ML18113A842

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Monthly Operating Rept for Jan 1979
ML18113A842
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/22/1979
From: STEWART W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18113A841 List:
References
NUDOCS 7902200053
Download: ML18113A842 (44)
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Text

,, VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER S.TATION MONTHLY OPERATING REPORT REPORT NO. 79-01 JANUARY, 1979 APPROVED:

MANAGER

.. ,. r -i-CONTENTS Section Key Personnel Changes Operating Data Report -Unit Ill CORRECTED COPY Operating Data Report -Unit ftl Operating Data Report -Unit if2 CORRECTED COPY Operating Data Report -Unit {12 Unit Shutdowns and Power Reductions

-Unit f.il Unit Shutdowns and Power Reductions

-Unit {J2 Load Reductions Due to Environmental Restrictions

-Unit #1 Load Reductions Due to Environmental Restrictions

-Unit #2 Average Daily Unit Power Level -Unit #1 Average Daily Unit Power Level -Unit #2 of Operating Experience Amendments to Facility License or Technical Specifications Facility Changes Requiring -NRC Approval Facility Changes That Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments That Did Not Require NRC Approval Other Changes, Tests and Experiments Chemistry Report Description

  • of All Instances Where Thermal Discharge Limits Were Exceeded Fuel Handling Procedure Revisions That Changed the Operating Mode. Described In The FSAR Description of Periodic Tests Which Were Not Completed Within The Time Limits Specified In Technical Specifications Inservice Inspection Reportable Occurrences Pertaining To Any Outage or Power Reductions Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Unit #1 -Hechanical Maintenance 1 2 2a 3 3a 4 5 6 7 8 9 10 12 14 14 15 15 16 17 18 19 22 23 24 25 26 1' f I .. -ii-e. Section Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Unit #2 -Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Unit !fl -Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Unit #2 -Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Un it /fl -Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods -Unit #2 -Instrument Maintenance Health Physics Summary Procedure Deviations Reviewed by Station Nuclear Safety and Operating Committee After Time Limits Specified in T.S. 28 30 32 34 36 38 39

,, ' I .. KEY PERSONNEL CHANGES JANUARY, 1979 Due to a reorganization of the station, the following new key positions were established effective on the dates indicated and filled by the individuals listed: Position Station Manager Superintendent-Operations Superintendent-Maintenance Superintendent-Technical Services Supervisor-Administrative Services Effective Date January 1, 19 79 Janaury 1, , 1979. January 1, 1979 January 1, ,1979 January 16, 1979 Inc umb en t w. L. Stewart J. L. Wilson R. F. Saunders T. A. Peebles R. L. Baldwin 1 I ... L l (_.. --,_,.. ----2tt-CORRECTED REPORT 1-22-79 Surry Unit 1 lJNIT ---------October 3, 1977 DATE--*-------

0. W. Akins COMP1.ETED BY ________ _ 50-280 DOCKET NO. ________ _ OPERATING STATt:S I. REPORTING PERIOD: __ o_o_o_1_7_7_0_9_o_1

_______ TllROliGH

__ 2_4_o_o_7_7_0_9_3_o

_____ _ 3. 4. HOURS IN REPORTING PERIOD: _ __._7_.2.,.0'-------,..rr,--------------------.--

21.t41 I i ... C't!RRENTLY AUTHORIZED POWER LEVEL 1MWthl DE!'ENDABLE CAPACITY (MWe-NETl

--,--""'-LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY> (MWe-NETl:_N_T_/

A ________ _ REASONS fOR RESTRICTION (IF ANYl: THIS REPORTING PF.RIOD YR TO DATE 5167.1 CtJMULA TIVE TO DATE 27, 721.5 a S. HOURS REACTOR WAS CRITICAL.

......*...*.

8 6. REACTOR RESER VE SHt:TDOWN HOURS ..*..*. 7. HOCRS GENERATOR ON LINE .............. . 8. UNIT RESERVE SHUTDOWN HOURS .........*. GROSSTH[RMALENERGY

10. 11. 1::.. GENERATED (MWHI .................... . GROSS ELECTRIC AL ENERGY GENERATED (MWH) ................*..*.

NET ELECTRICAL l:.SERGY GENERATED (MWH) RLACTOR AVAILABILITY

!*ACTOR ll) ........ . UNIT A VAILAB!LITY f ACTOR (2) ........... . l.'NITC'APA('!TY

!*ACTOR (3) .............*.

UNIT FORCED m:TAGE RATE (41 ......*.....

