ML20080T806

Monthly Operating Repts for Jan 1984

ML20080T806
Person / Time
Site:	Surry
Issue date:	01/31/1984
From:	Jones V, Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20080T792	List: ML20080T791 ML20080T806 ML20080T821 ML20080T828 ML20080T849 ML20080T865 ML20080T891 ML20080T903
References
NUDOCS 8403020059
Download: ML20080T806 (38)

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{{#Wiki_filter:2 -M m. N-e VIRGDRA ELECTRIC AND POWER COMPANY SURRY POWER frrA'I10N MONTHLY OPERA'11NG REPORT REPORT NO. 84, APPROVED BY: - b 5w i STATION MANAGER I l I l S403020059 840214 PDR ADOCK 05000290 R-PDR ..w-i-..---~..,,.,, - _ _, _,,,,,,,

i s t. 8aeti= A=e Operating Data Report - Unit il 1 Operating Data Report - Unit #2 2 Unit Shutdowns and power Reductions - Unit #1 3 Unit Shutdowns and Power Reductions - Unit #2 4 Imad Reductions Due to Environmental Restrictions - Unit #1 5 Imad Reductions Due to Environmental Restrictions - Unit #2 6 Average DaDy Unit Power Level-Unit #1 7 Average DaDy Unit Power Level-Unit #2 8 Summary of Operating Experience 9 - 10 Amendments to Facility License or Technical Specifications 11 Facility Changes Eequiring NRC Approval 12 FacDity Changes '! hat Did Not Require NRC Approval 13 Tests and Experiments Requiring NRC Approval 14 Tests and Esperiments That Did Not Require NRC Approval 14 Other Changes, Tests and Experiments 15 Ckmistry Report 16 r _ - 4^ *_- of AB Instances Where Thermal Discharge 17 Limits Were Exceeded Fuel Handling 18 - 19 Procedure Revisions 'lhat Changed the Operating Mode 20 Described in the PSAR rz -4A+ of Periodic Tests Which Were Not Compheted 21 Within the Tirse Limits Specified in Technical Specifications g I f _,_m,,._ ..;--......_. _..,.... _.,.._.m.,

11 s t Section M i Maintenance of Safety Related Systems During Outage or 22 -23 new Power Perios - Unit #1 - Mechanical Maintenance Maintennece of Safety Related Systems Dwing Outage or 24 - 25 Reduced Power Periods - Unit #2 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or 26 - 27 Baa==d Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or 28 - 29 Reduced Power Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or 30 - 31 Reduced Power Periods - Unit #1-L strument Maintenance Maintenance of Safety Related Systems During Outage or 32 - 33 Reduced Power Periods - Unit #2 -Instrument Maintenance Health Physics Summary 34 Procedure Deviations reviewed by Station Nuclear Safety and 35 Operating Committee after Time Limits Specified in T.S. 1 { e e S5 e t ....-.m..

Cort:ct2d Cipy OPERATING DATA REPORT DOCTT FO. 50-280 DATE 06 JAI! 84 CO'fPLETED BY Vivian H. Jones TELEPHONE 804-357-3184 9fEEA.EE52 EEd_ME

1. UNIT NAME SURRY UNIT 1

2. REPORTING PERIOD 120183 TO 123183

3. LICENSED THEKfE POLTR (!W")

2441 l """~~~~ ~~~ ~ l C. NAMEPLATE RATING (GROSS frdE) 847,5 l NOTES l

5. DESIGN ELECTRICAL RATING (RET ?!WE) 168

6. !!AXI:RC! DEPENDABLE CAPACITX (GROSS mkt) 811

7. !!AXI;REf DE?ENDABLE CAPACITY (liET ! W) 775

8. IF CHAPGES OCCUR IN CAPACITI RATINGS N/A (ITE*:S 3 THROUGH 7) SI1lCE LAST REPORT, GIVE REASONS

0. POWR LEVEL M WHICH RESTRICTED, IF ANY !!/A (NET !.ST)

10. REASol!S FOR RESTRICTIONS, IP ANT N/A THIS MONTH YR-TO-DATE CUf!ULATIVE

11. HOURS IN REPORTING PERIOD 744.0 8760.0 96648.0

12. NW:BER OF HOURS REACTOR WAS CRITICE 601.1 5181.2 59092.9 13.' REACTOR RESERVE SHUTDO:G HOURS 0.0 0.0 3765.2 ROURS GENERAMR ON-LINE 581.4 5012.5 57867.2 lb. UNIT RESERVE SHUTDCLW HOURS 0.0 n.0 3736.2

