ML20087M568

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Monthly Operating Repts for Feb 1984
ML20087M568
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/29/1984
From: Stewart W, Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Haller N
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
142, NUDOCS 8403300060
Download: ML20087M568 (44)
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VINGINIA ELECTRIC AND Powsu COMPANY Ricarwoxn,'/INGINIA 200 61 w.L.sinwimr x$*,"j"o!",'l""!,, 'Sareh 15, 1984 Mr. N. M. Haller, Director Serial No. 142 Office of Management and Program Analysis N0/WDC:acm U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 DPR-37

Dear Mr. Haller:

Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos. I and 2 for the month of February, 1984. Also, attached are the corrected pages of the Unit Shutdowns and Power Reductions for the Monthly Operating Report of January, 1984.

Very truly yours, f i kJ' W. L. Stewart Enclosure (3 copies) cc: Mr. R. C. DeYoung, Director (12 copies)

Office of Inspection and Enforcement Mr. James P. O'Reilly (1 copy)

Regional Administrator I Region II j Mr. D. J. Burke NRC Resident Inspector Surry Power Station l

8403300060 840229 DRADOCK05000g

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I VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 84-02 STATION MANAGER l

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's t Section Page Operating Data Report - Unit #1 1 Operating Data Report - Unit #2 2 Unit Shutdowns and power Reductions - Unit #1 3 Unit Shutdowns and Power Reductions - Unit #2 4 Load Reductions Due to Environmental Restrictions - Unit #1 5 6

Load Reductions Due to Environmental Restrictions - Unit #2 Average DaDy Unit Power Level- Unit #1 7 Average DaDy Unit Power Level- Unit #2 8 Summary of Operating EWence 9 Amendments to Facility License or Technical Specifications 12 PacDity Changes Requiring NRC Approval 13 FacDity Changes 'Ihat Did Not Require NRC Approval 14 Tests and Experiments Requiring NRC Approval 15 Tests and Experiments 'lhat Did Not Require NRC Approval 15 Other Changes, Tests and Experiments 16 Chemistry Report ,

17 Description of AH Instances Where 'Ihermal Discharge Limits Were Exceeded 18 Fuel Handling 19 Procedure Revisions 'Ihat Changed the Operating Mode Described in the FSAR 21 hStian of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 22

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s Section Page Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1- Mechanical Maintenance 23 Maintenance of Safety Related Systems During Outage or Reduced Power Periodi- Unit #2 - Mechanical Maintenance 26 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1- Electrical Maintenance 28 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit # 2 - Elect ical Maintenance 31 Maintenance of Safety Related Systems Dwing Outage or Reduced Power Periods - Unit #1-Instrument Maintenance 33 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 -Instrument Maintenance 35 Health Physics Summary 37

- Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee after Time Limits Specified in T.S. 38

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l 'c OPERATING DATA REPORT

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DOCKET NO. 50-280 DATE 07 MAR 84 COMPLETED BI V' M' 0 ***

TELEPHONE 804-357-3184 SEEA_A_ E E S$dIEE

1. UNIT NA4E SURRY UNIT 1
2. REPORTING PERIOD 20184 TO 22984
3. LICENSED TRERMAL POWER (MWT) 2441 l~~~~~ ~~ ~l
4. NAMEPLATE RATING (GROSS MWE) 847.5 l NOTES l S. DESIGN ELECTRICAL RATING ' NET MWE) 788
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) 811
7. MAXIMUM DEPENDABLE CAPACITY ' NET MWE) 775
8. IF CHANGES OCCUR IN CAPACITY RATINGS N/A (ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
9. POWER LEVEL TO WHICB RESTRICTED, IF ANY N/A (NET MWE)
10. REASONS FOR RESTRICTIONS IF ANI N/A THIS MONTH XR-TO-DATE CUMULATIVE
11. ROURS IN REPORTING PERIOD 696.0 1440.0 98088.0
12. NUMBER OF ROURS REACTOR WAS CRITICAL 571.8 1310.7 B04(13.6
13. REACTOR RESERVE SHUTDOWN ROURS 4.2 9.3 3774.5
14. BOURS GENERATOR ON-LINE 566.5 1280.0 59147.2
15. UNIT RESERVE SRUTDOWN HOURS 0.0- 0.0 3736.2
16. GROSS THERMAL ENERGY GENERATED (MWH) 1342137.5 3026287.4 137952591.7
17. GROSS ELECTRICAL ENERG7 GENERATED iMWR) 433030.0 972425.0 44292268.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 411451.0 923876.0 42001612.0
19. UNIT SERVICE FACTOR 81.4 e/o 88.9 */* 60.3 e/o 20 UNIT AVAILABILITY FACTOR 81.4 */e 88.9 */* 64.1 e/*
21. UNIT CAPACITY FACTOR (USING MDC RET) 16.3 ele 82.8 */* 55.3 */o
22. UNIT CAPACITY FACTOR (USING DER NET) 75.0 */* 81.4 */* 54.3 */o
23. UNIT PORCED OUTAGE RATE 1.6 */* 3.0 */o 21.3 */o
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS WINTER MAINTENANCE 24 14DA (T!PE,DATE,AND DURATION OF EACB)
25. IF SRUT DOWN AT END OF REPORT PERIOD, 03-09-84 ESTIMATE DATE OF STARTUP
26. UNITS IN TEST STATUS FORECAST ACHIEVED l

