ML20065T675

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Monthly Operating Repts for Aug 1982
ML20065T675
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/15/1982
From: Jones V
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20065T664 List:
References
NUDOCS 8211020639
Download: ML20065T675 (38)
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  • 4 a VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 82-08 AUGUST, 1982 APPROVED BY: 5 #N Station Manager 8211020639 820915 PDR ADOCK 05000280 R PDR

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- * . Section g Operating Data Report - Unit fl 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 f 2 6 Average Daily Unit Power Level - Unit #1 7 Average Daily Unit Power Level - Unit #2 8 Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRC Approval 12 Facility Changes That Did Not Require NRC Approval 12 Tests and Experiments Requiring NRC Approval 13 Tests and Experiments That Did Not Require NRC Approval 13 Other Changes, Tests and Experiments 14 Chemistry Report 15 Description of All Instances Where Thermal Discharge Limits Were Exceeded 16 1

Fuel Handling 17 l Procedure Revisions That Changed the Operating Mode Described in the TSAR 18 Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 19 Inservice Inspection 20 Reportable Occurrences Pertaining to Any Outage or Power Reductions 21 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 22 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 24

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Section Page a

Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 26 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 28 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit i1 - Instrument Maintenance 30 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance 32 Health Physics Sunsnary 34 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee af ter Time Limits Specified in T. S. 35 1

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, OPERATING DATA REPORT __

. a , DOCKET NO. 50-280 DATE 07 SEP 82 CONPLETED BY Vivian H. Jones TELEPHONE 804-357-3184

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1. UNIT NAME SURRY UNIT 1
2. REPORTING PERIOD 080182 083182
3. LICENSED THERMAL POWER (MWT) 2441 l~~~~~~~~~~~~~~~~~~~~~~~~l
4. NAMEPLATE RATING (GROSS MWE) 847.5 l NOTES l
5. DESIGN ELECTRICAL RATING (NET MWE) 788
6. MAXIMUM DEPENDABLE CAPACITY ( GROSS MWE) 811
7. VAXIMUN DEPENDABLE CAPACITY (NET MWE) 775
8. IF CHANSES OCCUR IN CAPACITY RATINGS N/A (ITEMS 3 THROUGH 7) SINCE LAST hEPORT, GIVE REASONS
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY N/A (NET MWE)

.0. REASONS FOR RESTRICTIONS, IF ANY N/A THIS MONTH YR-TO-DATE CUMULATIVE

.1. HOURS IS REPORTING PERIOD 744.0 5831.0 84959.0

.2. NUMBER OF HOURS REACTOR WAS CRITICAL 731.1 5368.2 51402.7

3. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 3731.5

.4. HOURS GENERATOR ON-LINE 727.6 5296.9 50371.7

.5. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 3736.2

.6. GROSS THERMAL ENERGY GENERATED (MWH) 1719679.7 12577586.7 116910853.1 19 GROSS ELECTRICAL ENERGY GENERATED (MWE) 533540.0 3953300.0 37772513.0

.a. hET ELECTRICAL ENERGY GENERATED (MWH) 504396.0 3746563.0 35823799.0

.9. UNIT SERVICE FACTOR 97.8 e/e 90.8 */e 59.3 e/e

!0. UNIT A YAILA BILITY FACTOR 97.8 */o 90.8 e/o 63.7 */o

?1. UNIT CAPACITY FACTOR (USING MDC NET) 87.5 */* 82.9 */o 54.4 e/ o

?2. UNIT CAPACITY FACTOR (USING DER NET) 86.0 */* 81.5 e/o 53.5 e/o

?3. UNIT FORCED OUTAGE RATE 2.2 e/* 3.9 */o 23.6 */*

?4. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTES FALL MAINTENANCE - 10-01 14 DAY (TYPE,DATE, AND DURATION OF EACH)

? 5. IF SHUT DOWN AT END OF REPORT PERIOD. .

ESTIMATE DATE OF STARTUP

?6. UNITS IN TEST STATUS FORECA ST ACHIEVED (PRIOR *TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION L-.