0 712.5 0 1,729,792 565,955 537,539 96 .3% 1.0% 0 3o72.S 26,972.8 0 0 12,193,702 61,282,058 4,009,580 20,087,943 19,056,134 78.9% 66 .2% I I * :.+10 64.4% 75.1% ::>b

  • i/o 2. 19.0% 13. 14. 15. l6. SHL'TDOWNS SCHEDUU::D TO BEGIN IN NEXT 6 MONTHS (STATE TYPE. DATE. AND DURATION OF EACHl: SIG Inspection, Nov. 19, 1977 -4 weeks 17. 18. (I) l2) If SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP: __ N_/_A _________

_ UNITS IN TEST STATliS !PRIOR TO COMMERCIAL OPERATION I REPORT THE FOLLOWING:

REACTOR AV Al LA Bl LITY FACTOR l'NIT AVAILABILITY

!"ACTOR lNITlAL CRlTICALlTY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL HOURS IN REPORTING PERIOD x 100 HOURS GENERATOR ON LINE HOURS IN REPORTING PERIOD DATE LAST FORECAST DATE ACHIEVED NFT ELFCTRIC-'.L POWF.R GENERATED l3l tJNIT C'APACITY

!"ACTOR MAX. DEPENOA!lLI:

CAPACITY !MWe*NETl X HOUR!) IN Rl:.l'ORTINt;

?t::RIOD (-4) UNIT FORC'ED OtJT AGE RA TE FORCED OUT AGE HOlJRS _H_O_V_R_S_G_E_N-'E-_R_A_T_O_R

___

' I I .-2a-OPER;.TING REPORT DOCKET HO.

-* DATE 05 FEE 7r:i COMPLETED BY O.J. COSTELLO TELE?HOOE 1 . U iV IT !l .4 _l.f E 2. RE?ORTIUG PERIOD 3. LICEllSED POWER u

RATING !GROSS MWE) 5. DESIGH ELECTRICAL RATING (NET MWE) E. UAXIMUM DEPENDABLE CAPACITY (GROSS MYE) 7.

DEPENDABLE lNET MWE) 8. IF CHANGES OCCUR CAPACITY RATINGS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS SURRY 17 9 2441 947.5 92 2 ?11 775 N/A U/l_!T 1 ,------------------------, I NOTES I I I I I '--------------*

' 9.

LEVEL TO RESTRICTED.

IF ANY N/A ! 10.

FOR RESTRICTIONS.

IF ANY 11. EOU3S Ill PERIOD 12. NUMBER OF HOURS REACTOR WAS CRITICAL 13. REACPOR RESERVE SHUTDOWN HOURS GENERATOR ON-LINE 15. UNIT RESERVE SHUTDOWN HOURS 15. GROSS THERMAL ENSRGY GENERATED (MWH) . .., ..l. I *

  • p ..l. -*
  • Q ..l. -* GROSS ELECTRICAL ENERGY GENERATED (MWH) llET ELECTRICAL ENERGY GENERATED (MWH) UNIT SERVICE FACTOR 20. UUIT AVAILABILITY FACTOR 21. UNIT CAPACITY ?ACTOR lUSING MDC NET) 22. UNIT CAPACITY ?A9TOR (USING DER NET) 23. UNIT FORCED OUTAGE RATE 24.

SCHEDULED OVER NEXT 6 MONTHS (TYPE.DATE.ARD DURATION OF EACH) IF DOWY AT END OP REPORT PERIOD, DATE OF STARTUP 2E. YllITS IN TEST STATUS TO OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION N/A THIS MONTH YR-TO-DATE "CUMULATIVE 744.0 704.1 0.0 702.7 0.0 36404.0 0.0 35561.E I) . 0 744.0 704.1 0.0 702.7 0. 0 1701725.0 1101125.o 546305.0 546305.0 s1g513.o 510.513.o 94.4 o/o 94.4 o/o 94.4 o/o o/o 99.9 o/o 39 .. 9 o/o e4.e ojo e4.e o/o 5.6 o/o 5.5 o/o 2£e53eee.o 25490232.0 o/o 6E.4 o/o El.4 o/o 57.9 o/o S/G INSPECTION

-6/2/79 15.1 o/o -3 WEEK ll/A FORECAST ACHIEVED

', , .... ,, I \. . *-----* *--*-* .. *-*--*. CORRECTED REPORT 1-22-79 Surry Unit 1 i.JNIT ---------nATE January 31, 1978 COMPLETED BY 0. w. Akins DOCKET NO. 5 o-23 o ---------OPERA TING ST A Tt.:S 0001 771201 2400 771231 l. REPORTING PERIOD: _______________

Tl!ROUl.H

HOURS IN REPORTING PERIOD: ____ 7_4_4 ___

2. CURRENTLY AUTHORIZED POWER LEVEL {MWthl 2441 .\tAX. DE!'ENDABLE CAPACITY 775 3. LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED

!If ANYl <MWe-NETl:

___ _..;.N.;,:./..;;A=----....,..--

4. REASONS fCR RESTRICTION llF ANY): s. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. Ii. 18. tl i THIS REPORTING PERIOD HOURS REACTOR WAS CRITICAL.

