ML18136A370

Monthly Operating Repts for Dec 1979

ML18136A370
Person / Time
Site:	Surry
Issue date:	01/03/1980
From:	Costello J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18136A369	List: ML18136A368 ML18136A370
References
NUDOCS 8001140241
Download: ML18136A370 (41)

Text

.*

VIRGINIA ELECTRIC AlID P.OWER COHPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT*NO. 79-12 DECEMBER, 1979 MANAGER 8001140 ~ <./,

-i-CO:NTENTS Section Operating Data Report 1 Operating Data Report Unit f.!2 2 Unit Shutdowns and Power Reductions Unit /Jl 3 Unit Shutdowns and Powe~ Reductions Unit 112 4 Load Reductions Due to Enviromnental Restrictions Unit 111 5 Load r-.eductions Due to Environmental Restrictions Unit #2. 6 7

Average Daily Unit Power Level Unit 111 8

Average Daily Unit Power Level Unit 1,!2 Sun:imary cf Ope.:::- a ting E):perience 9 Ar.u.endments to Facility License or Techr:ical Spec.ific.at:ions 10

. _11

Facility Changes Requiring HRC Approval ..

Facility Changes That Did Not Require NRC Approval 11 Tests and b:peiiments Requiring HRC Approval 12 Tests and Experiments That Did Not Require. NRG Approval 12 Othe.-::- Changes, Tests and Experiments 13

. Che.,.,.,.; stry Re.port* 14 Descr:..pt.ion of All I.~stanc.es Wnere Thermal. Discha.rge Limits 15 Were ~ceedec Ftie.l liand.li.ng 16 Proceau::-e. F-eYisions That Changed the Opera~ing Node Described In 19 The ?512 Descriptiot of Ferio.dic Tests* Which were Not Completed ~ithir. The - . 20 Time l..iz::its Speci£i.ed In .Technical Specifica-:ions 21 Reportaole.Oc.cu:-rences Pert:aining to Any.Outage or '.P6..-er Red.uct{ons 22

~iE.int.ena-::;.ce of Safety Re.lated Syst ;;;c: During Outage or Reduced Power 0

23' Pe::-iod.s - l:rci: i'.'l *- Mechanical Haintenance

~iE.in:.e:u.2nc:e of Sa=:ety Related Sysr:ems During Out.age or Redu::::.ed Power 26

?e:::-ioc.s - U:-.i: t.'2 - l:ied:ar~ical Maintenance

-ii-Section Maintenance of Safety Related Systems During Outage or Reduced 29 Power Periods - Unit /fl - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 31 Power Periods - Unit #2 - Electrical Maintenance Haintenance of Safety Related Systems During Outage or Reduced 33 Power Periods - Unit /fl - Instrument Maintenance Haintenance of Safety Related Systems During .Outage or Reduced 35 Power Periods - Unit /f 2 - Instrument Maintenance Health Physics Summary 37 Procedure Deviations reviewed by Station Nuclear .Saiety .and 38 Operating Committee after Time Limits Specified in T.S.

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11. HCUR5 IN P.2P:J?!ING P?F.IOD 744.0 Q7F.O.O 5>l4Fi4.Ct

12. J,'l"*::E?F QF HOURS HZ..lCJ'O!? .W tlS C.1.I::'IC AL c.o Q19.4 34499.9

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50-280 DOCKET NO.

UNIT SJllJJllOWNS AND rowr:n Jtl!PUt"nONS UNIT NAl\11: _ _SlJRH,Y _L__

llAlE _ _.JAN_,_2_._J_913D_

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/ilX-0 . Reactor Coolant Pump motor on gr:ound fault. Hotor will be replaced prior to startup.

79-11 12/30/79 48.0 D Unit down for replacement of RCP motor. I w

NRC requirement to successfully test I RCP snubber prior to startup.

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50-281 UOCKEl. NO.

UNIT SlllJJllOWNS AND rowmt JJEPUtnoNS UNIT NA1111: SURRY UNIT 2 l>AlE 1/2/~-

CO~IPl.ETEll llY 0.J. COSTELLO IH'.l1 0rt"f ~fOlflll DECEMBER* 1979 TELl'.l llONE (l.lOl1) 357-;3184

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LO.AD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: DECEt:IBER, 19 79 I

I I THE. HOURS LO.A.D 2 MW REDUCTIGNS 2 MW REA.SON I

DATE

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NONE DURING THIS REPORTING PEB IOD.

