filed during the period. At about 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months on November 13, 1980, with both units operating, it was discovered that the suction to the 1P4B boric acid transfer pump was isolated, thus making the pump inoperable. The pump was probably isolated af ter boric acid tank recirculation per Technical Specification sampling at about 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months on November 11, 1980. The 2P4A pump was also out-of-service for a portion of this time period for maintenance. Having both pumps inoperable is a violation of a limiting condition for operation and reportable per Technical Specification 15.6.9.2.A.2. The isolation of the pump probably occurred due to personnel error in returning

4 1

the valve lineup to normal following recirculation and sampling.

Following discovery, the valve lineup was returned to normal, verified by the Duty Shift Supervisor, and a pump operability test was performed.

l The unit is shut down at this time for its annual refueling outage. The unit is expected to return to line on December 28, 1980.

There was no safety-related maintenance performed during the period.

J I

e

,w

i NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 50-301 Docket No.

Unit Name Point Beach Unit 2 Date December 8, 1980 Completed By C. W. Fay Telephone 414/277-2811 i

I.

Unit 2 operated at 495 MWe net throughout the period with two load reductions and twc shut-downs. Load was reduced to 420 MWe net for five hours on Novenber 3, 1980, at the request of Power Supply and'to 435 MWe for approximately two hours on November 15, 1980, at the request of Power Supply.

5 The unit was taken off line at 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months on November 1, 1980, to perform numerous steam plant repairs

, to ensure continued reliable operation during the Unit i refueling outage. The unit returned to service at 0245 hours0.00284 days 0.0681 hours 4.050926e-4 weeks 9.32225e-5 months on November 2, 1980, and reached full power operation

, at 0808 hours0.00935 days 0.224 hours 0.00134 weeks 3.07444e-4 months on November 2, 1980.

Unit _ was alsc taken off line at 0858 hours0.00993 days 0.238 hours 0.00142 weeks 3.26469e-4 months on November 18, 1980, to meet Technical Specification require-ments for having one _ safety injection pump out-of-service for a period greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The reactor was shut down at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months . Following' repair of the safety injection

pump, the reactor was critical again at 1811 hours0.021 days 0.503 hours 0.00299 weeks 6.890855e-4 months on i November 18, 1980. The unit was brought back on line at 1905 hours0.022 days 0.529 hours 0.00315 weeks 7.248525e-4 months on November 18, 1980. A red phone notification. -

was made to the NRC regarding the outage.

Three licensee reportable events occurred during the i period.

On November 1, 1980, during normal power operation, performance of ICP 2.14 (Periodic Test Nuclear Instrumentation

- Power Range) found the P8 permissive bistable from Channel N44 to be set at 50.5%. This is a two-out-of-four logic scheme and j all other channels were within the 49% (+0, -1) specification.

1 This event is reportable in accordance with Technical Specification 15.6.9.2.B.l. The cause of the out-of-specification bistable is attributed. to instrument drift. The previous test of the

, bistable on September 12, 1980, was satisfactory. The bistable was adjusted and tested satisfactorily on November 1, 1980. The a other operable chann.els would have provided the safety function i of this circuit. The permissive provides for blocking of the

reactor . coolant flow trip when power is below its setpoint of 49% (Licensee Event Report No. 80-009/03L-0).

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At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on November 17, 1980, with the unit operating, the 2P15A safety injection pump was taken out-of-service to repair an oil leak. While repairing the oil leak, it was ncted that both the motor and pump-shaf t-to-coupling keys were sheared; however, due to binding of the coupling on the shafts, the pump had remained operable. In accordance with Technical Specification 15.3.3.2.b, an orderly shut-down of the unit was started at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on November 18, 1980. The reactor was shut down at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months . Following repair of the pump the unit was brought back on line at 1905 hours0.022 days 0.529 hours 0.00315 weeks 7.248525e-4 months on November 18. 1980. The cause of the sheared keys is unknown.

No loss of function of_the pump occurred however because of binding between the :oupling and shafts. The pump and motor were checked for datage, the keys replaced, and operability of the pump verified p::ier to return to service at 1801 hours0.0208 days 0.5 hours 0.00298 weeks 6.852805e-4 months on November 18, 1980 ' Licensee Event Report No. 80-010/03L-0).

During a norm <1 start-up on November 18, 1980, the indicated axial flux difference was noted as deviating from its target band. After unsuccessfully attempting to return the axial flux difference to the target band withir the time allotte1, the reactor was limited to 50% power. Eowever, the high neutron flux setpoint was not reduced to 55% as indicated by Technical Specification 15.3.10.B.2.d.l. This event was reportable in accordance with Technical Specification 15.6.9.2.B.1 Improper interpretation of Technical Specification 15.3.10.2.2.d.1 resulted in the f ailure to lower the high neutron flux setpoint (Licensee Event Report No. 80-Oll /03L-0) .

The only safety-related maintenance performed during the period was the repair of the 2P15A safety injection pump as l

decerited in the prior narrative.

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ML19345D655

Text

SUMMARY

SUMMARY

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