16. CROSS TSER'!E ENERGI GEllERATED (?!T.T) 1379905.7 11720014.4 134400614.3 l

17. GROSS EECTRICAL ENERG7 GENERATED (!NH) 431730.0 3713800.0 43319843.0

18. NET ELECTRICAL ENERGY GENERATED (INH) 409212.0 3517273.0 41077736.0 19.: UNIT SERVICE FACNR 78.1 e /*

57.2 */* 59.9 e/=

20..UllIT lVAILABILITY FACTOR 78.1 */*

57.2 e/o 63.1 */*

21. UNIT CAP /.CITX FACTOR (USING MDC NET) 71.0 */=

51.8 ele. 54.8 ele

22. UNIT CAPACITE FACTOR (USING DER NET) 69.8 e/=

51.0 e/* 53.9 e /*

23. UNIT FORCED OUTAGE RATE 21.9 e/*

4. 3 e le 21.6 ele

24. SHUIDO:RIS SCHEDULED OVER NEXT 61210llTHS WINTER !!AINTENANCE 24 10DA (TYPE,DATE,AND DURATION OF EACH)

25. IT SHUT DOWN AT END OF REPORT PERIOD.

ESTIl FATE DATE OF STARTUP'

26. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO Cott!ERCIE OPERATION)

INITIAL CRITICALITI INITIAL E ECTRICITY CW!MERCIE OPERATION m _

i OPERAT.*.?G DATA."EDORT DOCI:ET F0. 50-280 DATE 06 FEB 84 C0'!PLETED Py Vivian H. Jones T E ! ? Hol!E 804-357-3184 OPER_A_TIVG S_T_AT_JS_ -

