ML20206E046

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Monthly Operating Repts for Mar 1986
ML20206E046
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/31/1986
From: Jones V, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Beebe M
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
86-222, NUDOCS 8606230066
Download: ML20206E046 (23)
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VIRGINIA ELECTRIC AND POWER COMPANY {

I SURRY POWER STATION I MONTHLY OPERATING REPORT REPORT NO. 88-03

- APPROVED BY: //wk STATION MANAGER 1

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1 8606230066 860331 1 PDR ADOCK 05000280 R PDR l

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1 Section P_ age Operating Data Report - Unit No.1 1

Operating Data Report - Unit No. 2 2 Unit Shutdowns and Power Reductions - Unit No.1 3 Unit Shutdowns and Power Reductions - Unit No. 2 4 Average Daily Unit Power Level- Unit No.1 5 Average Daily Unit Power Level- Unit No. 2 5 Summary of Operating Experience 6 Facility Changes Requiring NRC Approval 7-8 Facility Changes That Did Not Require NRC Approval 7-8 Tests and Experiments Requiring NRC Approval 9 Tests and Experiments That Did Not-Require NRC Approval g Other Changes, Tests and Experiments 10
Chemistry Report 11 Description of AllInstances Where Thermal Discharge Limits Were Exceeded 12 Fuel Handling 13 - 15 Procedure Revisions That Changed the Operating Mode Described in the FSAR 16 ,

Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 17 j i

Maintenance of Safety Related Systems During Outage or Reduced j Power Periods - Unit No.1 - Mechanical Maintenance 18 l Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit No.1 - Electrical Maintenance 18

Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit No.1 -Instrument Maintenance 18 i

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11 Section Paje_

Maintenance of Safety Related Systems During Outage or Reduced -

19 Poiver Periods - Unit No. 2 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit No. 2 - Electrical Maintenance 19 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit No. 2 -Instrument Maintenance 19 1.

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Page 1 of 19

. ATTACHMENT 5 Page 1 of 3 OPERATING DATA REPORT FEB 0 21384 DOCKET NO. 50-280 DATE 4-2-86 COMJLETED BY V. Jones TELEPHONE (804) 357-3184 GPERATING STATUS

1. Unit Name: Unit 1 (Surry) Notes
2. Reporting Period: 03-01-86 to 03-31-86
3. Licensed Thermal Power (MWt): 2441
4. Nameplate Rating (Gross MWe): 847.5
5. Design Electrical Rating (Net MWe): 78R
6. Maximur. Dependable capacity (Gross MWe): 820 l
7. Maximum Dependable Capacity (Net MWe): 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last -

Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Not MWe): ,
10. Reasons For Restrictions, If Any:

1 This Month Yr.-to-Date Cummulative

11. Hours In Reporting Period 744.0 2160.0 116352.0
12. Number of Hours Reactor Was Critical 744.0 1791.9 74704.0
13. Reactor Reserve Shutdown Hours 0 0 3774.5 .
14. Hours Generator On-Line 744.0 1758.7 72597.2 4
15. Unit Reserve Shutdcwn Hours 0 0 3736.2

.16. Gross Thermal Energy Generated .

(MWH)  :.. 1814254.0 4133889.3 168016512.0 i

17. Gross Electrical Energy . i Generated (MWH) 607680.0 1374595.0 54146528.0 i
18. Net Electrical Energy  !

Generated (MWH) 578765.0 1305835.0 51339178.0 ,

19. Unit Service Factor 100.0 % 81.4 % 62.4 %

- 20. Unit Available Factor 100.0 % 81.4 % 65.6 %

21. Unit Capacity Factor l (Using MDC Net) 99.6% 77.4% 57.1% '

l 22. Unit Capacity Facter (Using DER Net) 98.7 % 78.7% 56.0% l

23. Unic Forced Rate 0 3.1 % 18.4 % '

24~. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):

