ML18113A842

Monthly Operating Rept for Jan 1979

ML18113A842
Person / Time
Site:	Surry
Issue date:	01/22/1979
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18113A841	List: ML18113A840 ML18113A842
References
NUDOCS 7902200053
Download: ML18113A842 (44)

Text

,,

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

MANAGER

.. -i-

,. r CONTENTS Section Key Personnel Changes 1 Operating Data Report - Unit Ill CORRECTED COPY 2 Operating Data Report - Unit ftl 2a Operating Data Report - Unit if2 CORRECTED COPY 3 Operating Data Report - Unit {12 3a Unit Shutdowns and Power Reductions - Unit f.il 4 Unit Shutdowns and Power Reductions - Unit {J2 5 Load Reductions Due to Environmental Restrictions - Unit #1 6 Load Reductions Due to Environmental Restrictions - Unit #2 7 Average Daily Unit Power Level - Unit #1 8 Average Daily Unit Power Level - Unit #2 9 S~ry of Operating Experience 10 Amendments to Facility License or Technical Specifications 12 Facility Changes Requiring -NRC Approval 14 Facility Changes That Did Not Require NRC Approval 14 Tests and Experiments Requiring NRC Approval 15 Tests and Experiments That Did Not Require NRC Approval 15 Other Changes, Tests and Experiments 16 Chemistry Report 17 Description *of All Instances Where Thermal Discharge Limits 18 Were Exceeded Fuel Handling 19 Procedure Revisions That Changed the Operating Mode. Described In 22 The FSAR Description of Periodic Tests Which Were Not Completed Within The 23 Time Limits Specified In Technical Specifications Inservice Inspection 24 Reportable Occurrences Pertaining To Any Outage or Power Reductions 25 Maintenance of Safety Related Systems During Outage or Reduced Power 26 Periods - Unit #1 - Hechanical Maintenance

1'

-ii-f I e.

. Section Maintenance of Safety Related Systems During Outage or Reduced Power 28 Periods - Unit #2 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 30 Periods - Unit !fl -Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 32 Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 34 Periods - Un it /fl - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 36 Periods - Unit #2 - Instrument Maintenance Health Physics Summary 38 Procedure Deviations Reviewed by Station Nuclear Safety and 39 Operating Committee After Time Limits Specified in T.S.

,, ' 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 Effective Date Inc umb en t Station Manager January 1, 19 79 w. L. Stewart Superintendent-Operations Janaury 1, , 1979. J. L. Wilson Superintendent-Maintenance January 1, 1979 R. F. Saunders Superintendent-Technical January 1, ,1979 T. A. Peebles Services Supervisor-Administrative January 16, 1979 R. L. Baldwin Services

1 I -2tt- CORRECTED REPORT 1-22-79

... Surry Unit 1 lJNIT - - - - - - - - -

October 3, 1977 DATE--*-------

0. W. Akins COMP1.ETED BY _ _ _ _ _ _ _ __

DOCKET NO. _ 50-280 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_ _ _ _ __

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

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

3. LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY> (MWe-NETl:_N_T_/A _ _ _ _ _ _ _ __

4. REASONS fOR RESTRICTION (IF ANYl:

THIS CtJMULA TIVE REPORTING PF.RIOD YR TO DATE TO DATE 718-~ 8 5167.1 27, 721.5 S. HOURS REACTOR WAS CRITICAL. . . . . . . * . . . * .

6. REACTOR RESER VE SHt:TDOWN HOURS ..*..*. 0 0 a

7. HOCRS GENERATOR ON LINE . . . . . . . . . . . . . . . 712.5 3o72.S 26,972.8

8. UNIT RESERVE SHUTDOWN HOURS . . . . . . . . . * . 0 0 0

~ GROSSTH[RMALENERGY 1,729,792 12,193,702 GENERATED (MWHI . . . . . . . . . . . . . . . . . . . . . 61,282,058

10. GROSS ELECTRIC AL ENERGY 565,955 4,009,580 20,087,943 GENERATED (MWH) . . . . . . . . . . . . . . . . * . . * .

l (_.. -- 11. NET ELECTRICAL l:.SERGY GENERATED 537,539 3:812~369 19,056,134

,_,.. (MWH) 1::.. RLACTOR AVAILABILITY !*ACTOR ll) . . . . . . . . .