1. ' UNIT !!/1!E SURRY UNIT 1

2. REPO? TING PERICD.

010134 TO 13184

3.. LICENSED THEi?:AL POTTR (!!KT) 2441 l~ ~

~~~~~~~l

4. NA!!E* LAX RATING (GROSS !NE) 847.5 l ROTES l

5. DEFIGN ELECTRICAL RATIIIG (NET F15T) 788

6. l'AXIb!W: DEPENDABLE CA?ACI ? (GROSS llWE) 811

7. !lAX1?lU'1 DEPENDABLE CA?ACIT! (NET %T) 775

~ 8. IF CHA!!GES OCCUR IN CA?ACITY RATINGS N/A (ITCIS 3 THROUGH 1) SIIlCE LAST REPORT, GIVE REASONS 9.; P0FTR LEVEL M WHICH RESTRICTED, IF AP! N/A .(VET ?!WE)

10. REAS0?:S FOR RESTh?CTIONS, IF ANY N/A THIS MONTH YR-TO-DATE CWiULATIIT 11'. HOURS IX REPORTI??G PERIOD 744.0 744.0 99392.0

12. NU:!BER OF HOURS REACTOR WAS CRITICAL 738.9 738.9

-59531.8

13. REACTOR RESFRVE Sh7lTDOWN ROURS 5.1 5.1 3770.3

14. HOURS GENERATOR ON-LINE 713.5 713.5 53580.7

15. UNIT RESERVE SHUTD0;01 HOURS 0.0 0.0 3736.2

- 16. CROSS THER'!AL E'IERGY GE?.TRAED (INH) 1694149.9 1684149.9 136610454.2

17. GROSS ELEC*RICAL ENERGY GENERATED (?iWH) 539395.0 539395.0 43859238.0 18.; NET ELECTRICAL EVERGE GENERATED (INR) 512425.0 512425.0 41590161.0

19: UNIT SERVICE FACTOR 95.9 e /*

95.9 e /* 60.2 e /*

20. UNIT AVAILABILIT! FACTOR

- 95.9 e /* 95.9 e/o 64.0 * /*

21. ; UNIT CAPACITY FACTOR (USING !!DC NET) 88.9*/*

88.9e/* 55.1 s/=

22. UNIT CAPACITY FACTOR (USING DER NET) 87.4 */*

87.4 e/o 54.2 e /o

23. UNIT MRCED OUTAGE RATE 4.1 * /*

4.1 */* 9.3 ele

24. SHUTD0VRS SCHEDULED OVER NEXT 6 !D!THS WINTER !!AINTENANCE 24 14 Days

'(TXPE,DATE,AND DURATICK OF EACH) L

25. IF SHUT D0VN AT END OF REPORT PERIOD, ESTTHATE DATE OF. STARTUP

26. UNITS IN TEST STATUS.

MRECAST ACHIEVED . (PRIOR N CO'N ERCIAL OPERATION) INITIAL CRITICALITY INITIAL ELECTRICITY COMTERCIAL OPERATION I ! ge-m p- -e r w- -,e- ~~v-- =vvet --wt-9e*"- - y

Ccrrected Copy OPEMTING DATA REPORT DOOFET NO. ' 50-281 DATE 06 JAN 84 COP!PLETED FI Vivian H. Jones TELEPHONE 804-357-3184 ..P.E_RA.. TING S.TA_WS. O i

1. UNIT NA*!E SURRY EEiIT 2 2 }{EPORTING PERIOD 120183 TC 123183 i

3. LICEESED THERIAL POWER (?!WT) 2441 l ~~~~ ~ ~~~~ ~~~ ~ l 5 NA!!EPLATE RATING (GROSS bNE) 847.5 l NOTES l

. Si DESIGN ELECTRICAL RATING (NET !NE) 788

6. !!AXIh7R! DE*ENDABLE CAPACITY (GROSS !!WE) 811

7. ?!AXIUli DEPENDABLE CAPACITY (NET INE) 775

8. 'IT CHANGES OCCUR IN CAPACIM RATIMS N/A (ITC S 3 THROUGH 7) SINCE LAST REPORT, GIVE REASOM '

- 9. POWER LEVEL M WHICH RESTRICTED, IF Alli N/A ' (?iET lM!E) ' 10. REASONS POR RESTRICTIONS, IF. ANY N/A THIS MONTH YR-TO-EMTE CIR!ULATIVE

11... HOURS IN PEPORTI!?G PERIOD 744.0 8760.0 93528.0

12. NER!PER OF HOURS REAC%R YAS CRITICAL 281.8 5896.4 58570.9

'13. REACMR RESERVE SHUTDOWN HollRS 0.0 0.0 0.0 1 -HOURS GE1? ERA."DR ON-LINS 253.3 5731.9 57576.0 '15. UNIT RESERVE SHUTD0is71 HOURS 0.0 0.0 0.0

16. GROSS THER'!AL ENE%7 GENERA?ED (!!WH)

'669954.0 13474526.9" 134715873.0 17e GROSS ELECTRICAL ENERGY GE!!ERATED (.WH)

• 184400.0 4312140.0 43794859.0

18. YlET ELECTRICAL ENE%X GENERATED (!NH) 174571.0 4086139.0 41507060.0 i19.; UNIT SERVICE FAC%R 34.0 * /=

65.4 e /* 61.6 e/*

20. UNIT AVAILABILITY FACTOR 34.0 * /*

65.4 e /* 61.6 ele

21. URIT CAPACITY FAC%R (USING RDC NET) 30.3 e/o 60.2 */*

57.3 e/o 22 UNIT CAPACITY FACTOR '(USING DER NET) 29.8 e/o 59.2 */*

56. 3 * /*

23. : UNIT FORCED OUTAGE RATE 0.0^

2.1 * /* 14.1 */*

24. Sh7lTDOWllS SCHEDULED OVER NEXT 6 !CNTHS SPRING b!AINENANCE 3-16 10 DAY f

- (TIPE,DA%,AND DURATION OF EACH)-

25. IF SHi?I DOWN AT END Oi' REPORT PERIOD, ESTD! ATE DATE OF STARTUP

26. UNITS IN TEST STATUS PORECAST ACHIEVED