OPERATIN] DATA REPORT

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DOCKET NO. 50-283 ~ l DATE 07 SEP 82 COMPLETED BY Nivian H. Jones TELEPHONE 804-357-3184

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1. UNIT NAME SURRY UNIT 2
2. hEPGhTIhG PERIOD 080182 083182
3. LICENSED THERMAL POWER (MWT) 2441 l~~~~~~~~~~~~~~~~~~~~~~~~l
4. h AMEPLATE RATING (GROSS MWE) 847.5 l NOTES l
5. DESIGN ELECTRICAL RATING (NET MWE) 788
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) 811
7. %t.tIMUM DEPENDABLE CAPACITY (NET MWE) 775
8. IF CHANGES GCCUR IN CAPACITI RATINGS N/A (ITEMS 3 THROUGH 7) SINCE LAST HEPGRT. GIVE REASONS
9. POWER LEVEL TO WHICH RESTRICTED. IF ANY N/A l (NET MWE) to. REASONS FOR RESTRICTIONS. IF ANY N/A THIS MONTH YR-TO-DATE CUMULATIVE u1. HOURS IN REPORTING PERIOD .744.0 5831.0 81839.0 u2. NU4BER GF HOURS REACTOR WAS CRITICAL 744.0 5276.1 50136.8 l L3. REACTOR RESERVE SHUTDOWN HOURS 0.0 0 . 0~ 0.0 s4. HOURS GENERATOR ON-LINE 744.0 5205.2 49316.9

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. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0

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16. GROSS THERMAL ENERGY GENERATED (MWH) 1810719.0 11852896.5 115150182.4 t7. GRCSS ELECTRICAL ENER3Y GENERATED (MWH) 583485.0 3807390.0 37484569.0 L8. NET ELECTRICAL ENERGY JENERATED (MWH) 552942.0 3596395.0 35525110.0
19. UNIT SERVICE FACTOR 100.0 */o 89.3 */o 60.3"a/*.
20. UNIT A VAILABILITY FACTOR 100.0 e/o 89.3 ele 60.3 e/o

?1. UNIT CAPACITY FACTOR (USING MDC NET) 95.9 e/* 79.6 */* 56.0 */*

!2. UhIT CAPACITY FACTOR (USING DER NET) 94.3 e/o 78.3 */* 55.1 */o

?3. UNIT FORCED OUTAGE RATE 0.0 3.2 s/* 16.0 */*

14. SHUTECWNS SCHEDULED OVER NEXT 6 MONTHS FALL MAINTENANCE - '11 19.g2 -

10 DA (TYPE.DATE. AND DURATION OF E/CH)

?5. IF SHUT DOWN AT END OF REPORT PERIOD.

ESTIMATE DATE OF STARTUP

16. UNITS 13 TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION) 1NITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION l

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1 DOCKETNO. 50-280

UNIT SHUTDOWNS AND POWER REDUCMONS surry one' UNIT NAME

  • DATE 09-07-82 , / , !,

COMPLETED BY vivian II. Jones REPORT MONDI August, 1982 TELEPHONE (804) %7-11 Ad x477 e.

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- 3g 3 yQ Licensee Eg Cause & Corrective Nii. Date h 3$ @ 2 5 oc Event 3,T Eu F

fE 5 j ;p, Report # mo g Prevent Recurrence d

82-20 08-12-82 F 0.0 A 4 Reduced power to 35% IAW Abnormal procedure 33 due to loss of blowdown capability on "A" S/G. The diaphram was replaced on TV-BD-100A and blowdown re-established and chemistry verified in specification prior to returning unit to full power. .

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s 82-21 08-24-82 F 16.4 G 3 Mechanics working near the steam header pressure transmitters with an impact wrench jarred the transmitters causing a spurious safety injection.

All personnel involved hgve been ,

made aware of the sensitivity of these transmitters to vibration.

3 4 I 2 Method: Exhibit G Instructions F: Forced Reason:

for Preparation of Data S: Scheduled A-Equipment Failure (Explain) I-Manual 2-Manual Scram. Entry Sheets for Licensee B-Maintenance of Test Event Reporn (LER) File (NUREG-C Refueling 3 Aulomatic Scram.

! 4-Other (Explain) 0161)

D-Regulatory Resitiction E-Operator Training & License Examination

' 5 F-Administrative G-Operational Error (Explain) Exhibit 1 - Same Source l'8/77) ll-Other IE xplain) b l e

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-281 UNIT NAME surrv Twn ,

DATE 09-02-82 -

REPORT MONT11 August, 1982 COMPLETED BY Vivian H. Jones

. TELEPflONE (804) 357-3184 x477 i

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Wo. Date gg  ; ,gg5 Event uT Action to oE 5 jgg Report # v%'0 v Prevent Recurrence 6

None during this repo rting period.

