ML20079M604
| ML20079M604 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1983 |
| From: | Jones V, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| 020, 20, NUDOCS 8401270372 | |
| Download: ML20079M604 (41) | |
Text
'
6 VIRGDEA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 83-12 APPROVED BY:
M sA 1 STATION MANAGER 1
8401270372 831231 PDR ADOCK 05000280 R
PDR hh l
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r-i Section g
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
Load Reductions Due to Environmental Restrictions - Unit #2 6
Average Daily Unit Power Level-Unit #1 7
Average Daily Unit Power Level-Unit #2 8
Summary of Operating Experience g
Amendments to Facility License or Technical Specifications 12 Facility Changes Requiring NRC Approval 13 Facility Changes 'Ihat Did Not Require NRC Approval 14 Tests and Experiments Requiring NRC Approval 15 Tests and Experinaents That Did Not Require NRC Approval 15 Other Changes, Tests and Experiments 16 Chemistry Report 17 Description of AllInstances Where 'Ihermal Discharge 18 Limits Were Exceeded Fuel HerGg 19 Procedure Revisions That Changed the Operating Mode 21 Described in the PSAR Description of Periodic Tests Which Were Not Completed 22 Within the Time Limits Specified in Technical Specifications
H Section Pm Maintenance of Safety Related Systems Durmg Outage or 23 Reduced Power Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems Durirg Outage or 25 Reduced Power Periods - Unit #2 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or 28 Reduced Power Periods - Unit #1 - Electrical Maintenam'.e Maintenance of Safety Related Systems Durirg Outage or 30 Reduced Power Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or 32 Reduced Power Periods-Unit #1-Instrument Maintenance Maintenance of Safety Related Systems Durmg Outage or 34 Reduced Power Periods - Unit #2 -Instrument Maintenance Health Physics Summary 36 Procedure Deviations reviewed by Station Nuclear Safety and 37 Operating Committee after Time Limits Specified in T.S.
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j OPERATING DATA EEPORT DOCKET l'O. 50-280 L
DATE 06 JAl? 84 CO'fPLITED RY Vtvian H. Jones TELEPHONE 804-357-3184 gggTI_NGSTA_wS
- 1. UNIT HA!!E SURRY UNIT 1
- 2. REPORTING PERIOD 120183 TO 123183
- 3. LICEh' SED THERIAL POWER (!fWT) 2441 l~~~~~~~~~~~~~~~l
- 4. NA!iEPLATE RATING (GROSS ?!WE) 847.S l NOTES l
S. DESIGN ET,ECTRICAL RATING (NET !!WE) 788
- 6. ?!AXI'!U:1 DEPENDABLE CAPACITY (GROSS MWE) 811
- 7. l'AXIXIE! DEDENDAELE CAPACITY (tiET !n'E) 775
. 9. PCi!ER LE'HL To in!ICH RESTRICTED, IF A!!! ll/A (NET l!'?E)
- 10. REASol!S FOR RESTRICTIONS IF ANY
. N/A THIS NONTE ??-%-DATE CUHULATI'M
- 11. HOURS IN RETORTING PERIOD 744.0 8760.0 96648.0
- 12. NWlEER OF HOURS REACTOR WAS CRITICM 601.1 5181.2 59092.9
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 3765.2
- 14. ROURS GENERATOR ON-LINE S81.4 S012.S 57867.2
- 15. UNIT RESERVE SEUTD0t!N ROURS 0.0 0.0 3736.2
- 17. GROSS ELECTRICAL ENERGY GENERATED (!!WH) 431730.0 3713800.0 43319843.0
' 18.1:5T ELECTRICAL ENERGY GEliERATED (!!WR) 409212.0 3517273.0 41077736.0
- 19. UNIT SERVICE FACNR 78.1 o/*
S7.2 ola S9. 9 < /*
- 20. UNIT AVAILABILITY FACTOR 78.1 */*
57.2 ole 63.7 ele
- 21. UNIT CAPACITY FACTOR (USING HDC NET) 71.0 =/*
S1. 8 * /*
S4.8 ele
- 22. UNIT CAPACITY FACTOR (USING DER NET) 69.8 o/*
S1. 0 o /*
S3.9 e/o
- 23. UNIT FORCED OUTAGE RATE 21.9 ele
- 4. 3 o le 21.6 e/*
- 24. SHUTDOWNS SCREDULED OVER NEXT 6 HONTRS WINTER MAINTENANCE 24 LODA (TYPE,DATE,A!;D DURATION OF EACE)
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTE! ATE DATE OF STARTUP
- 26. UNITS IN TEST STATUS P0 RECAST ACHIEVED (PRIOR TO CotD:ERCIM OPERATION)
INITIAL CRITICALITY INITIAL ETECTRICITY CCW!ERCIAL OPERATION.