.(PRIOR N C0!.B!ERCIAL OPERATION) INITIAL CRITICALITY-IEITIAL ELECTRICIS. COlE45RCIAL OPERATION

OPERATING DATA RE?0RT DOCEET NO. 50-281 DATE 06 FE9 94 CMPLETED RY Vivian H. Jones TEEPHONE 804-357-3184 35EdEE_MS_N.$' 1, UNIT NNIE SURRI UNIT 2

2. REPORTING PERIOD 10184 TO 13184

3. LICENSED THERYAL P0kTR (.%T) 2441 l~~~~~~~~~~~~~~l

4. NA?!EPLATE RATING (GROSS ?NE) ~

847.5 l NOTES l

5. DETIGN ELECTRICAL RATING (NET INE) 788.

6. ?!AXP!U'l DEPENDABLE CAPACITY (GROSS IS!E) 811

7. !!AXD!U'! DEPE!!DABLE CAPACITY (NET !!LT) 775

8. IF CHAi!GES OCCUR IN CAPACIH RATINGS N/A (ITDiS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS

9. PO:!ER LEVEL TO WHICH RESTRICTED, IF ANY N/A (NET 'D'E)

10. REASONS FOR RESTRICTIONS, IF ANT N/A THIS !!ONTH IR-TC-DA2E CU':ULATIVE

11. HOURS IN REPORTING PERIOD 744.0 744.0 94272.0

12. NUl!BER OF ROURS REACTOR WAS CRITICAL 720.2 720.2 59291.1

13. REACTOR RESERVE SHUTDOWll ROURS 23.8 23.8 328.1

14. HOURS GENERATOR O!!-LIVE 711.1 711.1 58287.1

15. UNIT RESERVE SHUROWN ROURS 0.0 0.0 0.0

16. GROSS TEES!AL ENERGY GENERATED (MWE) 1716190.5 1716190.5 136432063.4

17. GROSS ELECTRICAL ENEMY GENEPATED (MWH) 552460.0 552460.0 44347319.0

'19. VET ELECTRICAL ENERGY GENERAED (MVH) 524458.0 524458.0 42031518.0

19. UNIT SERVICE FAC%R 95.6 */*

95.6 */*

61. 8 * /=

20.' UFIT AVAILABILIM FACNR 9 5.6 */* - 95.6 */o 61.8 */e

21. UNIT CAPACIT! FACMR (USIM !!DC NET) 91.0 e/o 91.0 e/o 57.5 e/o

22. UNIT CAPACITY FACNR (USING DER ??ET) 89.5 ele 89.5 */*

56.6 */*

23. LWIT FORCED OUTAGE RATE 4.4 */*

4.4 */* 14.0 */o

24. SRUTDOWNS SCREDULED OVER NEXT 6 !!ONTHS SPRING !!AINTENANCE 3-16 14 Days.

(T!PE,DATE,AND DURATIO:! 0F EACH)

25. IF SEUT DOW AT END OF REPORT PERIOD, ESTIVA2E DATE OF STARMP

26. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR N Coff!ERCIAL OPERATION)

INITIAL CNITICALITY IllITIAL ELECTRICITI C0!2fERCIAL OPERATION t L L.

l t E twit 501U flMntfth At4D WER Rkhl)CTiONS E VI .pAIE Feh_ OG.19R4_, COMrl.ETEE) SY Vivian Jones ILEroRIMONH4 Jamaan TEt.EFIOUNE EXT. 477 j l l 6 3 I ~ W. Deee E. OI "k % gn (,ge,,,,,, g4 i E-can A t.e.cogw ]j Ewns-gi Actiusele ),E el jge Rep se s >u rieweis Rec =cene. f i l 84-1 01-06-84 F 23.0 0 3 84-001/003-0 SJ FCV Reactor trip caused by a voltage spike i from vital bus I while vital bus H was in i trip for periodic testing. The voltage spike was caused when Gaitronics was 2, re-energized af ter maintenance was l performed. i. I s ) 84-2 01-18-84 F 7.5 B 2 84-002/003-0 SJ FCV Reactor was manually tripped due to loss -l 1G R1 of various instrumentation caused by the semi-vital bus sporatically grounding i out. This was caused by a loose wire in j the breaker cubicle grounding out while another wire was being pulled out of ) cubicle. t i l l I 2 3 4 l F: Fawced Rusem: Metlead: Enlillelt G. Instencehnis 5: Schedaded A.Equirnient Fellwe(Esplein) 1 Menwel im reepesellwe of Does g.Melesenance of Test 2 Menwel sceem-Entry $heese fw I.leensee C. Refueling 3-Aulomaele Scism. Event Repwt (LER) File INUREG- ) D.Regwlsimy Resteletiese 4 Otlees (Emplain) 0161) E.Opesetor Tseining & IJcense Enesielneshwi 3 F.Administseelve Enlillele 8. Seine Sowce l G-Opesselonel l'eew (Esplein) 08/77) II.0tlies (Explain) 1