(PRIOR 20 009fERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY C09fERCIAL OPERATION

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OPERATING DATA REPORT DOCKET NO. 50-281 DATE 07 MAR 84 ]

COMPLETED BY V. M J0nes TELEPHONE 804-357-3184 OPERATING STATUS

1. UNIT NAME SURRE UNIT 2
2. REPORTING PERIOD 20184 TO 22984
3. LICENSED THER4AL POWER (MWT) 2441 l ~ ~ ~ ~ ~~ ~ ~ ~ ~ l
4. NAMEPLATE RATING ' GROSS MWE) 847.5 l NOTES l
5. DESIGN ELECTRICAL RATING (NET MVE) 788
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MVE) 811
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 775

' 8. IF CHANGES OCCUR IN CAPACITY RATINGS N/A (ITDIS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS

9. POWER LEVEL TO VHICH RESTRICTED, IF ANY N/A (NET MWE)
10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS MONTH YR-TO-DATE CUMULATIVE
11. HOURS IN REPORTING PERIOD 696.0 1440.0 94968.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL 696.0 1416.2 59987.1
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 23.8 328.1
14. HOURS GENERATOR ON-LINE 696.0 1407.1 58983.1
15. UNIT RESERVE SHUTDOWN HOURS 00 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 1659218.2 3375408.7 138091281.6
17. GROSS ELECTRTCAL ENERGY GENERATED 'MWH) 530760.0 1083220.0 44878079.0
18. NET ELECTRICAL ENERG7 GENERATED (MVH) 503388.0 1027846.0 42534906.0 19 UNIT SER;7CE FACTCR 100.0 e/o 97.7 e/o 62.1 e/o
20. UNIT AVAILABILITY FACTOR . 100.0 =/= 97.7 e/e 62.1 e/e
21. UNIT CAPACITY FACTOR (USING MDC NET) 93.3 ele 92 1 e/o 57.8 e/o
22. UNIT CAPACITY FACTOR (USING DER NET) 91.8 */* 90.6 e/* 56.8 */*
23. UNIT FORCED OUTAGE RATE 0.0 2.3 ele 13.8 ele
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTRS SPRING MAINTENANCE (TYPE,DATE,AND DURATION OF EACH) 3-16 14 DAYS
25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATE DATE OF STARTUP
26. UNITS IN TEST STATUS FORECAST ACHIEVED iPRIOR 20 COM!VERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITI .

CONVERCIAL OPERATION l

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' Corrected Copy for Janusry- ,

e f)oCREt NO. 50-280 ,

Unit Siluil) OWNS ANI)l'owEn Riii)DC160NS llNIT NAME Surry 1

.IPAT E Feb.OG.1994_

COMrl.ETEI) BY Vivian .iones REPORT MONill January 1El.ErilONE EXT. 477 4.

" Cown A Cmeeceive t.lcensee g4

}{g No. Date E Eb Event d Aethm in .

ici O ID [ jdi Repoel # j l'eevent Recuesence 84-1 01-06-84 F 23.0 0 3 84-001/003-0 SJ FCV Reactor trip caused by n voltage spike

- from vital bus I while Ch,11 OTO T was in

! trip for periodic testing. The voltage spike was caused when Gaitronics was 2, re-energized af ter maintenance was

' . performed. Future Galtronics Mainte-

! nance will be restricted.

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84-2 01-18-84 F 7.5 B 2 84-002/003-0 SJ FCV Reactor was manually tripped due to loss IG RI of various instrumentation caused by the semi-vital bus sporatically grounding out. This was caused by a locse wire in the breaker ciabicle grounding out while another wire was being pulled out of cubicle. The loose wire wris tightened.