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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS

. UNIT NO. 2 MONTH: . DECMEBER, 1979 I

DATE

- - l T:U1E HOURS LOAD 2 MW REDUCTIONS 2 1rw Milli

-- REASON NONE DURING THIS REPORTING PEI lIOD .

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MONTHLY TOTAL 0

e DOCKZI ,11iit'&so-280 UNI'!lf" SURRY I DAI'2 1-1.- 0 0 C0 1-JPL2T2D BY . 0 J C05T2LLO AV2P.~1 DAILY UNI:;' PJi./?P LZVF'L

.;,JT}.":'E: D2C?!*:BZE 79 AVZP.AG? DAILY POWZR LZVZL ,.W2RAG2 DAILY POW2R L?VZL D"-'Y (l.J N2T) D'1Y CMW2-N2.T) 1 752. 9. 17. .747.2 2 75F..4 18 751. 8

.;; 750.5 19 439.1 4 754.3 20 o.o

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11 751. 3 27 o.o ~........

12 1r.;;

752.3 74q,4 28 29 0.0 0.0

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14 751.1 30 o.o 15 749.7 31 o.o

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.... t: 749.8 DAILY UA"II PGf.i2F.. L-::VZL FO?!-t INSTRUCTIONS ON IEIS FOR!-!. LI5':: TE2 rfv'2.1AG2 DAILY UNIT POW?R L?VZL IN l*fw2-N2T FOP. 2'1CH DAY IN IHZ R.Z?OP.::'ING !1Cl,'Ib.'. THZE FIGUR2S WILL B2 US2D TO PLOI' A GRAPH FOR EACH RZPORT-ING 110NTH. NOTZ TH2 EY USING J::AXIUU!v! D2PZNDABL2 CAPACITY FOR TH? NF'J' 2L?CTRICAL F.A7'D1(; CF IHZ u1;r:, ':E2F.Z !.;',ff B? OCCASIONS f.i7H?N TH2 DAILY AVZRAG.? P0¥1ZR 2XCZ't:DS

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D:..I1~I [i;~:I7' PDtl2F. ,][T~?r.. 1::- ._-=;f;,*~z:: SHOl'LD BZ F00:::1~:o~~D TC ZXF~riif.: :T"H2 ei?.~AEZ!rI' /d. 0.'*~AL~l. 7

DOCKZT NO 50-***

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UNIT 0[R _ .L.i DA'J'2 1-1,...::io.

C0!1FL2T2D BY 0 J COS1'2LLO

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D2C2MBZR 79 AVZRAG.2' D,J.ILY POW2R L?VZL A1'i?RAG2 DAILY PCf*lZE LZT/ZL DAY (!1fi2-.NCJ') DAY (/.fw2..,NZ:!')

1 c.o 17 o.c 2 c.o 1P c.o 3 o.o 19 ('. c 4 o.o 20 c.o

~ c.o 21 0. 0.

~ 0.0 22 c.o 7 c.o 23 0;0 Q

0.0 24 o.o 9 0.0 25 o.c 10 o.o 2F. c.o 11 o.c 27 c.o

12 o.o 2c c.o

• 13 o.o 29 0,. 0 1 I*

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!Jr:..1.J.J- P0fl2!i LFVZL FOP!{ INSTRUCIIONS ON '.:HIS FOP..!*'., LiI3': 'I'H? AVZEAG2 DAILY UNIT POW2R LZVZL Ili !*f'i'12.,,/1:ZT FOR ZACH DAY IN

~i:lZ RZF>QR?I!lG !~.'!J.',~::rl:*. IHZ,):.. FIGL'Rl5 fiILL B? ['52D TO PLOI1 r.l GE./JYb~ FOR ZACl:.' R?FJQ_PI'!"'