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OPERATING DATA REPORT DOCEET NO. 50-281 DATE 06 JA?? 84 COtfrLETrD "y Vitier. H. Jones TELEPHONE 804-357-3184 O_PE_ RATING S_TA_TU_S
- 1. UNIT NN!E SURRY UNIT 2
- 2. REPORTING PERIOD 120183 TO 123183
- 3. LICENSED THER!M POWER (MWT) 2441 l~~~~~~~~~
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- 4. NN!EPLATE RATING (GROSS M2*)
847.5 l NOTES l
- 5. DESIGN ELECTRICE RATING (NET !!WE) 788
- 6. !!AXI;W1 DE*ENDABLE CAPACITY (GROSS I!WE) 811
- 7. ?!AXIlUi! DEPENDABLE CAPACITY (NET !3lE) 775
- 9. PC.7ER LEVFL TO WICH RESTRICTED, IF ANY N/A (NET I!VE)
- 10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS NONTH YR-TO-DATE CW!ULATIVE
- 11. HOURS IN REPORTING PERIOD 744.0 8760.0 93528.0
- 12. NID!BER OF HOURS REACNR YAS CRITICAL 281.B 5896.4 58570.9
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 253.3 5731.9 57576.0
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THER!AL ENERGY CENERATED (atWH) 569953.9 ~134?4526.8 134715872.9
- 17. GROSS ELECTRICAL ENERGY GENERATED (!MI) 184400.0 4312140.0 43794859.0
- 10. IlET ELECTRICE ENERGY GENERAED (f."4) 174571.0 4086139.0 41507060.0
- 19. UNIT SERVICE FACTOR 34.0 */o 65.4 e/o 61.6 e/o
- 20. UNIT AVAILABILITY FACTOR 34.0 o/*
65.4 * /*
61.6 o/*
- 21. UNIT CAPACITE FACTOR (USING NDC liET) 30.3 o/o 60.2 ole 57.3 ole
- 22. UNIT CAPACITY FMTOR (USING DER NET) 29.8 ele 59.2 o/*
56.3 ole
- 23. UNIT FORCED OUTAGE RATE 0.0 2.1 ole 14.1 o/=
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS SPRING MAINTENANCE 3-16 10 DAY (TYPE.DAS,AND DURATION OF EACH)
- 25. IF SHUT DCh?; AT END OF REPORT PERIOD, ESTIl: ATE DATE OF START!P
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- 26. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COlE1ERCIM OPERATION)
INITIAL CRITICALITI INITIAL ELECTRICITX.
CO.W4ERCIAL ' OPERATION
.o DOCKET NO.
50-280 UNIT SilHTDOWNS AND POWER REDUC 110NS UNIT NAME h rrv i
.DATE Jantary_ll6.1984 COMPLETED gy ' Vivian II. Jones REPORT MONTil December ione TELErilONE Ext. 477 i
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}Yj No.
Date
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, y oc Event g7 i
Action to fU Prevent Recurrence
$5 5
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6 80-21 12-15-83 F
125.3 A
3 Reactor trip caused by "C" RCP ' tripping.
The leads to the pump motor failed open. The leads were repaired.