e tW817SIMITDomes AND POTTER RkD4)Ct90NS MEY No. 50-281 (Nil i N A M E Surry 11 ~ .DATE Feh_DE 1924 NTEls my Vivian Jones REFORTMcNyts Januarv -_ 1 ELF.rSIGNE EXT 477 l "}" .[ - Lirassee 4 Conse & Co iecti,e }. Evens - Acelun se Nie., Dste L y, ,,e l. e ,se,_ lle_._e 0 84-1 01-13-84 F 25.2 A 2 84-001/003-0 BA NCV The reactor was manually tripped when 10 RI "A" main steam trip valve failed closed due to a broken air line. f 84-2 01-14-84 F 7.7 A 3 84-002/003-0 LD' PSF Reactor trip caused by a high-high level 84-003/003 O 1G RI in "A" S/G do to "A" feed :egulating valve failing to open. It failed open due 7 f to a broken air line. 1 i i i i 1 2 .1 4 F: Fmted Reason: Meelmd: Enhilill C Inesewcelims a 5: Selieduled A Eigulpment Fellae(Esplein) 1-Memsel Im peepasselon e4 Dses B Melatenance of Test 244ensel serem. Entry Seieets roe Lleensee } C.Refeeling .l Antomsele Scissa. Evens Repose (LER) File (NUREC. ] D Reguleemy Resselcolon 4 Uthee (E erleini 0161) j E Uressem Tesialeig & Ucense Esemineelon F.Adadaliteselve 5 G-Opeseelonel Esem (Esplein) Exhitele 1 Sewie Source l'el17) II-Ushes (Espielse) i I

LOAD RZDUCTIONS DUE TO N'TAL RESTRICTIONS . UNIT NO. 1 MONTE: Januarv,1984 DATE. TIME BOURS LOAD. W. REDUCTIONS. W WH REASON DIONE DURING THIS REPORTDii3 PERIOD 9 t ( l l l l MONTHLY TOTAL

s LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTICNS UNIT NO. 2 MONTE: January.1984

DATE, TIME HOURS-IAAD. MW.

REDUCTIONS. MW NWB REASON e NONE DURING 1 IRS REPORTNG PERIOD. e O e i O l NONTHLY. TOTAL

g;y y j ep .i t \\ DOCEET !!O 50-280 t g r i . t> f, UH12 512!d I i *6 j DATE 2-1-94 ,s s ,L C0!!PLETED BY Vivian H. Jones i [ 'a AVERACE DAILY U!!IT POVER LEVEL

(_.

VO!!THs.IANUARI 64 w f r ^ AVERACE DAILY POTGR LEVEL AVERAGE DAILY POVER LEVEL DA7 UtVE-EET1 DAY (1VE-NCI) ' ~ .e 1 742.4 17 747.0 0 2 740.4-18 329.2 3 744.3 19 509.8 4 746 */' 20 741.2 5 7L7.8 21 744.4 6 ..417.8 22 745.0 y' i, 7 .96.6 23 745.8 g 1 8 619.0 24 746.3 9 748.0 25 747.5 s 20 ' , 742.3 26 741.9 t p n. 11 744.0 27 748.9 kg g 12 { -745.7 28 747.6 3 / 'jl3 746.4 29 748.0 y a f. 14 j 741.3 30 747.0 t 1 n y'/[' 1'S U 745.9 31 745.9 t ' / s. 16 747.3 p j e , [.1

• 8
• -{y ;

s y,+ y ' ' *, j. s" s g,, DAILY UNIT POWER LEVEL 'NMI IRSTRUCTIONS l ON THIS 'FOPJ!, LIST TFiH' AVERAGE DAILY UNIT POWER LEVEL IN !!VE-NET POR EACR DAY IN h THE RE?0RTIN7 HONTE. ThESE FICURES VILL BE USED N PLOT A CRAPH FOR EACH REPORT- -ING MONTR. NOTE TRAT BY USING !!AXDf0M DEPE!:DABLE CAPACITY ?0R THE NET ELECTRICAL RATING OF THE UNIT, THERE~MAY BE OCCASIONS WHEN THE DAILY AVERAGE MVER EXCEEDS THE 100 */* LINE (CR TFE RESTRICTED POWER LEVEL LI!:E). IN SUCR CASES, THE AVERAGE y DAILY UNIT POWER OUTPUT SHEET.SHOULD BE FOOTNOTED N EXPLAIN THE APPARENT ANQ'!ALY. i , ~

e DOCYET NO N0-281 wmf 't4L"Y JI DATE 2-1-84 C0!!?LE"ED PY Vivian H. Jones AVERAGE DAILY UNIT POVER LEtTL l4CNTRs JANUARY 84 AVERAGE T.<ILY POWER LEVEL AVERAGE DAILY P0F!ER LEVEL DAY (HWE-NET) DAY (lfWE-NET) l. 1 744.1 17 742.5 2 746.3 18 741.6 3 747.4 19 740.8 4 745.0 20 745.2 5 733.9 21 745.0 6 745.0 22 744.8 7 741.4 23 742.6 8 743.5 24 740.3 9 747.3 25 740.1 10 746.0 26 739.3 11 745.9 27 739.3 12 745.6 28 739.4 13 390.4 29 740.8 14 19.0 30 741.0 15 644.9 31 740.0 16 743.8 DAILI UNIT POWER LEVEL MRI INSTRUCTIONS 'ON THIS FORf LIST THE AVERAGE DAILY UNIT POWER LEVEL IN.WE-NET POR EACR DAY IN THE REPORTING MONTR. TRESE FIGU3ES WILL BE USED % PLOT A GRAPR MR EACR REPORT-IK MONTR. NOTE THAT BY USIM HAXDIUM DEPEFDABLE CAPACITI POR THE NET ELECTRICAL RATING OF THE UNIT. THERE MAY BE OCCASIONS WHEN THE PAILY AVERAGE POWER EXCETDS THE 100 */* LINE (OR THE RESTRICTED P0kTR LEVEL LINE). IN SUCR CASEE THE AVERAGE DAILY UNIT POWER CUTPUT SREET SHOULD BE POOTNOTED M EXPLAIN THE APPARENT ant %!ALY. _g.

SUMMARY