Refueling 09 48 days

25. If Shut Down At End Of Report Period Estimated Date 'of Startup:
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved ,

l INITIAL CRITICALITY l INITIAL ELECTRICITY l COMMERCIAL OPERATION (9/77)

Page 2 of 19

- ATTACHMENT 5 Page 1 of 3 OPERATING DATA REPORT FEB 0 21384 DOCKET NO. 50-281 DATE 04-02-86 COMPLETED BY V. Jones

' - TELEPHONE (804) 357-3184 GPERATING STATUS

1. Unit Nase: Unit 2 (Surry) Notes ,
2. Reporting Period: 03-01-86 to 03-31-86
3. Licensed Thermal Power (MWt): 2441
4. Nameplate Rating (Gross MWe): 847.5
5. Design Electrical Rating (Net MWe): 788
6. Maximum Dependable Capacity (Gross MWe): 820
7. Maximum Dependable Capacity (Net MWe): 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last -

Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe): ,
10. Reasons For Restrictions, If Any:

1 This Month Yr.-to-Date Cummulative

11. Hours' In Reporting Period 744.0 2160.0 113232.0
12. Number of Hours Reactor Was Critical 744.0 1969.9 73912.6
13. Reactor Reserve Shutdown Hours 0 0 328.1 -
14. Hours Generator On-Line 744.0 1953.9 72719.3
15. Unit Reserve Shutdcwn Hours 0 0. 0

.16. Gross Thermal Energy Generated .

(MWH) .

1 a19a t 11 4721233.5 170028264.1

17. Gross Electrical Energy ,

Generated (MWH) 600705.0 1560055.0 55148359.0

, 18. Net Electrical Energy Generated (MWE) 571318.0 1483107.0 52269690.0 i 19. Unit Service Factor 100.0 % 90.5 % 64.2 %

20. Unit Available Factor 100.0 % 90.5% 64.2 %
21. Unit Capacity Factor (Using HDC Net) 98.3 % 88.1 % 59.3%
22. Unit Capacity Facter (Using DER Net) 94.4 % 87.1% 58.6 %
23. Unit Forced Rate 0 0 13.2 %
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

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25. If Shut Down At End Of Report Period Estimated Date 'of Startup: ,
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved l l

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION .

(1)/FF)

e DOCKfINO. 50-280 ,

UNIT SilU1 DOWNS AND POWER REDUCTIONS UNIT N AML Surry #1 DALE 04-02-86 .-

COMPl.ETED itY V Innae REPORT MON nl March .

TEl.EPilONE (804) 357 *t184 e.

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- [g 3 $YQ License: [g g3 h

g3 Cause & Curreceive Action so So. Date h, 3g i js5 i. vent u Preveni Recurrence t-fI $ gg Repor # oi O g

6 NO (E DURING TIII iREPORTING PERIOD.

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2 Method: Exliibit G-Instructions I

Reason: for Prcparation of Dai'. 2 l~: Fo ced A E gurpment Failure (Explain) 1 Manual Enery Sheets for Licens.ee g S: Scheduled 2 Manual Scram.

Eveni Report (LER) File (NURI G. w II. Maintenance of Tesi 3 Automatic Scram.

C.Refocling .

0161) o 4-Other (Explain) "

D Regulatory Restriction l'-Operator Training & Ucense Examination 5 5

F- Adnumst rative Ihlubit I - Same Source G.Operanonal Error (Explain)

Il Other (Esplain) es/77) .

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IHX'K E I NO. 50-281 IlNIT Sil01 DOWNS AND POWER REDUCllONS UNII N AME Surry 2 ,

D AIE 04-07-RR COMPl.ET ED liy V. Jones REPORT MON Ill March lEl.0PilONE f 804) 357-31f14

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p t; j C S j cd Reposi # es) U l*sevent l(cCuf sent'e Q ,, CC ym d

NONE DURING TilIS F EPORTING PERIOD.