I 80-22 12-24-82 F
24.2 A
3 Reactor trip caused by a high level in "C" S/G. The feed regulating valve went full opened due to a feed flow transmitter i'i' failing high due to frozen sensing line, also the "C" FRV stuck open. The sensing lines a
were thawed out and "C" FRV was repaired prior to startup.
i 80-23 12-25-83 F
4.3 G
3 Reactor trip caused by a low -low level "A" S/G during startup.
4 80-24 12-25-83 F
8.8 G
3 Reactor trip caused by a high level Iri"B" S/G during startup.
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4 Method:
Exhibit G. Instructions F: Forced Reasim:
S: Stheduled A Equipment Failure (Explain)
I-Manual for Pseparation of Data D-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee i i 3 Automatic Scram.
Event Report (LER) File (NUREG-
'g C Ilefueling D Regulatosy Resliiction 4-Ollies (Emplain) 01611 1
i E-Operator Training & Ucense Examination l
5 F Administrative Exhibit I Same Source i
G-Operational Esaur (Explain) j l'8/77)
Il-Other (Explain) l
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50-281' DOCKET NO.
UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Surry II DNIE Januarv 03.1984 COMPLETED sy Vivian II. Jnnee i
REPORT MONTil December 1983 TELErilONE Ext.477 9
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.! E 3
Y-Licensee Cause & Corrective Wo.
Date
[
gg j$
3 g 3' d,Evi k"t Event Action to F
$5 sE j15g Repost #
- G fu Prevent Recurrewe S
Reactor trip during plant shutdown ca Jsed 83-26 12-07-83 S
227.8 A
3 by a spike from first stage pressure when the generator output breakers were opened.
The plant was being shutdown to repair aux.
feed water check valves.
i 83-27 12-16-83 S
262.9 A
3 Reactor trip during plant startup caused a high level in "C" S/G, the plant was cooled f
down to repair "C" RCP's #1 seal.
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Exhibit G-Instructions 1
2 Method:
F: Forced Reason:
I Manual for Pseparation of Data S: Scheduled A Eituipment Failure (Explain) 2-Manual Scram.
Entry Sheels fue Licensee D Maintenance of Test 3 Automatic Scram.
Event Repost (LER) File NUREG-
- C. Refueling 4-Other (Explain) 0161)
- D Regulatory Ressiiction
!l.
E-Operator Tsaining & Ucense Examination 5
F Adminisirative Exhibit 1.Same Source G Operailonal Error (Explain)
I'8/77) ll-Othes (Explain)
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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS
" NIT NO.I NONTii; Oscsmbst, I000 DATE-TUfE HOURS LOAD, W REDUCTIONS, W F*H REASON' NONE DURING 'IHIS REPORTING PERIOD.
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MONTHLY TOTAL
LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS t
5-O. 2 30NIH: Decemtser,1980 DATE' TIZE -
HOURS LOAD, W REDUCTIONS, W WH REASON NONE DURING TfDS REPORTING PERIOD.
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MONTHLY TOTAL 1
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DOCKET NO 50-280 UNIT SURRY I DATE 1-1-84 CO/PLEED BJ Vivian H. Jones
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AVERAGE DAIT.Y UXIT POVER LEVEL MONTH: DECD!BER 83 AVERAGE DAILY POWER LEVEL AVERAGE D.4ILY POWER LEVEL DAY (NWE-NET)
DAY
(?NE-NET) 1 744.5 17 0.0 2
748.0 18 0.0 3
747.4 19 0.0 4
748.3 20 23.5 5
748.4 21 451.0 6
748.5 22 732.0 7
742.6 23 737.6 8
742.5 24 555.5 9
741.5 25 0.0 10 741.6 26 144.3 11 742.0 27 606.4 12 742.7 28 740.7 13 743.0 29 739.6 14 742.5 30 732.6 i
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15 419.3 31 744.6 l
16 0.0 l
DAILY UNIT POWER LEVEL FOMI INSTRUCTIONS ON THIS FORf, LIST ThlE AVERAGE DAILY UNIT MWER LEVEL IN INE-NET POR EACH DAY IN 1
THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH MR EACH REPORT-ING MONTH. NOTE THAT BY USING MAX 1 MUM DEPENDABLE CAPACITI FOR THE NET ELECTRICAL i
RATING OF THE UNIT, THERE MAX BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS j
THE 100 */* LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE i
DAILY UNIT POWER OUTPUT SHEET SHOULD BE E00TNOTED M EXPLAIN THE APPAREWT ANOMALY.