........... . 592.2 REACTOR RESER VE SHUTDOWN HOURS ...... . HOt:RS GENERA TOR ON LINE .............. . 0 589.4 UNIT RESERVE SHUTDOWN HOURS .......... . 0 GROSS THERMAL ENERGY GE:"ERATED tMWHJ .................... . 1,418,378 GROSS ELECTRICAL ENERGY GENERATED (MWHl .................... . 469,850 NET ELECTRICAL ENERGY GENERATED

.*................*..........

447,962 REACTOR AVAILABILITY FACTOR lll ........ . 79.6% ll:--l!T AVAILABILITY I-ACTOR (2) ........... . 79 2"' UNITCAPACITY

[*ACTOR !3) .............. . 77.7% l'NIT rORCED ot:TAGE RATE (41 ........... . .3% YR TO DATE 6762.5 0 6665.2 0 16,052,640 5,281,480 5,023,799 77.2% 74.0% 1.9% Ct:MULA TIVE TO DATE 29,316.9 28.565.2 0 65,140,996 21,359,843 20.267.564 6f\ I 'i'7, f,b.. 8'Z 59 1% 18.1% SHL'TDOWNS SCHEDCLED TQ BEGIN 1:-; "l!:.XT b MONTHS !STATE TYPE. D . .\TE. AND DURATION OF EACHJ: Refueling S/G Inspection.

APril 1978. 4 weeks N/A If SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DA Tf. OF ST ART UP:-------------

UNITS IN TEST STATCS !PRIOR TO COMMERCIAL OPERATION>

REPORT THE FOLLOWING:

REACTOR AVAILABILITY FACTOR l'NIT AVAILABILITY FACTOR INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL HOURS IN REPORTING P.ERIOD X JOO HOURS GENERATOR ON LINE HOURS IN REPORTING PERIOD NFT F.LFCTRICAL

?OWFR TED DATE LAST FORECAST DATE ACHIEVED Ol UNIT C'APACITY FACTOR MAX. DEPENL>ABLl:

CAPACITY X HOURS IN Rl:.fORTING P!:::Rl()l)

(4) UNIT FORCED OUT AGE RA TE FORCED OUT AGE HOURS HOL'RS GENERATOR ON LINE .. FORCED OlJTAGE HOURS a-OPERA'i'I:IG I I fl,,; REPORT DOCKET NO. 50-2R1 .. DATE OS FEB 79 COMPLETED BY O.J. COSTELLO TELEPHONE 904-357-3194 OPERATING STATUS .J_. U !.iIT N A:.1E REPORTING PERIOD 3. LICERSED THERMAL POWER (MWT) 4 UA0EPLATE RATING (GROSS MWE) DESIGN ELECTRICAL RATING lNET MWE)

DEPENDABLE CAPACITY (GROSS MWE) 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 0 IF CHARGES OCCUR IN CAPACITY RATINGS 3 THROUGH 7) SINCE LAST REPORT GIVE REASONS SURRY .UNIT 2 17 g 2441 947.5 2 811 775 NIA 1------------------------, I NOTES . l I I I I I _________________

._, *-9. POWER LEVEL TO WHICH RESTRICTED.