ING .h:Oll7'H. !10'!'2 '!'H,.l_I' EY USING HAXIMU!*: D.2'P2NDABL2 CAPACITY FOR TH? NFT 2L2C.TP.ICAL F:riI7!:,~;J CF Ib.-Z U!.~I7 ~ TH??2 !#;.~}' BZ OCCAi...::;Ia1~7 5 ~'t**t::"C:l-: :Tfi? EAILY rH1 2RAG2 *FCfl2.t~ ?i_~C22D . .~

71IZ 1C1 C ojo ;.~I . r2 (OF. T'll? E25."7F.IC~~D POfiFF L?i/2L LIN?). I!~; 5Uc7h. C"152,S, ::-F-:*t; AVFFA*~F D:..iL'X ~;t:II po; ...c:.~ Q~i.-:!?[i*-: 1...:;F*l??I ~-'>E:J~lLD Bl iO.'J-.?l~'OT?D :T'C' ?XPLAIN *TltZ ~PP~R?/:i*T ,.F~'O/.fADY"

-

SUMMARY

OF OPERATING EXPERI.

DECEMBER, 1979 Listed belo~ in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents.

UNIT 1 December 1 Tnis reporting period begins with the unit at 100% power.

December 19 At 1400 the reactor tripped due to a ground fault trip of the lA Reactor Coolant Pump motor. At approximately 1402 safety injection was initiated on a high steam header to steam.line differential pressure signal. A cooldown was commenced to effect repairs and the unit was less than 350°F-450 psig at 2330.

December 20 The unit reached cold shutdown conditiorts at .0620.

December 31 This reporting period ends with various maintenance in progress.

UNIT 2 December 1 This reporting period begins with the unit at cold shutdown, all fuel removed from the reactor and steam generator replace-ment in progress.

December 31 This reporting period ends with the unit at cold shutdown.

.AMENDMENTS TO ILITY LICENSE OR TECHNICAL SP. ICATIOU'S DECEMBER, 1979 NONE DURING THIS REPORTING PERIOD.

F ACILITY CllANGE.S REOUIRD.

NRC AP PROVAL DECEMBER, 1979 None during *this reporting period.

FACILITY CHANGES THAT

• DID NOT REQUIRE NRC APPROVAL DECEMBER., 1979 None during this reporting period.

TESTS AND EXPERil1Brrs REQUIRING .a

" NRC APPROVAL W DECEMBER, 1979 None during this reporting period.

TEST AND EXPERLlv:!ElITS THAT DID NOT REQUIRE NRC APPROVAL DECEMBER, 1979 ST Leak.age Monitoring Leakage monitoring was conducted on 12-19-79 on Unit No. 1. The test revealed small packing gland leaks, and also a few leaks in sampling lines. Maintenance requests were submitted to correct all discrepancies.

eaTHER CHANGES, T~~~~ AND EXP~ *,

DECEMBER, 1979 None during this reporting period.

• .I

~* - .

CHEMISTRY .REPORT DECEMBER , 19 79 T..S.6.6.A.ll PRL""i..\R.Y COOLANT UNIT NO. 1 UNIT NO. 2

• ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMDM MINIMDM AVERAGE

.Gross Radioact., µCi/ml 5.45E-l 6.41E-4 3.33E-l 3.20E-3 2.81E-6 4.48E;..4

• suspended soiids, ppm 0.1 0.1 0.1 p.3 0.1 0.1 Gross Tritium, UCi/ml 1. 50E-l 5 . 92E-2 1 . 25E~l NA* NA* NA*

Iodine-131, UCi/ml 3.lOE-1 4.BlE-3 2.84E-2 NA* NA* NA*

I-131/I-133 0.8580 0.2425 0.3953 NA*. NA* . NA*

Hydrogen, cc/kg 3 4.0 4.9** 20.5 NA* NA* NA*

Lithium, ppm 0.90 0.80 0.86 NA* NA* NA* -

Eoron-10, ppm + 266** I 56 135 218 83 113 OxYgen-16, pp!:l 2.4** 0.000 0.484 9.3 1.3 5.1 Chloride, ppm 0.05 Io .os o.os 0.05 0.05 0.05

• pR @ 25°C j 1 .00 5.32 6.62 5.59 5.25 5.40

~ Boron-10 = To:.al Boron x 0 al96 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T. S. 4 .13 .A *.8

• Phosphat:e . 90.0 ~orou 531 Sclfat:e 1040 .Chromate 0.36

~-----~---~~~-

50% NaOE 2085 Chlorine 0 .0

--~~~~~~~-

Remarks: *Test not applicable due to unit shutdown.

• • Unit shutdown.