4 I J '4 I 2 .

Mellpul: Enlelt G. insieucchins F: Fewced Reason:

1 Menwel for Feepseethniof Dass 5: Scliedisled A Eigvismient Fellwee(Emplain) 2-Menwel scesm. Entry Slicest Im Licenice B Malatenance of Test Event Repmt (LER) File (HURLG-C Refweling J Automatic Scism.

l 4-Other (Emplain) 01619

1) Regoleimy Restelettem .

1 - E.Opersone Teelning & IJcense linemineihnt -

3 1

F-Adadnistiselve EslAle I .Same Source G Opeseelonel Eseve (F.nplein) l rol17) Il-Otties (Emplain!

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. r 50-280

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Surry 1 -

UNlt Sh0Tl) OWNS ANI) POWER RtDUCTiONS E

.DA1E _ 03-05-84 COMPLETED Ry Vivian II. Jones REFOnt MONill FEB.,1984 1El.Eril0NE Ext.477

" I **3" "I Cowse A Cmiscieve E- (.lcensee g4 ,

Aethe la Ha. Date N. OI Event - gi reevent Recuseence

eD h g Repal # => O g' 3 84-003-00 LD PSF Reactor trip caused by "A" S/G 10w 84-3 02-06-84 F 9.3 A level with a steam flow / feed flow mismatch. The initiating event was l a loss of control power to Unit 1 polishers and the subsequent re-energizing of the tripped breaker.
&' Re-energizing control power caused i -

, the AOV's for the polish beds to go j closed causing a reduction in feedwater flow.

The corrective action was to replace the breaker that tripped causing a loss of control power. Also a sign will be posted by the breaker stating

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that "Do not re-energite breaker until j

polish bldg. is bypassed."

Shutdown for snubb'er outage and repairs.

! 84-4 02-24-84 S 120.2 II 1 4

. 3 1 2 Method: Emidbit G. insiewcikms F:l'enced Ressmi: fm roepeesWon of Dses 1 Menwel 5: Scheduled A-Equipment Fellme(Emplain) Entry Sheets Im t.lermee 2-Menwel Sceem. Event Repnt (LER) File INUREG.

" 5-Meintenance of Test 3 Autonistic Seese.

J C. Refueling 4 Othee (Emplain) 0161)

D Regulatmy Restelethm l E-Opeseen Tosining & Ucense Eneminetkne 5 i

F.Adadnistteilve Eshible I .Ssme Souece G-Opeestkmal Eveve (F.nplein)

II.Othes (Emplain) l'il .'7 )

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  • dorrg'e ttd Copy for Janurry , .

I'OCKETNO. 50-281 .

(WiliSilUTHOWNs AND rotfER RkDUCllONS UNIT NAME Surry 11 _,

  • DATE _ Feb 0G: 19R4

$ N t. EYED p Wan Jonn REPORT MoNill .Jannisary 1ELEril0NE EXT. 477

" 3" "b Cause A twiecilve

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Dia. . Deee E } '{g

- Event

  • Acehm su -

U w hevent Recmeence

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1 84-1 01-13-84 F 25.2 A 2 84-001/003-0 DA NCV The reactor was manually tripped when IG RI "A" main steam trip valve failed closed due to a broken air line. The air line was replaced.

84-2 01-14-84 F 7.7 A 3 84-002/003-0 LD' PSF Renctor trip caused by a high-high level h -

84-003/003.0 IG RI in "A" S/G due to "A" feed regulating valve failing open. It failed open due to f

a broken air line. The air line was re-placed l

t i 3 4

' I 2 Meshal: Enhlt,Il c. Innuncilims F: Fmred Messun: Im peepsesel m of Dans A.Estwipment Fellme(Emplain) .1-Manwel 5: SeheduleJ 2-Manuel 5ceam. Entry $heets foe tiemee

ll. Maintenance of Test Evene Repms (l.ER) File (NUREG-C.Refwelbig 3 Automsele Scenen.

, 4 Oshes (Esplein) 0161)

D.Regwisioey Restelcolon E.Opeesene Training A IJcense Essednethm 5

- F.Adadnlieneelve ' 15hible i .Same Source G.Opesselunel F.erm (Emplain) l II.Othee (Espisles) r8/77)

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DOCKET NO. 50-281 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Surry 2 -

  • DATE 03-05-84 -

COMPLETED BY Vivian II. Jonen REPORT MONTIf FEB.1984 TELEPHONE Ext.477

.! E $j$ ]YgM Licensee E* E"t b

Cause & Corrective Action to No. Dase h 3g Event 5i E

$5 sE j 375 g Repori # Jyv fu Prevent Recurrence d

84-3 02-11-84 S 0 II 1 Power was reduced to 65% (505 MW's) for load following.