IF ANY N/A (Ii ET

10. EEASORS FOR RESTRICTIONS.

IF ANY 11. :;_ 2. 13. 14 .. :i.5. '17. 1 g . 19. HOURS IN REP02TING PERIOD NUMBER OF HOURS REACTOR WAS CRITICAL REACTOR RESERVE SHUTDOWN HOURS HOURS GENERATOR DY-LINE UNIT RESERVE SHUTDOWN HOURS GROSS THERMAL ENERGY GENERATED lMWH) GROSS ELECTRICAL ENERGY GENERATED (MWH) NET ELECTRICAL ENERGY GENERATED (MWH) UNIT SERVICE FACTOR 20. UNIT AVAILABILITY FACTOR 21. UNIT CAPACITY FACTOR (USING MDC NET) 22. UNIT CAPACITY FACTOR tUSING DER NET) 23. UNIT FORCED OUTAGE RATE 24. SHUTDOWNS SCHEDULED OVER NEXT 5 MONTHS (TYPE.DATE.AND DURATION OP EACH) 25. IF SHUT DOWN AT END OF REPORT PERI09. ESTIMATE DATE OF STARTUP 25. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMM2RCIAL OPERATIOU N/A THIS MONTH YR-TO-DATE CUMULATIVE 744. 0 744.0 50448.0 . *744. 0 744.0 344-24.5 o.o 0. 0 0.0 744.0 744.0 33921. 3 0.0 0.0 0.0 1799584.0 79035761.0 590085.0 590085.0 25814E24.0 560289.0 560289.0 24485373.0 100.0 o/o 100.0 o/o 67.2 o/o 100.0 o/o 100.0 o I o E7.2 o/o 97. 2 o/o 97.2 o Io 62. 5 o/o 91. 6 o/o 91. 6 o/o '59.0 o/o 0.0 0.0 . 21.1 o/o STEAM GENERATOR 6 MONTHS 2/4/79 NONE FORECAST ACHIEi 1 ED Dale 79-1 1-1-79 1 F: Fmced S: Sd1tdulctl (1 1//7) UNIT SHUTDOWNS AND i'OWEn nEPUC"flONS REronT MoN*111 JANUARY 1979 F D 1 : ' Hc:1so11:

A-Eq 11ipmc11t Fall111c (Exp la In)

  • ll-Mal11tc11a11cc oi Test ('.He rucl111g Licensee Even I Rcpott $f 78-0l17 /03L-0 ; ' : D-Hcgulatory ltcstrh:tlon l'.-Opcralor Tral11l11g

& Uccmu Exa111!11utlon F-Ad 111i nist ral l*1c (;.Operalioual E1111r (Exj1lui11)

II 01hc1 (Explain)

J : . Method: I *Manual ' -c: u'1, g "t1 p. *E a aY u 2-Manu:il Scram. J-Aulonrnllc Scram. 4*Ulhcr {Explain)

DOCKET NO. _s_o_-_2_8_0

___ __ UNIT NA1\rr2 .;:.S.=U=Rl=J...Y'--"'l

___ _ J>ATE FEB. 2, 19 ..... 7..._9 __

BY S. STEVENS TELElllONE 357-31.§iL_

Cnusc & C11r1ecllve Action ltl Prevent llci:11rrc111:c Continuation of shutdown begnn 12-8-78 for primary to secondary leakage on 11 C" S/ G exceeding

0. 3 Gl'H limitation,.
  • Inspected steam generators and plugged leaking tubes. 4 s Exhibit G-lnslructlnns

'for Preparation of Dat:i . Entry Sheets for Licensee Evc111 ltcp1>rt (t.EJU File (NlJHEG* 0 I 6 I) Exhil>i1 I

  • S11111t:i:

l I I

"111. Dale F: Forcc<l
  • S: Si:htJuled 0 . , UNIT SHU1noWNS AND row1m rrnpUC'JlONS itEPOilT MONlll JANUARY 1979 L '-0 .. -,., :;) t.IJ .... Uccnscc -., c: t:* 'J u :J 5 *:= a 0. =' V'I Even I >. (! :J -5; I-:J ::r.: cl .!! t5i Rcpntt # Cl --.. 6 NONE DURING THIS : . .. --He:iso11:

A*Equlpmcnl failure (Explain)

U-Mal11lcna11cc oi Tcsl . .. . . . . .. : . C-Rcfucllng

.. . l>*lkg11la1ory Hcstrlcllrm E*Opcrn101 Tnll11l11g

& License J!xamlnallun F -Ad mi 11islra1 l*1c c;.npcra1!011al Ei111r (Explain)

II 01hc1 (Explain)

REPO . . ... t: u tJ 0 "O v; 'O >. 0 p.O V>U *Eu 0 . u . . lTING P1RIOD. : I . * . . MclhorJ: I *Manual 2*Mami:il Scram. J-Aulomallc Scram. *l*Olhcr (Explain)

DOCKET NO. 50-28} SURRY 2 UNIT NAME DATE llY TELE! llONE FEIL 2, J.9 79_ S

  • STEVENS 4 s C:1usc & C1>r1et.:1lve -Acl(o11 111 rrcvc111 Rci:11rrcncc
  • Exhlbll G-lnslrncllons for P1cp;m1tl1111 of ))ala . Entry Sheets for Licensee Evcnl lleporl (I.Ell) File (NllltEG*

.0161) Exhihi1 I

  • I VI I .,
  • t 1--.* 0 ,_ LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.l MONTH: JANUARY, 1979 I I I ! DATE Tll1E HOURS LOAD, HW. REDUCTIONS 2 HW liWH_ REASON -----NONE DURING THIS REPORTING PEB IOD. -, ---* ----. -.' MONTHLY TOTAL 0 -------* --.. -.*

-* ,_ LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS . UNIT N0.2 MONTH: JANUARY, 1979 ' I I I I DATE TI11E HOURS LOAD, HW.