OF OPERATING EXPE:lIENCE Januarv,1984 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulting in significant non-load related incidents. UNIT 1 01-01-44 0000 This reporting period begins with the unit at 100% power (785 MW's). 01-06-84 1324 Reactor trip caused by a voltage spike from vital bus I while vital bus II was in trip for monthly PT's. 1535 Reactor Critical 01-07-84 1224 Generator on the line, increasing power at 3%/ hour. The "A" feed regulating valve was disassembled and the plug, cage and stem replaced after a 1/2" nut was found. 1638 Unit at 100% power (785 MW's). 01-18-84 0834 Reactor trip caused by manual trip initiated because of oscillating instrumentation caused by sporatic loss i of semi-vital bus due to a loose lead in the breaker cubicle. 1229 Reactor Critical. 1605 Generator on the line, increasing power at 3%/ hour. 01-19-84. .2230 Unit at 100% power (785 MW's). 01-26-84 1047 Reduced load to 92% power (730 MW's), "A" feed regulating valve erratic. 1235 Repaired "A" feed regulating valve, increasing power. 1515 Unit at 100% power (785 MW's). 01-31-84 2400 This reporting period ends with the unit at 100% power (785 MW's). UNIT 2 01-01-84 0000 This reporting period begins with the unit at 100% power (785 MW's). 01-04-84 2355 Commenced load reduction for load following. 01-05-84 0035 Stopped load reduction at 92% power (735 MW's) at the request of system operator. 0410 Commenced power increase.

0500 Unit at 100% power (785 MW's). 01-13-84 1236 "A" main steam trip valve closed, Operator tripped reactor. 01-14-84 0212 Reactor Critical 0615 Reactor trip caused by incorrect lead being lifted and not following procedure while replacing failed relay. 1049 Reactor Critical 1350 Generator on the line. 1356 Reactor trip caused by "A" S/G high-high level due to "A" feed regulating valve failing to open. 1932 Reactor Critical 2137 Generator on the line. Commencingramp at 150MW/ hour. 01-15-84 0145 Holding power at 54% (400 MW's) due to severe vibrations in feed lines caused by broken air lines. 0425 Repaired air lines to feed regulating valves. Commenced power increase. 1040 Unit at 100% power (780 MW's). 01-19-84 1100 The divert valve on IB heater was diverting. Repaired valve and MW's increased to (785 MW). 01-28-84 1045 Commenced unit rampdowndse to vital bus III inverter being out of service. 1102 Stopped ramp at 98% power (770 MW's), inverter repaired. 1108 Commenced power increase. 1130 Unit at 100% power (785 MW's). 01-31-84 2400 This reporting period ends with the unit at 100% power (785 MW's). 10-l

~ AMENDMENTS TO FACILITY IJCENSE OR TECHNICAL SPECIFICA'110NS -The Nuclear Regulatory Commission issued, on January 17, 1984, Amendment Nos. 92 and 91 to the Operating License for Surry Power Static,n, Unit Nos. I and 2, respectively. These ammendments revise the Technical Specifications to add new limiting conditions for operation and surveillance requirements which address engineered safety feature filter systems and the bottled air system for the main control room. -The Nuclear Regulatory Commission issued, on January 17, 1984, Amendment Nos. 93 and 92 to the Operating License for Surry Power Station, Unit Nos.1 and 2, respectively. These amendments revise the Technical Specifications related to fire protection. These changes reflect the upgrading and installation of fire protection systems. .. _ _ _.. _ _ _ - _ _... _.. _ _ -. _ _. _ _.. _.. _... __ _ - _. _.. _ _. ~. _., _ _. _ - - _. _ - _ _ - _, _ _ _ _. _ _.... _ -.

~~ - - - - _. - -.. - - e FACHJTY CHANGES REQUIRING NRC APPROVAL i NONE DURING THIS REPORTING PERIOD. t 4

• t l