78.9% 66 .2%

13. UNIT A VAILAB!LITY f ACTOR (2) ........... .

I I * :.+10 64.4%

96 .3% 75.1%  ::>b

• i/o

14. l.'NITC'APA('!TY !*ACTOR (3) .............*.

1.0% 2. '~% 19.0%

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

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. If SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP: _ _ N_/_A_ _ _ _ _ _ _ _ __

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

DATE LAST DATE FORECAST ACHIEVED lNITlAL CRlTICALlTY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL (I) REACTOR AV Al LA Bl LITY FACTOR x 100 HOURS IN REPORTING PERIOD HOURS GENERATOR ON LINE l2) l'NIT AVAILABILITY !"ACTOR ~-~~-~-~~~--~x100 HOURS IN REPORTING PERIOD 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 FORCED OUT AGE HOlJRS

(-4) UNIT FORC'ED OtJT AGE RA TE O_N_L_l_N_E_+_F_O_R_C_~_:o~o-u-*T_A_G_E_H_O_U_R_S~XIOO

_H_O_V_R_S_G_E_N-'E-_R_A_T_O_R___

' I I

.-2a-OPER;.TING REPORT DOCKET HO. 50-2~0

-* DATE 05 FEE 7r:i COMPLETED BY O.J. COSTELLO TELE?HOOE £04-357-31~4 1 . U iV IT !l .4 _l.f E SURRY U/l_!T 1

2. RE?ORTIUG PERIOD 17 9

3. LICEllSED ~~ERMAL POWER ~MWT) 2441 ,------------------------,

u ~~MEPLATE RATING !GROSS MWE) 947.5 I NOTES I

5. DESIGH ELECTRICAL RATING (NET MWE) 92 2 I I E. UAXIMUM DEPENDABLE CAPACITY (GROSS MYE) ?11 I I

7. MAXI~UU DEPENDABLE C~PACITY lNET MWE)

8. IF CHANGES OCCUR I~ CAPACITY RATINGS 775 N/A

.IT~US 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS

9. PO~ER LEVEL TO ~HICH RESTRICTED. IF ANY N/A

10. R~ASONS FOR RESTRICTIONS. IF ANY N/A THIS MONTH YR-TO-DATE "CUMULATIVE

11. EOU3S Ill REPORTI~G PERIOD 744.0 744.0 5355~.o

12. NUMBER OF HOURS REACTOR WAS CRITICAL 704.1 704.1 36404.0

13. REACPOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 1~. HOU~S GENERATOR ON-LINE 702.7 702.7 35561.E

15. UNIT RESERVE SHUTDOWN HOURS 0. 0 0.0 I) . 0

15. GROSS THERMAL ENSRGY GENERATED (MWH) 1701725.0 1101125.o e2os7E7~.o

..l. I

• GROSS ELECTRICAL ENERGY GENERATED (MWH) 546305.0 546305.0 2£e53eee.o

• p

..l. -

• llET ELECTRICAL ENERGY GENERATED (MWH) s1g513.o 510.513.o 25490232.0

• Q

..l. -

• UNIT SERVICE FACTOR 94.4 o/o 94.4 o/o 66.L~ o/o

20. UUIT AVAILABILITY FACTOR 94.4 o/o 94.~ o/o 6E.4 o/o

21. UNIT CAPACITY ?ACTOR lUSING MDC NET) 99.9 o/o 39 .. 9 o/o El.4 o/o

22. UNIT CAPACITY ?A9TOR (USING DER NET) e4.e ojo e4.e o/o 57.9 o/o

23. UNIT FORCED OUTAGE RATE 5.6 o/o 5.5 o/o 15.1 o/o

24. SHUTDO~NS SCHEDULED OVER NEXT 6 MONTHS S/G INSPECTION - 6/2/79 - 3 WEEK (TYPE.DATE.ARD DURATION OF EACH)

IF ~HUT DOWY AT END OP REPORT PERIOD, ll/A ZSTI~ATE DATE OF STARTUP 2E. YllITS IN TEST STATUS FORECAST ACHIEVED

~PRIOR TO CO~MERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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 ATt.:S 0001 771201 2400 771231

l. REPORTING PERIOD: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Tl!ROUl.H - - - - - - - - - - - - - - - -