HW MWH REASON ------NONE >URING THIS REPORT] NG PERIO:C. ... .. -*-* *****--* .MONTHLY TOTAL 0 -.. ... -* -------* - r MONTE: ----JAliUARY 1978 AVERAGE DAILY LEVEL DAY (Mf.fE-liET) 1 0.0 2 90.7 3 733.2 4 735.5 5 735.4 6 738.4 7 737.4 8 735.9 9 736.1 10 735.6 11 736.4 12 737.6 13 749.8 14 746.3 15 745.4 16 745.5 DAILY UNIT POWER LEVEL FORM INSTRUCTIOQS DOCKZT t'IO e DATE CO.HPLETED BY M'ERAGE DAY 17 lS 19 20 21 22 23 24 25 26 27 28 29 30 31 50-2<:l0 SURRY I 2-1-7g 0 J COSTELLO DAILY Pm/ER U.1I-lE-NET) 749.3 745.3 743.8 738.6 745.7 .744-.9 744.8 746.5 745.4 744.7 743.2 744.6 742.7 742.8 743.2 LEVE ON THIS FORM. LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACEf ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UUIT. THERE MAY BE OCCASIORS WHEN THE DAILY AVERAGE POdER EXCEEDS THE.100 o/o LINE (OR THE RESTRICTED POWER L&VEL LINE). IN SUCH CASES. THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY

... ,.....,_,,.-,_

-=-'="""---=-=**-::-:::*=***,....*

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---..... . AY..E..!J.flQ.£ l2!lI..Id.

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!{ONT!-!:

JANUARY 1978 AVERAGE DAILY POi-IER LEVEL DAY (MWE-l/ET) 1 751.3 2 742.3 3 755.6 4 763.5 5 752.e 6 762.1 7 762.0 8 761.6 :,.. 9 761.0 10 762.6 11 763.2 12 761.e 13 750.4 14 761.2 15 760.4 16 761.2 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS .XET NO ll lJ I'.i' DATE COMPLET&D BY LE.K&L. AVERAGE' DAY 17 18 19 20 21 22 23. 24 25 26 27 28 29 30 31 50-221 SURRY II 2-1-1e 0 J COSTELLO DAILY

(/.fWE-NET) 760.0 75'.r.2 750.3 761.5 750.5 751.3 760.3 758.5 747.5 742.6 737.1 725.4 715.2 710.7 724.3 LEVE ON THIS FORM.-LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FDR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL EATIOG OF THE UNrT. THERE MAY BE OCCASIONS THE DAILY AVERAGE POWER EXCEEDS 75E 100 o/o LIYE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY wfARY OF OPERATING EXPERIENCE e JANUARY, 1979 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in ificant non-load related incidents.

UNIT 1 January 1 This reporting period began with the unit at cold shutdown condition for steam generator tube leak repairs. January 2 Unit temperature/pressure exceeded 350°F/450 PSIG at 0310. reactor was taken critical at 1556 arid the main generator.

was placed on the line at 1716. The unit reached 50% power at 1830_ and power was maintained at 50% until 2225 to allow calibration of reactor coolant loop flow transmitters.

power to 100% began at 2225. January 3 At 0245 reactor power was held at 99% due to high steam flow .alarms. January 12 -Tne high steam flow alarms were rescaled in accordance with setpoint change SP-79-02.

The unit was at 100% power at 1848. January 20 -Reactor power was reduced to 98% at 0030 to accomplish Special Test ST-6 and power was returned to 100% at 0745. January 24 -A temporary 75 KVA 230 KV/34.5 KV transformer has been installed in place *of the No. 1 Autotie transformer to supply the No. 5 34. 5 KV bus. The transformer was placed in service at 1445.

31 -. This reporting period ends with the unit at 100% power. UNIT 2 January 1 January 10 -January 20 -January 25 -January 26 January 28 January 29 January 30 This reporting period begins with the unit at 100% power. Unit 2 containment inner door of" personnel air lock was damaged. Outer door was closed and_properly sealed. Use of the personnel airlock is prohibited until after unit is shutdoWn..

Pressurizer pressure channel 455 was placed in trip mode at 1223 due to instrument drift. At approximately 0001 commenced coastdown phase at end-of-life by reducing power as necessary to maintain Tave* Unit at 98% power in coastdown phase .. at Unit at 97% in coastdown phase at E.D.L. Unit at 96% in coas tdov.7Il phase at E.O.L. Unit at 94% in coastdown phase at E.O.L.