84-4 02-12-84 S 0 H 1 Power was redisced to 76% (615 MW's) for load following. i 02-14-84 S ,0 Power was reduced to 64% (500 MW's) .

84-5 .il 1 for load following.

02-15-84 S 0 H Power was reduced to 64% (500 MW's) 84-6 1 for load following.

84-7 02-17-84 S 0 II 1 Power was reduced to 64% (500 MW's) for load following.

02-18-84 0 Power was reduced to 64% (500 MW's) 84 S li 1 for load following.

84-9 02-19-84 S 0 li 1 Power was reduced to 64% (500 MW's)

J for load following.

' 3 4 l 2 Method: Exhibit G . Instructions F: Forced Reason: for Preparation of Data A Equipment Failure (Explain) 1 Manual

. S: Scheduled 2 Manual Scram. Entry Sheels for Licensee B Maintenance of Test Event ReporI (LER) File (NUREG-C. Refueling 3 Automatic Scram.

4-Other (Emplain) 0161)

D Regulatory Restriction E-Operator Training & License Examination -

5 F Administrative Exhibii 1.Same Simree G Operational Error (Explain) l'8/77) llether(Explain)

4 LOAD REDUCTIONS DUE TO ENVIRONMENTAL PISTRICTIONS 9

UNIT NO.1 MONTE: February,1984 DATE, TIME HOURS- LOAD, W REDUCTIONS, MW WE REASON NONE DURING 1111S REPORTING PERIOD.

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l LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.2 MONTH: February,1984 DATE, TDE HOURS- LOAD, MW REDUCTIONS, MW MWH REASON NONE DURING T ilS REPORTIRG PERIOD.

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MONTHLY TOTAL

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DOCKET NO 50-280 1 UNIT SURRY Z

  • DATE 3 88:

COMPLETED By V. M. Jones AVERAGE DAILY UNIT POWER LEVEL MONTH: PEBRUARY 84 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l DAY (MWE-NET) DAY tMWE-RET) \

1 745.7 16 746.6 2 746.3 17 748.5 3 745.8 18 747.1 4 748.6 19 743.7 5 750.8 20 745.5 6 586.3 21 744.7 7 249.6 22 744.6 8 715.6 23 743.7 9 746.0 24 662.8 10 747.6 25 0.0 11 745.3 26 0.0 12 746.2 27 0.0 13 746.2 28 0.0 14 749.4 29 0.0 15 747.1 DAILY UNIT POWER LEVEL FOM INSTRUCTIONS ON THIS FOR>f, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN NWE-NET POR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED M PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY POR THE NET ELECTRICAL RATING OF THE UNIT, THERE MAI BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 */* LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTROTED N EXPLAIN THE APPARENT ANONALY.

DOCKET NO 50-281 UNIT SURRY II DATE 3-1-84

. . COMPLETED BY v. n. Jones AVERAGE DAILY UNIT POWER LEVEL MONTH: FEBRUARY 84 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWE-NET) DAY (MWE-NET) 1 741.0 16 682.4 2 738.4 17 695.2 3 739.3 18 722.9 4 740.2 19 657.5 5 740.7 20 668.5 6 739.5 21 735.0 7 736.8 22 737.3 8 738.0 23 735.0 9 738.6 24 737.6 10 738.2 25 736.3 11 738.2 26 739.3 12 679.8 27 735.6 13 723 8 28 738.3 l

14 707.0 29 738.5 15 675.8 DAILY ' UNIT POWER LEVEL FOM INSTRUCTIONS ON THIS FOM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET NR EACH DAY IN THE REPORTING MONTB. THESE FIGURES WILL BE USED N PLOT A GRAPH FOR BACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT. THEM MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 */* LINE 'OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANQtALY.

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SUMMARY

OF OPERATING EXPERIENCE FEBRUARY,1984 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

Unit One 02-01-84 0000 This reporting period begins with the Unit at 100% power (785 MW's).

02-06-84 1847 Reactor trip caused by "A" S/G low level with a steam flow / feed flow mismatch. The initiating event was the condensate polishing demineralizer AOV's closing when control power was restored following a spurious breaker trip.