HOURS IN REPORTING PERIOD: _ _ _ _7_4_4 ___....,.,.T"T"::-------------------~----

2. CURRENTLY AUTHORIZED POWER LEVEL {MWthl 2441 .\tAX. DE!'ENDABLE CAPACITY <~tWe-NET) 775

3. LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED !If ANYl <MWe-NETl: _ _ __..;.N.;,:./..;;A=----....,..--

4. REASONS fCR RESTRICTION llF ANY):

THIS Ct:MULA TIVE REPORTING PERIOD YR TO DATE TO DATE 592.2 6762.5 29,316.9

s. HOURS REACTOR WAS CRITICAL. . . . . . . . . . . . .

6. REACTOR RESER VE SHUTDOWN HOURS ...... . 0 0

7. HOt:RS GENERA TOR ON LINE . . . . . . . . . . . . . . .

589.4 6665.2 28.565.2

8. UNIT RESERVE SHUTDOWN HOURS . . . . . . . . . . . 0 0 0

9. GROSS THERMAL ENERGY 1,418,378 16,052,640 65,140,996 GE:"ERATED tMWHJ . . . . . . . . . . . . . . . . . . . . .

10. GROSS ELECTRICAL ENERGY 469,850 5,281,480 21,359,843 I

GENERATED (MWHl . . . . . . . . . . . . . . . . . . . . .

\. . 11. NET ELECTRICAL ENERGY GENERATED 447,962 5,023,799 20.267.564

{~WH) .*................*..........

12. REACTOR AVAILABILITY FACTOR lll . . . . . . . . . 79.6% 77.2% 6f\ 'i'7, I

13. ll:--l!T AVAILABILITY I-ACTOR (2) . . . . . . . . . . . . 79 2"' f,b.. 8'Z

14. UNITCAPACITY [*ACTOR !3) .............. . 77.7% 74.0% 59 1%

15. l'NIT rORCED ot:TAGE RATE (41 . . . . . . . . . . . . .3% 1.9% 18.1%

16. 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 Ii. If SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DA Tf. OF ST ART U P : - - - - - - - - - - - - -

18. UNITS IN TEST STATCS !PRIOR TO COMMERCIAL OPERATION> REPORT THE FOLLOWING:

DATE LAST DATE FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL tl i REACTOR AVAILABILITY FACTOR X JOO HOURS IN REPORTING P.ERIOD HOURS GENERATOR ON LINE l'NIT AVAILABILITY FACTOR ~-~----------~X\00 HOURS IN REPORTING PERIOD NFT F.LFCTRICAL ?OWFR GF~ERA TED Ol UNIT C'APACITY FACTOR MAX. DEPENL>ABLl: CAPACITY !~We-NET) X HOURS IN Rl:.fORTING P!:::Rl()l)

FORCED OUT AGE HOURS (4) UNIT FORCED OUT AGE RA TE ~-------------------------~x100 HOL'RS GENERATOR ON LINE .. FORCED OlJTAGE HOURS

a-I I OPERA'i'I:IG 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 SURRY .UNIT 2

~- REPORTING PERIOD 17 g

3. LICERSED THERMAL POWER (MWT) 2441 1------------------------,

4 UA0EPLATE RATING (GROSS MWE) 947.5 I NOTES . l

~- DESIGN ELECTRICAL RATING lNET MWE) ~2 2 I I

~. MAXI~UM DEPENDABLE CAPACITY (GROSS MWE) 811 II _________________._,I

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 775 0

IF CHARGES OCCUR IN CAPACITY RATINGS NIA

,ITE~S 3 THROUGH 7) SINCE LAST REPORT GIVE REASONS

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY N/A (Ii ET M~IE)