.... . I UNIT 2 January 31 --11--TMHARY OF OPERATING EXPERIENCE A (CONTINUED) This reporting period ended with the unit at 96% after replacing deborating demineralizer resin and placing demineralizer in service to remove remaining boron. This action allowed subsequent increase in power of approximately 2%. M1EHDIIBNTS TOl*CILITY LICENSE OR TECHNICAL Sl-IFICATIOHS JANUARY, 1979 .The Nuclear Regulatory Commission has issued an amendment No. 46 December 29, 1978, which modifies Surry Unit No. 1 operating license. The amendment results from the NRG Staff!s review of the Steam Generator Inspection Program. Of significance, the conditions limit the operation of Surry Unit No. 1 and has .. the following provisions:

1. Unit No. 1 shall be brought to the cold shutdown condition in order to perform an inspection of the steam generators within six months of equivalent operation from December 29, 1978. Nuclear Regulatory Commission (NRC) approval shall be tained before resuming power operation following this inspection.

Equivalent operation is defined as operation with the reactor coolant at or above 350°F. 2. Reactor coolant leakage from the coolant (RCS) to the secondary system (SS) through the generator tubes shall be limited to 0.3 gpm per generator, as described in the.NRG Safety Evaluation of May 6, 1977. With any steam generator tube leakage ater than this limit the reactor shall be to the cold shutdown condition within 24 hqurs. NRC approval shall be obtained before resuming reactor operation.

3. Reactor operation shall be t*erminated if RCS to SS leakage which is attributable to 2 'or more steam generator tubes._ which occurs during a 20 day period. NRC approval shall be obtained before resuming reactor operation.
4. The concentration of radioiodine in the reactor coolant shall be limited to 1 µCi/gram during normal and to 10 µCi/gram during power transients as defined in Appendix A-1 to the Technical Specifications of the:_li:cense.

Appendix A-1 was issued with the May 6, 1977 Order and shall remain in effect for six equivalent months from December 29, 1978. The Nuclear Regulatory Commission has issued amendment 47 and 46 to the Operating License fcir the Surry Power Station Unit Nos. 1 and 2, respectively January 19, 1979. The amendment results from the NRC Staff's review .of the Steam Generator Repair Program. Of significance, the ditions have the following provisions:

1. 2. The Surry Power Station Steam Generator Repair Program for Unit Nos. 1 and 2 is approved.

During the steam generator repair :program the following conditions shall be met: (a2 All fuel shall be removed from the reactor pressure vessel and stored in the spent fuel

AMENDMEJ\TTS LICENSE OR TECHNICAL SPECIFICATIONS

.., (CONTINUED) (b) The temporary and ventilation systems shall be operating for all cutting and grinding operations involving components with removable radioactive contamination

>2200 DPM per 100 cm 2* (c) The health physics program and procedures which have been established for the steam generator repair program shall be implemented. (d) Progress reports shall be provided at 60 day intervals from the start of the repair program and due 30 days after close of the interval with a final report provided within 60 days after completion of the repair. These reports will include: (i) A summary of the occupational exposure expended to date using the format and detail of Table of the report entitled "Steam Generator Repair Program". (ii) An evaluation of the effectiveness of dose reduction techniques as specified in Chapter 6 of the report entitled "Steam Generator Repair Programs" in reducing occupational exposures. (iii) An estimate of radioactivity released in both liquid and gaseous effluents. (iv) An estimate of the solid radioactive waste generated during the repair effort including volume and radioactive content. 3. Sixty days prior to fuel loading, the program for operational testing and startup shall be submitted for NRC review. a! ACILITY ClL<\NGES REQUIRIHG

.,., NRC APPROVAL JANUARY, 19 79 None .during this reporting period. FACILITY CHANGES THAT DID. NOT .REQUIRE NRC APPROVAL JANUARY, 19 79 None during this reporting period.

  • ' I , STS AND EXPERH1ENTS RE UIRING NRC APPROVAL e JANUARY, l979 None during this reporting
period. TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL JANUARY, 19 79 None during this reporting period. " 0T CHANGES, . TESTS EXPERIMENT JANUARY, 19 79 None during this reporting period.