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t 2 3 4 Method: Exhibit G - Instructions F: Forced Reason:

S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee i C Refueling 3 Autornatic Scram. Event Reporn (LER) File (NUREG i D Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & Ucense Examination

! F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source t'8/77 ) 11 O her(Explain) e

. o i LOAD REDUCTIONS DUE TO ENVIRONMENTAL RISTRICTION_S_

UNIT NO. 1 MONTH: August, 1982 DATE TIME HOURS LOAD, W REDUCTIONS, MW MWH REASON Noneiluring this reporting period.

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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.2 MONTE: August, 1982 DATE TIME HOURS LOAD, MW REDUCTIONS, MW MWH REASON None during this reporting pt riod.

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MONTHLY TOTAL

-7 :0CiGT NCr 59-280 UNIT SUERY I CA'E 9-1-82 CJMPLETES By Vivian H. Jones AVERAJE DAILY UNI." PCL'ER LEVEL 40n:"=: AUJUS: 82 AVERAJE :AILY PCMER LEVEL AVER 4]E :AILY PCWER LEVEL

AY (5'E-NET) CAY (%'E-NET) 1 712.3 17 715.5 2 715.0 18 717.9 3 713.9 19 715.2 4 715.8 20 714.0 5 717.4 21 713.6 6 714.5 22 720.8 7 714.8 23 715.8 8 714.9 24 393.5 9 715.2 25 346.5 10 716.7 26 710.0 11 717.2 27 715.1 12 471.2 28 714.8 13 487.1 29 716.8 14 716.3 30 718.8 15 715.3 31 716.5 16 714.5 DAILY UNIT POWER LEVEL FOR4 INSTRUCTIONS ON TiIS FORM, LTST TdE AVERA15 DAILY UNIT PCWER LEVEL TN XiE-NET FOR EACE CAY IN THE REPOR"ING MONYd. THESE FIllRES VILL BE USED TO PLOT A JRAPE FOR EACE REPORT-1Ni MGhm. ACTE TEAT EY USIN3 MAXIMUM DEPEN:ABLE CAPACITY FOR THE NET ELEC'RTCAL RATING OF TIE UNIT, TiERE MAY BE OCCASIONS WEDI THE D.tTLY AVERAJE PCWER EXCEEDS THE 100 e/o LTNE (CR .'EE RES"RICTED PCMER LEVEL LTNE). IN SUCE CASES, tie AVERA]E EAILY UNIT PCWER CU.*PC" SERET SEGULD BE F00'NO'E: TO EXPLAIN TEE APPAhEN" ANOMALY.

' 'B' 20:KET N' 50-281 Ui;IT SURRY II CATE 9-1-82 C0%'PLE."E: EY vivian u. Jones AVERAJE DATLY UNIT PCWER LEYEL N3HTE: AUlbS" 82 AVEhAJE :ATLY POWER LEVEL AVER 4]E :AILY PCL'ER LEVEL CAY (&T-NET) :AY (Y=T-l.TT) 1 743.3 17 739.0 2 743.8 18 738.6 3 743.3 19 734.3 4 743.3 20 735.6 5 742.3 21 736.2 6 740.5 22 735.8 7 739.6 23 749.3 8 744.8 24 742.7 9 748.1 25 743.9 10 747.9 26 747.0 11 747.9 27 745.7 12 747.9 28 736.8 13 745.2 29 750.4 14 746.3 30 757.3 15 740.1 31 744.9 16 739.8 CATLY UNIT ENER LEVEL FORY INSTRUCTIONS CN TiIS F0hM, LIST TEE AVERAE DAILY UNIT PCWER LEVEL IN MJE-NET FOR EATi CAY IN THE EEPOR"Ih]. MONTE. BESE FIJUhES WILL BE USE: TO PLOT A 2 RAPE FOR EACE REPORT-IN] MGNT3. h0TE TEAT BY USTN] MAXINUM DEPEN:ABLE CAPACITY FOR Ti2 NET ELECTRICAL hL'Ik] 0F Td5 UNIT, TiEEE MAY 25 GCCASICNS WEEN TEE :AILY AVERAJE POWER EXCEE:S THE 100 el* LINE (CR TEE RESTRICTE: POWER LEVEL LINE). IN SUCE CASES, THE AVERAJE DAILY UNIT PCJER CUTPUT SEEET SECULD BE FOOTNOTE: 70 EXPLAIN TEE APPARENT ANONALY.