10. EEASORS FOR RESTRICTIONS. IF ANY N/A THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REP02TING PERIOD 744. 0 744.0 50448.0

_ 2. NUMBER OF HOURS REACTOR WAS CRITICAL . *744. 0 744.0 344-24.5

13. REACTOR RESERVE SHUTDOWN HOURS o.o 0. 0 0.0 14 .. HOURS GENERATOR DY-LINE 744.0 744.0 33921. 3

i.5. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 GROSS THERMAL ENERGY GENERATED lMWH) 1799584.0 1799584~0 79035761.0

'17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 590085.0 590085.0 25814E24.0 1 g . NET ELECTRICAL ENERGY GENERATED (MWH) 560289.0 560289.0 24485373.0

19. UNIT SERVICE FACTOR 100.0 o/o 100.0 o/o 67.2 o/o

20. UNIT AVAILABILITY FACTOR 100.0 o/o 100.0 o I o E7.2 o/o

21. UNIT CAPACITY FACTOR (USING MDC NET) 97. 2 o/o 97.2 o Io 62. 5 o/o

22. UNIT CAPACITY FACTOR tUSING DER NET) 91. 6 o/o 91. 6 o/o '59.0 o/o

23. UNIT FORCED OUTAGE RATE 0.0 0.0 . 21.1 o/o

24. SHUTDOWNS SCHEDULED OVER NEXT 5 MONTHS STEAM GENERATOR REPLA~EMENT (TYPE.DATE.AND DURATION OP EACH) 6 MONTHS 2/4/79

25. IF SHUT DOWN AT END OF REPORT PERI09. NONE ESTIMATE DATE OF STARTUP

25. UNITS IN TEST STATUS FORECAST ACHIEi1 ED (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMM2RCIAL OPERATIOU

UNIT SHUTDOWNS AND i'OWEn nEPUC"flONS DOCKET NO. _s_o_-_2_8_0___~ __

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

J>ATE FEB. 2, 19.....7.. _9__

l CO~ll'l.ETED BY S. STEVENS .~

REronT MoN*111 JANUARY 1979 TELElllONE (801~) 357-31.§iL_

Licensee

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79-1 1-1-79 F D 1 78-0l17 /03L-0 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.

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,_ 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.

0-MONTHLY TOTAL 0

LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS

. UNIT N0.2 MONTH: JANUARY, 1979

' II I HOURS LOAD, HW. REDUCTIONS~ HW I

MWH REASON DATE TI11E - -

NONE >URING THIS REPORT] NG PERIO:C.

.MONTHLY TOTAL 0

DOCKZT t'IO 50-2<:l0 e UN~'l.'

DATE CO.HPLETED BY SURRY I 2-1-7g 0 J COSTELLO r

MONTE: JAliUARY 1978 AVERAGE DAILY PO~/ER LEVEL M'ERAGE DAILY Pm/ER LEVE DAY (Mf.fE-liET) DAY U.1I-lE-NET) 1 0.0 17 749.3 2 90.7 lS 745.3 3 733.2 19 743.8 4 735.5 20 738.6 5 735.4 21 745.7 6 738.4 22 .744-.9 7 737.4 23 744.8 8 735.9 24 746.5 9 736.1 25 745.4 10 735.6 26 744.7 11 736.4 27 743.2 12 737.6 28 744.6 13 749.8 29 742.7 14 746.3 30 742.8 15 745.4 31 743.2 16 745.5 DAILY UNIT POWER LEVEL FORM INSTRUCTIOQS 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 REPORT-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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.XET NO 50-221 ll lJ I'.i' SURRY II DATE 2-1-1e COMPLET&D BY 0 J COSTELLO AY..E..!J.flQ.£ l2!lI..Id. !l.N.I.l'.. E.QE!..~E. LE.K&L.