., PRHlt...RY COOLANT ANALYSIS Gross Radioact., µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml Iodine-131, µCi/ml I-131/1-133 Hydrogen, cc/kg Lithium, ppm Boron-10, ppm + Oxygen-16, ppm Chloride, ppm pH @ 25°C e-SURRY POWER STATION CHEHISTRY REPORT JANUARY 1979 T.S.6.6.A.ll UNIT NO. 1 HAXIMUM MINUfUM AVERAGE 5.14E-l 1. 46E-2 3.18E-l 0.3 0.1 0.2 1. 76E-l 1. 05E-2 9. 91E-2 2.00E-2 3.21E-3 8. 51E-3 0.7673 0.1669 0.3873 l.l) 35.6 1.1 22.7 2.77 0*.54 2.10 254 99 128 7.700 (1) 0.000 0.355 0.05 0.05 0.05 7.38 6.12 7.13 + Boron-10 Total Boron x 0.196 Phosphate Sulfate 50% NaOH Remarks: (1) Unit fll NON-RADIOACTIVE CHEMICAL RELEASES , POUNDS T.S. 4.13.A.8 0.0 Boron 1,112 Chromate 1,400 Chlorine Shutdown.

UNIT NO. 2 MAXIMUM MINIMUM AVERAGE 1. 74E-l 4. 78E-2 9 .93E-2 0.4 o-.o 0.2 l.02E-l 7.54E-2 8.46E-2 6.12E-4 3.03E-4 4.20E-4 0.1548 0.0508 0.0934 37.9 27.1 32.1 0.31 0.10 0.20 . 10 0.0 4 o.ooo 0.000 0.000 0.05 0.05 0.05 8.84 6. 98 7 .68 259 0.0 0.0

  • RIPTION OF ALL INSTANCES WHER DISCHARGE LU1ITS WERE EXCEED.c.

JANUARY, 1979 Due to impairment of the circulating water system following days the thermal discharge limits were exceeded as noted. January 3, 1979 January 4, 1979 January 28, 1979 * *

  • Exceeded 17.5°F 6T across station. Exceeded 15°F 6T across station. Exceeded 15°F across station.
  • Indicates dates when station was <15°F across the station for spmetime during the day. T'nese excursions were allowable under T.S. 4.14.B.2.

There were no reported instances of significant adverse environmental impact. On January 25, 1979, the temperature change at the station discharge exceeded 3°F per hour due to severe temperature transient of James River

  • at both intake and discharge and was reported in accordance with T.S. 4 *. 14.B.1. FUEL HAHDLIHG JANUARY, 1979 Two shipments of new fuel for the upcoming refueling on Unit 2 were received.

One shipment containing 12 fuel assemblies arrived January 22, 1979, and another shipment containing 4 fuel assemblies arrived January 29, 1979.

---.. --. *---:. :-: .:--=-*---* -----**----.IJ--:-*-.

    • ;.;._-.-:..o.---""";"**-

.. :-*:.-....... *-.*

--. --.-..£. . ---# --------.

    • -*--. -* --------

-. -. ________

... __ I .. y e UNIT NO. 1 e FUEL lIANDLING , JANUARY. 1979 DATE NO OF ANSI NO. NEW OR SPENT FUEL SEIPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICI-lllENT SHIPPING CASK ACTIVITY LEVEL --* I . I None during thi13 reporting period. -. --" I i I I

__ -____ , __ ,

____ , --__

..

* --________ , __ -----e !UNIT NO. 2 FUEL HANDLING JANUARY, 1979 ANSI NO. ---. . *-*-**----

.. ****-.. ---* ..........

____ *-*-***

..... _,,,_ ___ _ DATE SIPPED/RECEIVED NO OF ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT 1.1Elv OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL 1 22 79 12 LM06FV/3.4

2. 5 mrem/hr. LH06F8/3 4 2.5 mrem/hr. LM06FW/3.4 2.5 mrem/hr. I LM06EX/3.4
2. 5 mrem/hr. -LM06ES/3.4 2.5 mrem/hr. LM06FC/3.4 2.5 mrem/hr. LM06F7/3.4 2.5 mrem/hr. LM06F0/3.4 2.5 mrem/hr. LN06FU/3.4 2.5 mrem/hr. LM06F5/3.4 2.5 mrem/hr. LM06F9/3.4 2.5 mrem/hr. LM06F4/3.4 I 2. 5 mrem/hr. h29-79 4 LM06EN/3.4 2.5 mrem/hr. LM06ER/3.4 2.5 mrem/hr-.-

LM06FA/3.4

2. 5 mrem/hr. LM06FD/3.4 2.5 mrem/hr. I --I I ---C1 I . , REVISIONS THAT CHANGED T' . 110DE DESCRIBED IN THE FS .. -JANUARY, 1979 None during this reporting period. ION OF PERIODIC TESTS WHICH wA NOT DHPLETED WITHIN THE TI.HE SPECIFIED IN TECHNICAL SPECIFICATIONS JANUARY, 1979 None during this reporting period. INSERVICE INSPECTIOU JANUARY, 1979 None during this reporting period. -

RE TABLE OCCURRENCES PERTAINING

'1l ANY OUTAGE OR POWER REDUCTIONS JANUARY, 1979 None during this reporting period.