SUMMARY

OF OPERATING EIPERIENCE AUGUST, 1982 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 August 1 This reporting period begins with the unit at 100% power.

August 11 1421 - TV-BD-100A failed closed stopping all blowdown from "A" S/G.

August 12 1002 - Commenced decreasing power. This was done as a precaution since secondary side chemistry could not be verified on "A" S/G. (h e sample points came off the

. blowdown line down stream of TV-BD-100A) .

1528 - Stopped decreasing power at 35%.

2159 - TV-BD-100A was repaired and blowdown restarted on "A" S/G.

2359 "A" S/G secondary side chemistry has been verified

'in specification and a power increase started at 3% per hour.

August 13 2200 - The unit reached 100% power.

August 24 1315 - The unit tripped and safety injected on a spurious ..

Steam Header to Steam Line Differential Pressure signal.

The spurious signal was a result of mechanics working in the vicinity of the Steam Header pressure transmitters with an impact wrench. These transmitters are very sensitive to vibration.

1715 - The dose equivalent Iodine exceeded 10 microcuries per milliliter. Started six (6) hour clock for cooldown of the reactor coolant system (RCS) to <500 0F.

2018 - Cooled RCS down to <5000 F.

August 25 0207 - Dose equivalent Iodine was verified within allowable specifications. The RCS was heated up and the reactor was l made critical.

l . 0540 - The generator was placed on the line.

0641 - Unit at 55% power with all main feed flow control valves in automatic. Reduced rate of power increase to l

34 per hour.

August 26 0437 - The unit reached 100% power.

August 31 This reporting period ends with the unit at 100% power.

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Summary of Operating Experience (continued) August, 1982 Unit Two August 1 This reporting period begins with the unit at 100% power.

August 31 This reporting period ends with the unit at 100% power.

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AMENDMENTS TO FACILITY LICD?SE OR TECHNICAL SPECIFICATIONS AUGUST, 1982 The Nuclear Regulatory Commission, on August 17, 1982, issued Amendment Nos. 79 and 80 to the Operating License for Surry Power Station Unit Nos. 1 and 2 respectively. The changes have been designated as Technical Specification change No. 89.

These amendments revise the Technical Specifications to incorporate revised inservice surveillance requirements for snubbers, both mechanical and hydraulic.

Accordingly, the paragraph 3.B of the operating License for Unit 1 and 2, respectively, is amended as follows:

(Unit 1) "B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."

(Unit 2) "B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."

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  • N FACILITY CHANGES REQUIRING NRC APPROVAL AUGUST, 1982

- None during this reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL AUGUST, 1982 Unit

. D/C 80-54 Charging Pttttp Lube Oil Cooler TCV Modification 1 This design change provides automatic temperature control of the charging pump lube oil systems. An air operated control valve was installed in the service water outlet of each lube oil cooler (three per unit). A capillary type thermal element was installed in the oil line which provides the signal to a pneumatic indicating temperature controller.

Control air is supplied to the temperature controller with the output signal operating the control valve.

Summary of Safety Analysis The modification enhances the reliability of'the charging pump lube oil cooler service water system.

Automatic temperature control of the charging pump lube oil system enhances safe and efficient operation during normal and post-accident operations.

D/C 81-19 Machine Shop Replacement Facility 1&2 D/C 81-19 Machine Shop Replacement Facility - HVAC Summary of Safety Analysis The addition of the Machine Shop Replacement Facility does not minimuze the safety of operating units or effect the operation of safety related equipment.

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, TESTS AND EXPEP!MENTS REDUIPING NRO APPROVAL AUGUST, 1982 None during this reporting period.

TESTS AND EXPERIMEICS THAT DID NOT REQUIRE NRC APPROVAL AUGUST, 1982 Special Test Mo. Title Unit Date Completed ST-52 RCS Flow Measurement Data 1&2 08-05-82 ST-52 RCS Flow Measurement Data 1&2 08-26-82 ST-140 Control / Relay Room Penetration Test 1&2 08-26-82 ST-145 Auxiliary Building vent-Vent Delay Time Test 1&2 08-31-82 O

  • OTHER CHANGES, m 3 n o m gg AUGUST, 1982 e

None during this reporting period.