~ DESCRIPTION OF ALL INSTANCES~

rHEID1AL DISCHARGE .LIUITS WERE ~ .t.EDED DECEMBER, 1979 Due to impairment of the circulating water system on the following days the thermal discharge limits were exceeded as noted.

December 1, 1979

• Exceeded 17 .5°F f:i.T across stat:i_on December 2, 1979

• Exceeded 15°F b.T across station Decemb.er 8 1979

• Exceeded 15°F f:i.T across station 11, ' 1979 Exceeded 15°F 6.T across station December

• December 12, 1979 "* Exceeded 15°F f:i.T across station December 13, 1979 Exceeded 17.5°F f:i.T across station December 14, 1979

• Exceeded l5°F f:i.T across station December 15, 1979

• Exceeded 15°F f:i.T across station December 16, 1979

• Exceeded l 5 °F f:i.T across station December 17, 1979

• Exceeded 17 .5°F f:i.T across station December 19, 1979

• Exceeded 15°F b.T across station

• Indicates dates where station f:i.T was <15.0°F across the station for sometime during the day.

The f:i.T excursions were allowabl.e under Technical Specifications 4.14.B.2.

There were* no reported instances of. signif-icant adverse emt.ironmental impact.

On December 12; 1979 the temperature change at the station discharge exceeded 3°F per hour while removing "D" waterbox from service for suspected tube leakage. This event was reported in accordance with Technical Specifications 4.14.

On December 19, 1979, the temperature change at the station discharge exceeded 3 °F per hour, . when Unit Ho. 1 reactor tripped on failure of lA reactor. coolant pump. This event was allowable in accordance with Technical Specification 4.14.

L

FUEL HAlIDLIUG DECEMBER, 1979 There was no fuel received or shipped during this reporting period .

. **

-* . -** -~-- *-- -----

UNIT NO. 1 Page 17 e FUEL RANDLill"G DECEHBER, 1979 e .

. ..

DATE NO OF ANSI NO. NEW OR SPEN'! FUEL SHIPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL

..

None during this reportin~ neriod.

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UNIT NO. 2 J

' . . e FUEL HANDLING DECEMBER, 1979 Page 18 e

'

DATE NO OF ANSI NO.

SHIPPED/RECEIVED NEW OR SPENT FUEL ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL None during this reporting period.

..

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ROCEDURE REVISIONS THAT OPERATING MODE DESCRIBED IN DECEUBER, 1979 None during this reporting period.

- DESCRI~N OF PERIODIC TESTS WHICH w'ER..41aoT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNIC..~ SPECIFIC..fJIONS DECEHBER, 1979 PT-24.4E Fire Protection System P.T. to determine that all fire extinguishers are properly installed and operational was not completed as scheduled on 12-15-79. The inspection was completed satisfactorily on 12-26-79, 4 days beyond the 25% grace period granted in Technical Specifications.

PT-44.1 The Piezometer Reading P. T. to document the depth of the water table at Surry Power Station was not completed as scheduled on 12-25-79. The procedure was completed on 1-2-80 one day beyond the grace period authorized.

INSERV'ICE INSPECTION DECEMBER, 1979 The monthly visual inspection required by IE Bulletin 79-17 Revision 1 (Pipe Cracks In Stagnant Borated Water Systems) was completed on Units 1 and 2. Unit 2 will not receive another visual inspection unless the ultrasonic examination scheduled prior to startup is not accomplished. The monthly inspection on Unit 1 will continue. No reportable indications have been noted.

Ultrasonic .inspection of the reactor coolant pump motor flywheels was completed satisfactory as part of the ongoing inservice inspec-tion scheduled for the Unit 2 refueling.

Unit 2 preservice inspection was complete on steam generator 11 C" secondary side and on all reactor coolant piping associated with the steam generator replacement project.

REP.LE OCCURRENCES PERTAINING TO-ANY OUTAGE OR POWER REDUCTIONS DECEMBER, 1979 Unit No. 1 outage occurred on 12~19-79 because of a reactor coolant pump malfunction. The details of this problem and the actions surrounding this event are contained in LER 79-041/ZlX-O. (050-280).