3 4 I 2 l'mintent G - Insisudi, ins *e Meiliud: .

g I:: 1:n ted Reason: los Picparaison ut Daia A Etguspment Failure (Emplain) 1 Manual S Scheduled 2 Mae ual Scram. I.niry sliccis fue 1.itensee cm Il Mainienance of Test 1.veni Repuoi(t.l.Ril'ile (Ntlitl&

  • C.Hefueling 3 Automanic Scram.

4 Onlier (Emplaisil 0161) S, D Regulainey itesisiction -

E-Opesaine Tsaining & l.icense Examinaison

  • 5 F AtImamsisaiive INinha l Same Source G Ope ational I. sur (Extilain) es/11) 11 Olliesilaplani) s

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AVER 2GE DAILY UNI T POWER LE VEL SURRY POWER STATION PROGR AM N0512681 04/01/83 09.34.49 .

REPORTING MONTH - MARCH 1986 .

DOCKET NO. 50-280 DOCKET NO. 50-281 DATE APRIL 1, 1986 COMPL ETED BY v. H. JDNES UN I T ON E UN IT TWD AVERAGE DAILY PDwER LEVEL AVERAGE DAILY POWER LEVEL '

DAY -9WE-NET- -MWE-NET- .

1 777 8 767.9 2 780 0 771.0 3 778.5 770.3 4 778.2 743.3 5 777.6 737.5 6 779 3 761 2 7 779.3 761.C 8 779.7 763.3 9  ??6.8 763 3 10 776 1 766.2 11 777.1 767 1 12 777 0 770.0 13 779.6 770.5 14 779 1 767.8 15 778.1 771 4 16 779.4 774.1 17 77S.7 771.9 18 777 3 766 3 19 774.5 774.4 20 774 2 772.7 21 776 1 772 7 22 F80.3 774.5 23 781 1 775.6 24 780 8 773 3 25 778.5 771.4 26 777 6 771.6 27 776 6 769.5 28 772.9 772 1 29 779 2 773.0 30 777.7 770.7 31 776 0 768.8

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Page 6 of 19 )

SUMMARY

OF OPERATING EXPERIENCE MONTH / YEAR March.1986 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 03-01-86 0000 This reporting period begins with the unit at 100% power,815 MW's.

03-31-86 2400 This reporting period ends with the unit at 100 % power, 815 MW's.

UNIT TWO 03-01-86 0000 This reporting period begins with the unit at 100 % power,810 MW's.

03-04-86 2209 Commenced unit rampdown to maintain condenser vacuum. "A" waterbox removed from service.

2322 Holding power at 86 %, 655 MW's.

2359 "A" waterbox RTS still having trouble maintaining vacuum. l 03-05-86 0320 Found leak in SD piping elbow for "A" 5th point drain cooler, installed soft patch.

0351 Commenced power increase at 150 MW's/hr.

0539 Unit at 100 % power,810 MW's.

03-31-86 2400 This reporting period ends with the unit at 100 % power,810 MW's.

Pago 7 of 19 FACILITY CHANGES REQUIRING NRC APPROVAL ,

MONTH / YEAR MARCH,1986 NONE DURING THIS REPORTING PERIOD. ,

- j FACILTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL I MONTH / YEAR MARCH,1986 [

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DC 84-85 Appendix "R" Coordination Study Fuse Replacement Unit 1 I This design change eliminates the possibility of losing electrical power j to safety related equipment due to electrical faults. The change provides j for coordination between various loads and their breakers / fuses of their '

load buses. This will assure that the load protection device will clear the fault condition before the bus feeder breaker. This is important since if the bus feeder breaker trips, then all equipment on the bus is lost, not just the faulted piece of equipment.

Summary of Safety Analysis The modification reduces the possibility of loss of more safety equipment than necessary thus enhancing the safety of the plant.