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SURRY PO'JER STAT 10E CHEMISTRY REPORT August , 19 82 T. S . '6. 6. 3.d PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE (A) EO (B) E-1 E-1 E-1 Gross Radioact., pCi/ml 5.73 1.74 3.13 0

8.60 1.62 2.39

. Suspended Solids, ppm 0.1 0.1 0.1 0.1 0.1 0.1 E-1 E-2 E-1 E-1 E-1 E-1 Gross Tritium, pCi/ml 1.34 6.10 1.08 3.38 2.50 3.03 (A) E-2 E-2 Eo E-3 E-4 E-3 Iodine-131, pCi/ml 8.20 8.24 1.28 9.27 7.92 2.14 I-131/I-133 1.6800 .3941 1.0900 1.6502 .3189 .7665 (C)

Hydrogen, cc/kg 46.7 20.8 30.8 42.8 31.1 35.2 Lithium, ppm 1.10 .40 " .76 1.62 1.05 1.29 Boron-10, ppm + 118.97 57.43 68.21 127.40 115.25 122.89 0xygen-16, ppm .005 .000 .000 .000 .000 .000 Chloride, ppm <.05 <.05 <.05 <.05 <.05 <.05

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pH @ 25'C 7.12 6.54 6.85 6.99 6.64 6.74

+ Boron-10 = Total Baron x 0.196 NON-RADIOACTIVE CHDiICAL RELEASES, POUNDS

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T. S . 4.13. A. 6 Phosphate -

Boron 564 Sulfate -

Chromate 0.0 5'0% NaOH -

Chlorine Remarks: (A) High activity level following reactor trip 8/24; (B) PC-4 not in service; used NC-2; (C) ' Hydrogen level too low (following reactor trip); recommended increased pressure on VCT. (D) Four separate lithium additions 8/6, 8/10, 8/17, & 8/27; (E) Following reactor trip; (F) The levels of these chemicals should create no adverse environmental impact.

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. DESCRIPTION OF ALL INSTANCES WHERI

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THER!iAL DISCHARGE LUiITS E RE EXCEEDED AUGUST, 1982 Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.

i 1 August 13 - Exceeded 15'F AT across station

  • 14 - Exceeded 150 F AT across station 15 - Exceeded 15'F AT across station 16 - Exceeded 150 F AT across station 17 - Exceeded 158 F AT across station

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18 - Exceeded 15 0 F AT across station 19 - Exceeded 15'F AT across station 20 - Exceeded 17.5 0F AT across station

  • 21 - Exceeded 158 F 6T across station 22 - Exceeded 17.5 0 F AT across station 23 - Exceeded 150 F AT across station
  • 24 - Exceeded 17.5 0F AT across station
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25 - Exceeded 150F AT across station

  • 26 - Exceeded 15'F AT across station
  • 27 - Exceeded 15 0F AT across station
  • 28 - Exceeded 17.5'F AT across station 29 - Exceeded 17.50 F AT across station
  • 30 - Exceeded 150 F AT across station
  • 31 - Exceeded 15 0F AT across station *
  • Indicates dates where station AT was less than or equal to 15.0'F across station for some time during the day.

The AT excursions were allowable under Technical Specification 4.14.B.2. There were no reported instances of adverse environmental impact.

The temperature change at the station discharge exceeded 3 0 F per hour on August 24, 1982, due te a Unit 1 reactor trip. This event was allowable in accordance with Technical Specification 4.14.B.l. There were no reported instances of adverse environmental impact.

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FUEL HANDLING AUGUST, 1982 Units One and Two None during this reporting period.

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PROCEDURI REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR AUGUST, 1982 i

I None during this reporting period.

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' DESCRIPTION OF PERIODIC TESTS WICE kTRE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECECGCAL SPECIFICATIONS AUGUST, 1982 None during this reporting period.

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20 INSERVICE INSPECTION AUGUST, 1982 Units One and Two None during this reporting period.

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. REPORTAB2 OCC"JRRENCES PERTAINING TO ANY OUTAE OR POWER REDUCTIONS AUGUST, 1982 None during this reporting period.

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MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 MEOIANICAL MAINTENANCE AUGUST, 1982 None during this reporting pericd.

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HEALTH PHYSICS AUGUST, 1982 There was no single release of radioactivity or radiation exposure specifically associated with an outage that accounted for more than 10%

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