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DOCZET NO 50-281 UNIT SURRY II DATE 1-2-84 COMPLETED BY Vivian H. Jones V
AVERACE DAILY UNIT POWER L "l:L MON"Hz DECDfBER 83 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWE-NET)
DAY (MWE-NET) 1 739.3 17 0.0 2
739.4 18 0.0 3
741.1 19 0.0 4
744.5 20 0.0 5
743.5 21 0.0 6
737.7 22 0.0 7
37.1 23 0.0 8
0.0 24 0.0 9
0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 175.5 12 0.0 28 483.0 13 0.0 29 646.1 14 0.0 30 746.4 15 0.0 31 740.2 16 0.0 DAILY UNIT POWER LEVEL FOPN INSTRUCTIONS l
ON THIS FOMI, LIST THE AVERAGE DAILY UNIT POWER T.EVEL IN MVE-NET FOR EACH D4Y IN ~~~
THE REPORTING MONTH. THESE FIGURES WILL BE USED M PLOT A GRAPH POR EACH REPORT-
.ING MONTE. NOTE THAT BI USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE imIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 */* LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH Oa5ES, THE AVERAGE t
l DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED % EXPLAIN THE APPARENT ANOMALY..
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SUMMARY
OF OPERATING EXPERIENCE December,1983 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 ONE 12-01-83 0000 This reporting period begins with the unit at 100% power (785 MW's).
12-15-83 1335 Reactor trip, caused by "C" RCP tripping 1744 Commenced RCS cooldown to repair "C" RCP motor connector 2114 RCS < 350'F,450 psig 12-16-83 0243 RCS < 200'F 12-19-83 1125 RCS > 200*F
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1500 RCS > 350'F,450 psig 12-20-83 1236 Reactor critical 1852 Generator on the line, increasing power at 3%/hr.
12-22-83 0153 Unit at 100% power (780 MW's) 12-24-83 1751 Reactor trip caused by high level in "C" S/G 12-25-83 1410 Reactor critical 1805 Genc'ator on the line 1810 Reactor trip, caused by low -low level in "A" 5/G 2011 Reactor critical 2223 Generator on the line 2228 Reactor trip, caused by high level in "B" S/G 12-25-83 2358 Reactor critical 12-26-83 0717 Generator on the line, increasing power at 3%/hr.
12-27-83 1900 Unit at 100% power (780 MW's) 12'-31-83 24'30 This reporting period ends with the unit at 100% power (785 MW's) -.,
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SUMMARY
OF OPERATING EXPERIENCE December,1983 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 TWO 12-01-83 0000 This reporting period begins with the unit at 100% power (780 MW's) 12-06-83 2229 Commenced plant shutdown at 150 MW's/ hrs. to repair aux. feed water check valves.
12-07-83 0332 Reactor trip caused by turbine trip when generator output breakers were opened.