Maintenance of Safety Related Systems During Outage or Reduced Power Periods*

UNIT #1 Mechanical M.q.intenance

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Maintenance of Safety Related Systems During Outage or Reduced Power Perio.ds UNIT 112 Mechanical Maintenance

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• Rif1',11Ri'D OIL Lil'.JK :1. 9120511109 . P9 17/I t/'/9 SI MOV l'l/1 \/'19 SI MOV 11ov.s1"2"r,3,1 Lil*IITORllQl'P: LP:.111.ING orr. Rf.P,IITii'.'D on iF1IK 2 9120511111 7'i'.'ST /1F'r,JE'l! 1'11LVl Sr.'T RiiLiff 1'Ri!:5S 2 912or,t1101 101 n/11 /'19 sr VAl.V2' TrV*SI*'.lPSA,I P/11 /'19 51 V,lf,V,,- TrV*f11*7P5P8 TEST R'iTf.JFi!' V.ILVii' Si'T Ri!:LIFF PRFSS '2 912or.1*101 tot VALl'ii 11.v-sr-7n5A nsr nn.rr;;; v.nvii' Sii'T RFLIFF PRFSS '1 9120r,11103 101 l'J/11/'19 SI 211 OT//(.[I l'S-5 WC:T.D SOl'RCf. TIOV .TO BPR.t T1ICKFD f.IFWW SOl'l'ir.ii' T(I ,,.Nn PWr. 2 9120~1131 17/1'.!//9 fl/

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l'J/20/'19 TIC V1ILVii' DC 79-05 Cf/,Jll(Jf' STl'DS TO ,<:,<;

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~mv.sI.2nr.9n REPL,ICE STl'VS kt:ri.ir."cv srl'vs  :! 9t1101s1r, 71r, 17/'lll/"/9 SI MOV r.r;l'L,lc;r; ourno,lfm s;i: ,If. 9i1130Ri5 350

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11/11/'19 INSTii rs .. su-2011 nr:rr;,tcil' PTl/fSSl 111i': SllITCI/ llil'l'f,,ICW 1'1/rSSl'll?: SYITCTI 7 912090"/00 25 t'J/11/'19 *""'

CTI INSTR n.n1r9 G1r.8 IS JJllOK?; Rii"Pi11Cl"n Gtll'Ga '1 912110535 3 17/IS/"/9 Cl/ INSTR rrr..11q,1 . INVrr.,1ron n;i:,111 OUT*Oll.T. . .. Cl/r:Cli/W. TNTEGR,ITOR FOTI l'TiOl'im OPS 2 9l21117q5 23 17/l"l/"19 lln MON11'011 RI*Sll**'.li'I INDIC.ITOTI voes NT GO .TO C1li >t.1ilk OPER1ITOR t:RROll c,1r, CfltCICiW SAT 2 9121*10~30 F.*

~IVNI*i'on TII*ll~m.759 IllVIC,ITOR VOES NOT GO TO c,ir, /.l,li11i . orrn.ITOR l:R110TI c,1r, C/JtCli /),IT 2 9121110~31 F.*

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INIJJC,ITOR VOP.S NOT GO fO Tllf c,1r, /.J,lfl . OI'r:tl1ITOll 08110'1 C.JL CHi::CKF.D S1IT 1 9i1t11or,31 r,R 12/.1"1/'19 RU MONlTOR RI*S.?tt'it?

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• HEALTH PHYSICS DECEMBER, 1979

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There was no single release of radioactivity or radiation exposure specifically associated with an outage that acc~unted for more than 10%

of the allowable annual values in 10CFR20.

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~ PROCEDURE DEVL~TIONS REVIETJED BY STATION NUCLEP.J.I' SAFETY AND OPERATING cm£HTTEE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS DECEHBER,

• 19 79 NUMBER UNIT TITLE DEVIATION 2 Feedwater Flow F-2-297 Data Sheet - Change 3 volt PT-2.lOA data point simulated inches to 142.60.

This procedure was deviated October 16, 1979 and reviewed by the Station Nuclear Safety and Operating Committee December 5, 1979.

1 Waste Gas Decay Tank "B" Tank placed in hold.

OP-23.2 Operation This procedure was deviated November 29, 1979 and reviewed by the Station Nuclear Safety and Operating Committee December 14, 1979.

OP-23.2 1 Waste Gas Decay Tank Hz Analysis not setup Operation for operation.

This_ procedure was deviated November 29, 1979 and reviewed by the Statio~ Nuclear Safety and Operating Committee December 14, 1979.