DC 82-27 Component Cooling Trip Valve Operator Airline Filter - Unit 1 This design change added filters to the air' supply lines of the actuator pneumatic-pilot relay valves for Component Cooling Trip valves TV-C C-109A 6 B and TV-CC-209A 6 B. The filters are capable of

, removing both particulates and moisture to prevent pneumatic-pilot relay valve malfunction.

. Summary of Safety Analysis The installation of air supply. filters together with the establishment of an effective filter element replacement periodicity will result in increased trip valve operational reliability.

DC 80-52 Containment High Range Radiation Monitoring System Units 18 2 This design change installed two High Range Containment Radiation Monitors to provide indication in the control room of containment radiation level.

Summary of Safety Analysis The modification provides additionalinformation on performance of safety systems following an accident.

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Page 8 of 10 Corrected Copy FACIllTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH / YEAR FEB. - 1986 DC 84-37 DC RG 1.97 Emergency Ventilation Damper Position Indication Unit 2 This design change provides position indications of emergency ventilation dampers and satisfied RG 1.97 and RG 1.89 requirements. Environmentally qualified limit switches were mounted on the dampers to provide position indication such that the original qualification and operation of the dampers is not degraded.

Summary of Safety Analysis Thi modification added limit switches, which are environmentally qualified to emergency ventilation dampers. It does not change the operation of the emergency ventilation dampers or the operation of other safety systems.

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. TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH / YEAR M AR C H,1986 NONE DURING THIS REPORTING PERIOD.

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TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL  ;

i MONTH / YEAR M ARC H,1986  !

I NONE DURING THIS REPORTING PERIOD.

Paga 10 of 19 OTHER CHANGES, TESTS AND EXPERIMENTS MONTH / YEAR March.1986 1 .

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PROC.NO. TITLE UNIT ST-186 Bolting Identification Test 162 f.

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4 PG' 28-06 Page 11 of 19 VIRGINIA PO G SUR 6 PO G STATIQ!

CEDiISTRY F M C MARCH 19 86 i

ANALYSIS L"IT NO. 1 Uf4T1' 10. 2 MAXIF1H MINIFIE AVERIGE !aXIMUM MINIBE AVERAGE i

0 -1 ,1,49 0 Gross Radioact., uCi/ml 1.98 9.91 2.04~ 7.23~ 1.40~

Suscended Solids, c:2n 0.0 0.0 0.0 0.0 0.0 0.0 j

-1 3.59-2

-1 9.19-2

-2 8.80 -2 3ross Tritiun, uCi/ml 1.40 1.01 8.46 Iodine 131

, uCi/ml 2.43 1.38 -2 1.75

-2 1.34

-4 7.42 -5 1.02 -4 131 j7 131 I 0.25 0.16 0.19 0.16 0.07 0.10 Hvdrocen, cc/kg 32.4 27.9 30.0 40.7 26.1 30.9 Mthiun, c:2n 0.57~ 0.37 0.50 1.16 0.94 1.05 Boron-10, can* 22.5 7.2 14.1 109 97 103 0xygen, (D.O.)r c:2n 60.005 40.005 40.005 4 0.005 *0.005 60.005 Chloride, c:2n 6 0.01 4 0.01 40.01 6 0.01 6-0.01 6 0.01 pH @ 25'C 7.65 6.95 7.35 6.76 6.41 6.66

  • Boron-10 = Total Baron x 0.196 EEMARKS: No LiOH was nadad t o eithr unit in March. CAT Bed placed in service _

on Unit 2r 03-06 ' 0333 to 0506 dna to 2r concentration being hich in hana- '

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"E DESCRIPTION OF ALL INSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED MONTH / YEAR March,1986 i

. , NONE DURING THIS REPORTING PERIOD.

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FUEL HANDLING J

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UNIT # 1 MONTH / YEAR March,1986 DATE NO. OF ANSI NO. NEW OR SPENT FUEL

' HIPPED / RECEIVED

. ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL ~

New Fuel Ship. #1 03-18-86 - 12 LMOJGB < 5 mr/ hr.