0650 Commenced RCS cooldown 1029 RCS < 350'F,450 psig 1445 RCS < 200*F 12-10-83 1920 RCS > 200*F 2330 RCS > 350*F,450 psig 12-11-83 053G RCS at HSD 1130 Commenced RCS cooldown to repair 2-SI-88,238 1517 RCS < 350*F,450 psig 1855 RCS < 200'F 12-13-83 0535 RCS at mid-nozzle 12-14-83 0750 Commenced fill & vent of RCS l
12-15-83 0855 Completed RCS fill and vent 1809 RCS > 200*F 12-16-83 0001 RCS > 350*F,450 psig l
0605 RCS at HSD 1145 Reactor critical 1517 Generator on the line 1519 Reactor trip, caused by high level in "C" S/G l
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12-17-83 1702 Shutdown reactor in preparation to go to CSD to repair "C" RCP's #1 naal c
12-12-83 0041 RCS < 350*F,450 psig 0404 RCS < 200'F 2055 RCS at mid-nozzle 12-22-83 2125 Commenced fill & vent of RCS 12-23-83 0040 Completed RCS fill & vent 0559 Hold RCS heatup due to high conductivity in RCS 12-26-83 1430 RCS > 200*F 1950 RCS > 350'F,450 psig 12-27-83 1148 Reactor critical 1414 Generator on the line, increasing power at 150 MW/hr.
2010 Holdies power at 68% for station dT limit of 23*F (520 MW's) 12-29-83 0410 Commenced slow power increase, monitc, ring station AT 1915 Unit at 100% power (785 MW's) i l
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AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS The Nuclear Regulatory Commission issued, en November 14,1983, Amendment Nos. 91 and 90 to the Operating License for Surry Power Station, Units 1 and 2, respecti'tely.
These amendments revise Technical Specification tables 3.8-1 and 3.8-2 which list containment isolation valves. This change replaces valves for the hydrogen analyzer system and the Residual Heat Removal Sample line, and removes valves for the leakage monitoring detection system. Several administrative errors are also corrected.
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FACILITY CHANGES REQUIRING NRC APPROYAL NONE DURING THIS REPORTING PERIOD.
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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL UNIT DC 82-11C Control Room Habitability Installation of Redundant 1&2 Cholorine Monitors Two chlorine monitors were installed in the main control room to meet the requirements of IEEE 279, 1974, Regulatory Guide 1.78, and Regulatory Guide 1.95.
The chlorine monitors sample the control room normal air intake by means of redundant and fully separated inline sensors installed in the ducting support channel installed ahead of the isolation dampers.
Summary of Safety Analysis The addition of redundant chlorine monitors will provide increased protection for the Control Room Operators and will satisfy the single failure criteria for the monitors given in Regulatory Guide 1.78, Regulatory Position 14.
DC 82-23 Removal of the Steam Generator Blowdown Tanks 1&2 This design change removed existing Steam Generator Blowdown Tanks. The Steam Generator Blowdown Flash Tanks were no longer being utilized because of modifications to the system installed with Design l
Change 76-31.
Summary of Safety Analysis The modification does not decrease the margin of safety due to the fact the blowdown tanks are no longer utilized in operating the present system.
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b TESTS AND EXPERIMENTS REQUIRING NRe arPRovrL NONE DURING THIS REPORTING PERIOD.
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL NONE DURING THIS REPORTING PERIOD.
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l VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CHEMISTRY REPORT December 19 83 T.S.
6.6.3.d PRI N COO N UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE
-1
-3 1.68E 1.56E' 3.66E 4.56E 4.61E 9.05E' Gross Radioact., uCi/ml Suseended Solids, pom 0.0 0.0 0.0 0.0 0.0 0.0
-1
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-2 Gross Tritium, uCi/ml 1.70E 4.80E 1.27E 1.81E 2.17E 8.42E-Iodine 131, uCi/ml 1.13E+0 1.43E 2.45E 2.28E 2.71E 1.54E
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-3 l33 0.96 0.28 0.65 0.21 0.07 0.12 I
/I 46.6 14.1(A) 27.1 30.6 4.0 16.3 (
Hydrocen, cc/ke Lithium, pom (B) 2.10
.90 1.12 2.58
.66 1.62 Boron-10, ppm.
342 88 142 322 151 246
- Oxycen, (D.O.), ppm
<0.005 4 0.005 4 0.005 1.50 4 0.005
.202 4 0.05 4 0.02 0.02 0.14 4 0.02 0.04 Chloride, pom pH 6 25'C 6.94 6.18 6.65 6.70 5.94 6.34
- Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (C)
RELEASES, POUNDS T.S.