FACILITY CHANGE THAT f DID NOT REQUIRE NRC APPROVAL UNIT DC83-23 Removal of Fire Protection Isolation Valve 1&2 This design' change replaced a 4" tap valve located in the fire protection line extending from the main t loop to the personnel change building. The valve was removed and replaced with a spool piece as a result of paving the cask loading / unloading area. The new pad would have made the valve inaccessible. ptmmary of Safety Analysis Fire protection capabilities to safety-related equip-ment was maintained in accordance with Technical i Specifications during the necessary fire main isolation. The modifications to the fire protection system will increase the reliability and versatility of the system. DC82-11B Control Room Habitability: Redundant Control 1&2 Room Isolation Damper 7 The existing control room isolation dampers were not single failure-proof and cannot be practically modified. The dampers were replaced with seis mically qualified

dampers, and additional seismically qualified dampers with seismic supports and dedicated controls and instrumentation was installed in series to satisfy the sir;;1e failure criterion.

Summary of Safety Analysis The modification did not adversely affect normal station operation or the operation of any safety related equipment. The control room pressure boundary was maintained by installing blanking plates in the ductwork during the modification.

A, k e TESTS AND EXPERDfENTS REQUIRING NRC APPROVAL NONE DURING THIS REPORTING PERIOD. TESTS AND EXPERDfENTS THAT DID NOT REQUIRE NRC APPROVAL NONE DURING THIS REPORTING PERIOD. i l 1 e l _14 l

m -w m O C 0 OTHER CHANGES TElfrS AND EXPERIMEN15 i NONE DURING THIS REPORTING PERIOD. 4 4 l I l l, I -.... -- 2

~ '.. VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CHEMISTRY REPORT i JANUARY 19 84 I T.S. 6.6.3.d PRIM COON UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE +* -1 +* -1 2 -1 3ross-Radioact., uCi/ml 3.18E 6.45E 1.8BE 3.00E 1.08E '.75E Suspended Solids, ppm 0.0 0.0 0.0 0.0 0.0 0 ~1 ~ ~ ~ ~ ~ Gross Tritium, uci/ml 1.38E 4.02E 7.6BE 3.40E 6.51E 1.57E Iodine 131, ECi/ml 1.20E* 3.80E 2.78E" 5.77E 3.PDE 2.27E ~4 ~ ~ j 131 133 L,,.. I /I .86 .39 .55 .43 .07 .1R IAI Hydrogen, cc/kg 40.5 23.2 29.2 44.1 26.0 36.2 I Lithium, ppm 1.23 .78 .94 2.02 1.27 1.45 Boron-10, ppm

• 125 69 85 216 138 153

Dxygen, (D.O.), ppm 40.005 40.005 4 0.005 2 0.005 40.005 40.005 Chloride, com 4 0.05 20.02 0.02 40.05 40.02 0.02 pH 0 25*C 6.90 6.65 6.81 6.79 6.53 6.66

• Boron-10 = Total Boron x 0.196 l-NON-RADIOACTIVE CHEMICAL (C)

RELEASES, POUNDS T.S. 4.13.A.6 Phosphate Boron. 110 Chromate 0.0 sulfate-Chlorine nn -50% NaOH l~ REMARKSr (A) Operations n6tified Chenistry r+t---- --.ded increase in NCF eressure. l (B) Litbi- =Mitians =da to Urtit 1r 300r==. 1/6; 325 c== 1/7e 260,== 1/7, 227 esrw 1/19s 200 - 1/20. Ca* inn bad c1=nad in service on Unit I for lithite re-vair 1/sel/13 Lithian additons made to (kiit 2: 500 cans 1/13; 400 cans 1/14; 800 cans 1/14r 150 r== 1/24r -130 cas 1/25. Ca+4cvs had n1M in service on Unit 2 fne lithium renvair 1/2r 1/3r 1/Er '1/6; 1/Br 1/9r 1/10r 1/12,1/17,1/1Re ' r 20, 1/22, 1/21, 1/26, 1/24. Ic1 h 1s,u 1= nf these chemicals should produce no advere envirornental impact.

sm 9 LMdFIf0N OF ALL DISTANCES hHERE TIITMAL DISCHARGE LIMITS WERE EXCEEDED NONE DURDIO THIS REPORTING PERIOD. O f D t s* e...

FUEL HANDLING UNIT 1 January,1984 i NONE DURING T)flS RhPORTING PERIOD. t' e 0 eD _

FUEL HANDLDIG UNIT 2 January,1984 s 9 NONE DURING THIS REPORTING PERIOD. e O f 9* 4.. _ - _ _ _ _ _ _ _ _ - _ _ _. _ _ _.-_ - _ _