!{ONT!-!: JANUARY 1978 AVERAGE DAILY POi-IER LEVEL AVERAGE' DAILY PO~!ER LEVE DAY (MWE-l/ET) DAY (/.fWE-NET) 1 751.3 17 760.0 2 742.3 18 75'.r.2 3 755.6 19 750.3 4 763.5 20 761.5 5 752.e 21 750.5 6 762.1 22 751.3 7 762.0 23. 760.3 8 761.6  :,.. 24 758.5 9 761.0 25 747.5 10 762.6 26 742.6 11 763.2 27 737.1 12 761.e 28 725.4 13 750.4 29 715.2 14 761.2 30 710.7 15 760.4 31 724.3 16 761.2 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS 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 REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL EATIOG OF THE UNrT. THERE MAY BE OCCASIONS WHE~ THE DAILY AVERAGE POWER EXCEEDS 75E 100 o/o LIYE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAG~

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 sign-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. Th~

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. Inc~easing 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.

Janua~y 31 - . This reporting period ends with the unit at 100% power.

UNIT 2 January 1 This reporting period begins with the unit at 100% power.

January 10 - 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..

January 20 - Pressurizer pressure channel 455 was placed in trip mode at 1223 due to instrument drift.

January 25 - At approximately 0001 commenced coastdown phase at end-of-life by reducing power as necessary to maintain Tave*

January 26 Unit at 98% power in coastdown phase .. at ~EDL.

January 28 Unit at 97% in coastdown phase at E.D.L.

January 29 Unit at 96% in coas tdov.7Il phase at E.O.L.

January 30 Unit at 94% in coastdown phase at E.O.L.

I

-TMHARY OF OPERATING EXPERIENCE A (CONTINUED) ~

UNIT 2 January 31 - 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 ob-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 r~actor coolant sys~em (RCS) to the secondary system (SS) through the s~eam generator tubes shall be limited to 0.3 gpm per s~eam generator, as described in the.NRG Safety Evaluation of May 6, 1977. With any steam generator tube leakage gre-ater than this limit the reactor shall be ~rought 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 op~ration 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 Nos~ 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 con-ditions have the following provisions:

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

2. 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 po~l.

AMENDMEJ\TTS TO~CILITY LICENSE OR TECHNICAL SPECIFICATIONS

.., (CONTINUED) ~

(b) The temporary contain~ent 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 5.3~1 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 pre-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 &~D EXPERIMENT JANUARY, 19 79 None during this reporting period.

., e- SURRY POWER STATION CHEHISTRY REPORT JANUARY 1979 T.S.6.6.A.ll PRHlt...RY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS HAXIMUM MINUfUM AVERAGE MAXIMUM MINIMUM AVERAGE

~

Gross Radioact., µCi/ml 5.14E-l 1. 46E-2 3.18E-l 1. 74E-l 4. 78E-2 9 .93E-2 Suspended Solids, ppm 0.3 0.1 0.2 0.4 o-.o 0.2 Gross Tritium, µCi/ml 1. 76E-l 1. 05E-2 9. 91E-2 l.02E-l 7.54E-2 8.46E-2 Iodine-131, µCi/ml 2.00E-2 3.21E-3 8. 51E-3 6.12E-4 3.03E-4 4.20E-4 I-131/1-133 0.7673 0.1669 0.3873 0.1548 0.0508 0.0934 l.l)

Hydrogen, cc/kg 35.6 1.1 22.7 37.9 27.1 32.1 Lithium, ppm 2.77 0*.54 2.10 0.31 0.10 0.20 Boron-10, ppm + 254 99 128 10 0.0 4 (1)

Oxygen-16, ppm 7.700 0.000 0.355 o.ooo 0.000 0.000 Chloride, ppm 0.05 0.05 0.05 0.05 0.05 0.05 pH @ 25°C 7.38 6.12 7.13 8.84 6. 98 7 .68

+ Boron-10 Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES , POUNDS T.S. 4.13.A.8 Phosphate 0.0 Boron 259 Sulfate 1,112 Chromate 0.0 50% NaOH 1,400 Chlorine 0.0 Remarks: (1) Unit fll Shutdown.