4.13.A.6 Phosphate Boron-117 Sulfate __
Chromate 0.0 50% NaOH Chlorine
0.0 REMARKS
(A). Operations notified; Chemistry recommended increase in VCT pressure.
(B). Lithium additions made to Uniti: 1700gms. 12/15; 535gms. 12/19; 800gmsr 12/20:
635gms. 12/26; 325gms. 12/27. Additions to Unit 2: 1260rms. 12/7: 250 cms. 12/7; 356 cms.
12/11; 1950gms. 12/15; 455gms. 12/15; 025gms. 12/17; 2025gms. 12/24: 2100gms. 12/26:
400gms. 12/27;- 220gms. 12/29. Cation Bed placed in service on Unitt for Lithium removal:
12/11. Unit 2: 12/1: 12/8: 12/31.
(C) The levels of these chemicals should nroduce no ad-verse environmental imnact.
(on 1?/94/83 h4ch.mecific cenAnctivity vne aet ct a in nnit 2 Primary. A cation resin vessel was placed in service for clean-up. Investigations are con-tinuing to locate source.) 1 l
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4 DESCRIPTION OF ALLINSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED NONE DURING TfDS REPORTING PERIOD.
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FUEL HANDLING UNIT I December,1983 NONE DURING THIS REPORTING PERIOD.
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FUEL HANDLING UNIT II December,1983 NONE DURING TIIIS REPORTING PERIOD.
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PRnCEDURF REVIS!OMM THA_T ORANGED THE OPERATING MODE DESCRIBED Di THE FSAR NONE DURING TIUS REPORTING PERIOD.
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DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS f
Unit 1&2 PT-23.1D Security Monthly Inverter Battery Test Was missed in May,1983. The test was performed and no problems were noted.
Unit 1 PT-27G Heat Tracing System Was missed in June and August,1983. The subsequent tests were performed and no problems were noted.
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PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR SAFETY AND OPERATDF COMMITTEE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS December,1983 Date Date SNSOC Procedure No.
Unit Title Deviated Reviewed M MP-C-G-017 2
Piping / Components (Repair / Replacement 12-08-83 12-23-83 Program)
EMP-C-FP-43 1
Sealing of Fire Stops using Dow Corning 07-14-82 12-23-83 Q3-6548 Silicone RTV Foam OP-16 1
Spent Fuel Pit Makeup Cooling and 11-19-83 12-08-83 Purification System MOP-8.15 1
Removal of BA Transfer Pump "D" 11-19-83 12-08-83 PT-15.1B 2
Steam Generator Auxiliary Feedwater 11-20-83 12-08-83 Pumps PT-19.1 2
RWST Chemical Addition Tank and Con-11-20-83 12-08-83 tainment Spray System MOV's PT-21.1 A 2
Degraded /undervoltage Protection System 11-22-83 12-08-83 Calibration H-Bus PT-21.1 A 1
Degraded /undervoltage Protection System 11-22-83 12-08-83 Calibration H-Bus PT-21.1B 1
Degraded /undervoltage Protection System 11-22-83 12-08-83 Calibration J-Bus PT-21.1B 2
Degraded /undervoltage Protection system 11-22-83 12-08-83 Calibration J-Bus i
PT-24.7 1
Fire Protection - Deluge System 11-21-83 12-08-83 l
l PT-26.6 1,2 Radiation Monitoring Equipment Back-11-18-83 12-08-83 l
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9 VIRGINIA ELucTHIC AND Powen COMPANY Ricianown,VIHOINIA 232G1 W.L. STEWART Vaca Passansat weetain o,eminon.
January 12, 1984 Mr. N. M. Haller, Director Serial No. 020 Office of Management and Program Analysis N0/WDC: Jab U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Nashington, D. C.
20555 30-281 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 December, 1983.
Very trul-yours, ts L w~
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 Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 6(?'d 4