2300 Reactor critical.

02-07-84 0404 Generator on'the line, increasing power at 3%/ hour.

02-08-84 0815 Unit at 100% power (785 MW's).

02-24-84 1800 Commenced unit ramp down for snubber outage.

2347 Generator off the line.

02-25-84 0000 Reactor shutdown.

0623 RCS < 350*F/450 psig.

1358 RCS < 200*F.

2250 Declared an " Unusual Event" due to vent-vent activity

, > 100% of T.S.

2320 Secured from " Unusual Event," actual release was 79%

of T.S., release was from overhead gas system into the 1 auxiliary building while draining stripper.

02-28-84 0650 RCS is degassed, depressurized RCS, commenced draining to mid-nozzle.

1551 RCS is at mid-nozzle.

02-29-84 1350 Commenced RCS head evacuation.

2400 This reporting period ends with the unit at cold shutdown and at mid-nozzle with head evacuation in progress.

Unit Two 02-01-84 0000 This reporting period begins with the unit at 100% power (785 MW's).

02-11-84 2355 Commenced power reduction for load following.

02-12-84 0225 Stopped ramp at 69% power (505 MW's).

0508 Commenced power increase.

0740 Unit at 100% power (780 MW's).

2340 Commenced power reduction for load following.

02-13-84 0125 Stopped ramp at 76% (615 MW's) due to vibrations in feedwater system, increasing power to stabilize plant.

0258 Unit at 92% power (730 MW's), plant stabilized and holding.

0340 Commenced power increase.

i 0429 Unit at 100% power (780 MW's).

02-14-84 0030 Commenced power reduction for load following.

0202 Stopped ramp at 76% power (615 MW's) due to oscillations in feedwater system.

l 0220 Commenced power increase.

0258 Stopped ramp at 84% power (650 MW's), plant stabilized, tightened packing on "B" FRV.

0308 Commenced power reduction to check for vibrations.

0340 Stopped ramp at 74% power (588 MW's), no vibrations.

0436 Commenced power increase.

0639 Unit at 100% power (780 MW's).

2328 Commenced power reduction for load following.

02-15-84 0155 Stopped ramp at 64% power (500 MW's).

0509 Commenced power increase.

0750 Unit at 100% power (780 MW's).

2341 Commenced power reduction for load following. ,

l 02-16-84 0155 Stopped ramp at 64% power (500 MW's).

0424 Commenced power increase.

0648 Unit at 100% power (780 MW's).

1430 Commenced power reduction due to 2-II inverter removed from service for repair and ' vital busses II and IV are cross-tied.

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1509 Stopped ramp at 88% power (740 MW's), inverter returned to service.

1700 Unit at 100% power (780 MW's).

02-17-84 0008 Commenced power reduction for load following.

0227 Stopped ramp at 64% power (500 MW's).

0405 Commenced power increase.

0627 Unit at 100% power (780 MW's).

02-18-84 0145 Commenced power reduction for load following.

0245 Stopped ramp at 84% power (680 MW's).

0448 Commenced power increase.

0555 Unit at 100% power (780 MW's).

2305 Commenced power reduction for load following.

02-19-84 0116 Stopped ramp at 64% power (500 MW's).

0530 Commenced power increase.

0750 Unit at 100% power (780 MW's).

2255 Commenced power reduction for load following.

02-20-84 0105 Stopped ramp at 64% power (500 MW's).

0515 Commenced power increase.

0731 Unit at 100% power (780 MW's).

02-21-84 0130 Commenced power reduction for load following.

0203 Stopped ramp at 92% power (730 MW's).

0226 Commenced power increase.

0316 Unit at 100% power (780 MW's).

02-23-84 0052 Commenced power reduction for load following.

0150 Stopped ramp at 84% (680 MW's).

0156 Commenced power increase.

0300 Unit at 100% power (780 MW's).

02-29-84 2400 This reporting period ends with the unit at 100% power (780 MW's).

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AMENDMENU TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS NONE DURING THIS REPORTING PERIOD

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FACILITY CHANGES REQUIRING NRC APPROVAL NONE DURING THIS REPORTING PERIOD 1

l FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL UNIT j 1

DC82-02 Control Room Exhaust Fan Circuit Modification 1&2 l l

This design change modified the circuitry for Control Room Exhaust Fan VS-F-15 to prevent the fan from starting after a Safety Injection signal reset until it is started manually.