• RIPTION OF ALL INSTANCES WHER

• DISCHARGE LU1ITS WERE EXCEED.c.

JANUARY, 1979 Due to impairment of the circulating water system on~the following days the thermal discharge limits were exceeded as noted.

January 3, 1979 Exceeded 17.5°F 6T across station.

January 4, 1979

• Exceeded 15°F 6T across station.

January 28, 1979

• Exceeded 15°F ~T across station.

• Indicates dates when station ~T was <15°F across the station for spmetime during the day.

T'nese ~T 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.

-=-*---* -.#'~ .. :-*:.-....... ---# --------. **-*--. -* - - -- ---- -. -. ________ *---:.  : .:- --

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y UNIT NO. 1

, 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.

--~

e

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

!UNIT NO. 2 FUEL HANDLING JANUARY, 1979 DATE NO OF SIPPED/RECEIVED ANSI NO. 1.1Elv OR SPENT FUEL ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT 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 LINIT~

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

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 u MR TOTDllNTM '"1 Ot/01/79 RC SG 1 RC-8-1A Rf,MOVF./lNST/ILf, PRIM M/INWAYS INSTALLF,D ~!llNl{/IYS 1 9121112'13 lj3lJ

• • 1 01 /07./7q VS C//If.,/,f,fl 1 *V~:*F.-111 f'llN ll/JLTS SLIPPING CllfSCKlW SAT 1 807010600 7 Ol/O'J/7'J 88 /lllTCI/ ESCllI'F: MllllW/IY Ol11NGS RF:PL/JCf,fJ ORINGS 1 817.311700 113 01/0'J /7'J /JS llt11'Cll VALVE LP.AK TllUU RF.PAIRF:O VALVE 1 A12311701 ~3

/JF.'l'I' 'f01'/lf, 527

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Maintenance of Safety Related Systems During Outage or Reduced Power Periods

/

UNIT f!2 Mechanical Maintenance C.

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

., r c

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

I

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(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 u MR TO'J'WNTM l'/.f/W !.f'l'N 1 -11:.: l'-*1 n Ill SCONN /RF.CONN T'MP N7'R ~*on MF.CTI vrsc+RF:C 1 A12t2111JO 7711 01 /O'J./7Q f1'S 8/1/,!JNCF: FUf.fl'+,lfO'fO/l B/l!,/INCF. /JNIT 1 qo10111Joo 7.4 rJ1/0?/7'1 RC /'Ui*ll' 1 /1'C I' *1/J

/IC /'{}/.fl' 1 *UC** 1'

• 111 TJ/lf,/INCP. HJMl'+.'>IOTOTI TJ/lf,ANCF:D MOTO/l+TYJMT' 1 qo1D11601 23 rJt/0?/7" R7.1

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~1aintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #2 .

Electrical Maintenance c

-*-=

- ~ Electrical Maintenance UNIT 2 There was none during this reporting period.

/

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c t". Co * ,)

(

Maintenance of Safety Related Systems During .

Outage or Reduced Power.Periods

( UNIT #1

(

Instrument Maintenance c

Instrument Maintenance UNIT 1 There was none during this reporting period.

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

• rr

~*' UNIT ff2 Instrll!D.ent P.aintenance C.

~-

• • • Instrument Maintenance

. UNIT 2

(

There was none during this reporting period *

.\

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~~ HEALTH PHYSICS JANUARY, 1979 e

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----

• • • • • - \. -\'-- ~ .*.* <"

PROCEDUl-?EVIATIONS REVIEWED BY $TATION~LEAR SAFETY AND OPERATING COHtHTTEE AFTER TIME LIMITS SPECIFIED IN TECirn1CAL SPECIFICATIONS JANUARY, 1979 Number Unit Title Deviation PT-17.2 2 Containment Inside Recirculation Step 5. 3-Change to 11 This Spray Pumps reading should be 110 :.

amps. Step. 6.1-Change to

" The ammeter read-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.