. 4k

^ LMOJGG LMOJHC LMOJHG LMOJH9 i

LMOJG4 LMOJGF LMOJGP ,

1 LMOJG9 LMOJGQ LMOJHI y ,,

LMOJGU New Fuel Ship #2 03-20-86 12 LMOJHM LMOJG2 LMOJGX LMOJH8 l

LMOJGS 1 LMOJG H LMOJG1 LMOJGJ l LMOJGN l l

LMOJGW y LMOJGY V

it 03-20-86 12 LMOJGT < Smr/hr.

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FUEL HANDLIMG UNIT > I MONTH / YEAR March,1986 DATE NO. OF , ANSI NO. NEW OR SPENT FUEL FIPPED/ RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LE*/?:

New Fuel Ship. #3 03-25-8B 12 LMOJG3 < Smr/hr.

A A A LMOJHD LMOJH6 LMOJGR LMOJH4 LMOJHF LMOJHB LMOJGL LMOJHL LMOJHO LMOJGO y LMOJHE New Fuel Ship. #4 03-27-86 LMOJGE

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LMOJHJ l

LMOJG8 l l

LMOJEM  !

LMO TGC LMOJGV LMOJHA LMOJG6 LMOJGA l LMOJG Z LMOJH7 ---

03-27-86 12 LMOJHH <5 mr/hr.

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Page 15 of 19 FUEL HANDLING UNIT # 2 MONTil/ YEAR M AR C H,1986 DATE NO. OF ANSI NO. NEW OR SPENT FUEL HIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL ;

NONE D1 JRING THIS REPORTING PERIOD.

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. . l PROCEDURE REVISIONS THAT CHANGED THE OPERATING AtODE DESCRIBED IN THE FSAR MONTH / YEAR March.1986 ' i NONE DURING THIS REPORTING PERIOD.

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Page 17 of 19 DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH / YEAR March.1986 PROC. NO.' ' TITLE UNIT 1-PT-1S.6 Equipment Hatch Leak Test 1 1-PT-24.22 Fire Protection Systems (Training Services) 1 1-PT-24.37 Warehouse Smoke Detector Check 1 2-PT-16.6 Equipment Hatch and Emergency Personnel Escape Hatch Leak Test 2 e

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Pags 18 of 19 MAINTENANCE OF SAFETY RELATED SYSTEMS DURING .

OUTAGE OR REDUCED POWER PERIODS i UNIT NO.1 f, l

t MONTH / YEAR March.1986  !

NONE DURING THIS REPORTING PERIOD.  !

The below listed codes denotes the following departments: {

l 0228 or R03 -

Mechanical 0229 or R04 -

Electrical 0237 or T22 -

Instruments l

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Page 19 of 19 P

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l MAINTENANCE OF SAFETY RELATED SYSTEMS DURING '

OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 MONTH / YEAR March,1986 The below listed codes denotes the following departments:

0228 or R03 -

Mechanical 0229 or R04 -

Electrical 0237 or T22 -

Instruments NONE DURING THIS REPORTING PERIOD.

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O VIRoINIA ELucTRIC AND PowzR CoxrANY RxcitwoNn, VINGINIA 20 2 61 W.L.Srawaar Vics Puumanswv Nuctuan Oramarione April 15, 1986 Mr. Maurice R. Beebe Serial No.86-222 Office of Resource Management N0/JDH:vlh U.S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D.C. 20555 50-281 License Nos. DPR-32 DPR-37

Dear Mr. Beebe:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos.

1 and 2 for the month of March, 1986.

Very truly yours, T m W. L. Ste art Enclosure (3 copies) cc: Mr. James M. Taylor, Director (12 copies)

Office of Inspection and Enforcement Dr. J. Nelson Grace .

Regional Administrater NRC Region II NRC Senior Resident Inspector  !

Surry Power Station 4

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