.. c c Haint-enance of Safety Related Systems During Outage or Reduced.Power*Periods UNIT Ill Mechanical Maintenance

..

TJP.l'T=NF:C/I UNI'rt-(MllCNTE:NllNCP.

OF S/IF'E.'TY RRT,AT'SfJ SYS'l'eMS DURING OUTAGE OR REOUCF:D POWEii PERIODS) r.r::*rsr.1w 1rr 5YS COM/' M/lliKNO Sl/Hi'lllliY WKf'EWf Ot/01/79 RC SG 1 RC-8-1A Rf,MOVF./lNST/ILf, PRIM M/INWAYS INSTALLF,D 01 /07./7q VS C//If.,/,f,fl 1

f'llN ll/JLTS SLIPPING CllfSCKlW SAT Ol/O'J/7'J 88 /lllTCI/ ESCllI'F:

MllllW/IY Ol11NGS RF:PL/JCf,fJ ORINGS 01/0'J /7'J /JS llt11'Cll VALVE LP.AK TllUU RF.PAIRF:O VALVE /JF.'l'I'

'f01'/lf, u MR TOTDllNTM 1 9121112'13 lj3lJ 1 807010600 7 1 817.311700 113 1 A12311701 527 * '"1 **1 ') I N ..._, I

' (_ ,_ C. --Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT f!2 Mechanical Maintenance

/ Mechanical Maintenance UNIT 2 There was none during this reporting.period.

. , r c c . Maintenance of Safety Related Systems During Outage*or*Reduced Power Periods UNIT frl Electrical Maintenance

IJN!'/'1 -(M/IT NTl\NA/lr:g OF' SM'P.1'Y /1T\f,A1'F;TJ sy,c:nu:;

U/IRJNG OUTAGF: OR RP./JUCF:D POWER PF.RIO/JS)

IU-:1'.'C/(liV/11'

!:YS COlfl' 1111/i'KNO SUNW'./lY r{KJ'E: rw 01 /O'J./7Q f1'S l'/.f/W !.f'l'N 1 -11:.: l'-*1 n Ill SCONN /RF.CONN T'MP N7'R MF.CTI vrsc+RF:C rJ1/0?/7'1 RC /'Ui*ll' 1 /1'C I' *1/J 8/1/,!JNCF:

FUf.fl'+,lfO'fO/l B/l!,/INCF.

/JNIT rJt/0?/7" /IC /'{}/.fl' 1 *UC** 1'

  • 111 TJ/lf,/INCP.

HJMl'+.'>IOTOTI TJ/lf,ANCF:D MOTO/l+TYJMT'

/ tf,"/"f '{'()"/'II/, u MR 1 A12t2111JO 1 qo10111Joo 1 qo1D11601 TO'J'WNTM 7711 7.4 23 R7.1 I w f-' I <' I

(_. c of Safety Related Systems During Outage or Reduced Power Periods UNIT #2 . Electrical Maintenance

'*

/ i \..._ -*-= --33-Electrical Maintenance UNIT 2 There was none during this reporting period.

t". Co * ,) ( ( ( c :c Maintenance of Safety Related Systems During . Outage or Reduced Power.Periods UNIT #1 Instrument Maintenance Instrument Maintenance UNIT 1 There was none during this reporting period.

" ..

  • c *rr C. .. . " *" * *.*:.::.-Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT ff2 Instrll!D.ent P.aintenance

..

      • .. (
  • Instrument Maintenance UNIT 2
  • There was none during this reporting period * . \
I HEALTH PHYSICS e JANUARY, 1979 There was no single release of radioactivity specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20. There were no individuals who received single radiation exposure specifically associated with Unit #1 outage, which accounted for more than 10% of the allowable annual values in 10CFR20.101.

r----*****-\. -\'--.*.* <" Number PT-17.2 PROCEDUl-?EVIATIONS REVIEWED BY SAFETY AND OPERATING COHtHTTEE AFTER TIME LIMITS SPECIFIED IN TECirn1CAL SPECIFICATIONS Unit 2 JANUARY, 1979 Title Containment Inside Recirculation Spray Pumps Deviation Step 5. 3-Change to 11 This reading should be 110 :. amps. Step. 6.1-Change to " The ammeter ing should be 110 amps + 10 amps for 2-RS-P-lA

    • :-11 Step 3.3-Did not dewater pumps. This procedure was completed and the deviation initiated January 4, 1979. The procedure deviation was reviewed by the Station Nuclear Safety and* Operating Committee January 25, 1979.
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