Summarv of Safety Analysis The modification prevents the exhaust fan from running against the closed exhaust valve MOV-VS-103B. The change makes the operation of this fan consistent with the design basis of ESF equipment.

DC82-11D Sodium Analyzers - Control Room Habitability 1&2 This design change replaced four sodium analyzers which do not require dimethylamine gas or any other toxic reagents. The replacement analyzers also have identical power and signal ratings as the original analyzers.

Summary of Safety Analysis

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The modification does not affect the operation of any safety-related equipment. This replacement eliminates the probability of a hazard due to the leakage of dimethylamine gas.

l TES'IS AND EXPERIMENTS REQUIRING l NRC APPROVAL l NONE DURING THIS REPORTING PEltIOD.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL NONE DURING THIS REPORTING PERIOD

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OTHER CHANGES, TESTS AND EXPERIMENTS NONE DURING THIS REPORTING PERIOD i

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CHEMISTRY REPORT February 19 84 T.S. 6.6.3.a PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM- MINIMUM AVERAGE FAXIMUM MINIMUM AVERAGE

-1 -1 ~

~1 Gross Radioact., uCi/ml 3.18 + 2.07 1.45+ 4.28 3.26 1.28 Suspended Solids, pom 0.0 0.0 0.0 0.0 0.0 0.0

-1 -2 -2 3.50

-1 1.78

-1 -1 Gross Tritium, uCi/ml 1.34 6.70 9.05 2.71 Iodine 131, uCi/ml 1.44+ 4.27 ~2 4.09 -1 5.R1~4 6.47 -5 3,,,-4 1

131 /I 133 .82 .44 .63 0.41' .07 0.18 Hydrogen, cc/kg 32.8 4.3(A) 18.3 49.3 33.2 40.5

!ithium, ppm 1.95 .59 .99 1.dP 1_96 1 1A Boron-10, ppm

  • 307 54 44 las 17n 17p Oxvgen, (D.O.), ppm 4 .005 <.005 <.005 < .005 < .00s < _ nn; Chloride, ppm 4.02 4 .02 4 .02 c .02 4 .02 < . 02 pH 9 25'C 6.88 6.21 6.72 6.81 6.56 6.65
  • Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (C)

RELEASES, POUNDS T.S. 4.13.A.6 Phosphate -

Boron. 156 Sulfate -

Chromate 0.1 50% NaOH -

Chlorine 0.0 REMARKS: (A) Unit shutdown on 2/24/84 for sprina outaae. Degassing emoleted on 2/28/84 (B) Lithiun =AAitions mama to Unit 1: 260ms. 2/1 200ms. 2/3 220r==. 2/4 1123ams.

2/7; 165ams. 2/8; 160ams. 2/9; 210r==. 2/24r 206 Mr== . 2/25,catirm ha planaa in earuirw

~

I on Unit 1 for Lithiun reoval; 2/14; 2/18; 2/19; 2/20; 2/21; 2/23. Unit 2 Lithium maa-itions; 115ams. 2/12; 225ms. 2/14; 178ams. 2/15; 200r==. 2/16r 150rma. 2/17, ??ne==.

2/19; Cation Bed in serview on Unit 2 fnr Lithim herwal e?/?,?/110/?A fr) h 1===1= nf these chemir al a shonla ornanew nn navora. .mri .. ...._ .t=1 4 -=r+ _

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. DESCRIP110N OF ALLINSTANCES WHERE

- THERMAL DISCHARGE LIMITS WERE EXCEEDED l

l NONE DURING THIS REPORTING PERIOD

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. FUEL HANDLING Unit 1 i NONE DURING THIS REPORTING PERIOD

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FUEL HANDLING Unit 2 NONE DURING THIS REPORTING PERIOD I

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PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR NONE DURING THIS REPORTING PERIOD l

(

4

. DESCRIPTION OF PERIODIC TESTS WIUCH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICA110NS NONE DURING TIUS REPOR17NG PERIOD O

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HEALTH PHYSICS 4 ** , * '

February,1984 There was no single release of radioactivity or radiation exposure specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFT20.

d

4,***- PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR SAFETY AND OPERATING COMMITTEE AFTER TIME LIMITS SPEuwir.D IN TECHNICAL SPECIFICATIONS DATE DATE SNSOC UNIT TITLE DEVIATED REVIEW NO.

TOP 2000 1,2 Spent Resin Catch Tank 11/02/83 02/02/84 Resin Removal MOP 48.2 1 Return of "A" Condenser 01/03/84 02/02/84 Water Box to Service

.

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