PROCEDURE REVISIONS THAT CHANGED THE OPERATDfG MODE DESCRIBED IN THE FSAR NONE DURING THIS REPORTDIG PERIOD. l l l l 4 t e* I b i. i le_.._._ c'

y 0 0 DESCRIPMON OF PERIODIC TESIS WIUCH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS NONE DURING THIS REPORTING PERIOD. e t t a .,s .-s s a 4 MADITENANCE OF SAFETY RELATED SYErrEMS DURDIG OUTAGE OR REDUCED POWER PERIODS UNrrNO.1 MECHANICAL MAINTENANCE O 4 0 9*..... -. -.-. ~.....-. -. -. --.-..

_6-.. _ -.. .... _.-..... g g. 9 .. pg f l ll ' NAINTENAnt.10F SAPCTT.. MLit.R.D. 81 stint Drnt!M Ct97. ACE.CR JE.8.tC..tB. N.e.t._R. 98R.10.tur.... (V MPTe NECM \\ .. yy.. ~.. y..-..---. (o VtPERP NR .) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~ ~ 01/05/P% FV ' F5IIf "1-5f-21 ~ ~ ~ Lhi N fifid5df (^ CLKAND FALFEeMP StT 312160902 e 01/01/8% CW PtsfP..,,,1-CW-P,1 A. ,, CPAKCF off. JN Pt#fP,,,,,, __ _,,,, _, t CNA KPD CIL 312291100 ( 01/01/9% M VALVE NV-NS-102M VAT.VE 1. EARS TWRtf M11. ACE CA!. WETS IN VALVE 312291051 ~ ~ ' ~ ~ ' ~ ~ ' ~ ~' 01/07/9% ftT FALFE 5.i-Id-lotj FALkI LTJits f*IMil~ ( REPLACED CASKETS IM VAT.VK 312291050 si 01/01/9% TV VALVR 1-9Ef-21 PtMIARITE' ~ ~ ' ~ ~ ~ ~ ^~~ " ~~ PSEED PLM l# sorf ' ~ ~ ' ' ' ~ ~ "~401011220 ' i (. 01/19/9% C3 FALFE l-CS-30 PACKlW LEAE AWilST Jt9WFE CatPD ); 1 ANITTED PACKIM %01051006 ~ ~ f "~ ~~ 01/19/9% ST FJf,kf i~3fM ~~~ l'4CTIUC lili-JhlO5f 1: ( ant!STED PACK 1M %0105100% 01/t9/Se FC FAT.FE' ' ~ ~1-7C-0%4 PT.AK E LEAKS ~ '~' TTCllTEN@ LKAK %Q1051003 ( 01/19/9% RC' VALVE t-X-OSS PLANCE LEAKS t. I TIC 7/TETFD LEAK 401051002 U 01ft9/9% St V4l.Vb' ^ ~~1-5545' ~ ~ ' PACKlM libit~hnitISf dllhI'bWCEtib~~" ~ '~ ~~ ' ~ ' ~ ' ' ' (*S ANCISTfD PACKlK 4010511%1 } PACKIM LEAK 01/19/9% St VALVE 9/A ~ ~ 312291650' ~ ~ ~ " " ' ' ~ ~ " ' ~ ~ ~ ~ AD17%TED l'JCKIAC ' ~ ~~ ^ ~ ~ ( 01/19/9% KI FALFK 1-3f-11 1-Sf-11 #8 PLACE AtrT 04 JRdstMPEEL i REIMSTAl.1.Et> ht!T 312290910 ~' ' " " ~ ~ ~ ~ ~ ~ ' ' ' ~ ' * *

• 01n9/9m rs viL>t* "iti-iii.'16tfr ~ noor su inoiritT 1.tM

( NOT 7U40tp rf.AKE 80LTS 401121959 ) g 01/25/84 FW Valve FCV-FW-1478 Install New Cage t-. ( Install' Hew Cage 401061410 l t b f. (. t s l W W d

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• 2:19 Mi-. PAGE 7 -~ ~

g g teTTs 2 .l~ l NAIN1 TRANCE Of SAWfi NEA?ltD SFSTIFt3 NREM CtrTACE OR MilDCED ltMtR NRiotG DEPTs 195T 2 l 1 nsTstarDT srs cw. mano.. . stemnT. t ? t 01/13/04 ST. NtfTR 925, --- - NETER NRADS 30 PSIC-RIMER -- -- - l 18PICATToms AM #0fpfAL 4010A1721 OS/1%/*% BD FITT!N PE-nO-202A SVACEIDW TITTIM l INSTATLED M8lf !!TTIK - 6011 % t 511 -- 01/15/0% RP IMPIR ALL FOM D0 ROT IWOICATE LEVEL PEPLAND F4 AND ANIRSfTD K-12 4011500%5 t 4 . I ^ l t t e I ) tb ( ** 1' e 4 I s 1 i I i l s ! l v. I { ( 1 ( l ] l l .I 4 i 8 l = %no M NSIIRRYa t

CerrIcted Copy . = HEALT.7 PHYSICS January,1984 There was no single release of radioactivity or radiation exposure specifically asociated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20. l i- --.psc--- m-r re-v -.-,v- ,e-, yy. - --.,._.

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g; PROCEDURE DEVIATIONS REVIEWED LT STATION NUCLEAR SAFETY AND OPERATING COMMITTEE AFTER TIME LIMITS SPECIFIED DI TECHNICAL SPECIFICATIONS e..

1. 1. [

[ January,1984 Date Date SNSOC Procedure No. Unit Title Deviated Reviewed OP-1B - 2 Containment Checklist 12-20-83 01-12-84 OP-14A 2 Valve Sheet Checkoff Residual Heat 09-18-83 01-20-84 Removal 5 l y W f i 1 r. s ,1 s. J I Y. a Y f. -s-s. / / >\\ F 3 g 4' l' j.

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