ML20066D541

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Monthly Operating Repts for Sept 1982
ML20066D541
Person / Time
Site: Surry  
Issue date: 10/04/1982
From: Jones V, Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20066D540 List:
References
NUDOCS 8211110390
Download: ML20066D541 (40)
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VIRGINIA ELECTR1k AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 82-09 SEPTEMBER. 1982 APPROVED BY:

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Station Manager o

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8211110390 821014 DR ADOCK 05000280 PDR 6

i Section Page g

k 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 il 5

Load Reductions Due to Environmental Restrictions - Unit (2 6

7 Average Daily Unit Power Level - Unit #1 8

Average Daily Unit Power Level - Unit #2 Summary of Operating Experience 9

Amendments to Facility License or Technical Specifications 11 12 Facility Changes Requiring NRC Approval 13 Facility Changes That Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval 15

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Tests and Experiments That Did Not Require NRC Approval 15 Other Changes, Tests and Experiments 16 Chemistry Report 17 Description of All Instances Where Thermal Discharge Limits 18 Were Exceeded Fuel Handling 19 Procedure Revisions That Changed the Operating Mode Described in 22 the FSAR i

Description of Periodic Tests Which Were Not Completed Within.the 23 8

Time Limits Specified in Technical Specifications 24 Inservice Inspection Reportable Occurrences Pertaining to Any Outage or Power Reductions 25 Maintenance of Safety Related Systems During Outage or Reduced Power 26 Periods - Unit #1 - Mechanical Maintenance 28 Maintenance of Safety Related Systems During Outage or Reduced Power

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Periods - Unit #2 - Mechanical Maintenance o

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Maintenance of Safety Related Systems During Outage or Reduced Power 29 Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 31 Periods - Unit #2 - Electrical Maintenance 32 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance 34 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance 35 Health Physics Sumnary 36 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee af ter Time Limits Specified in T. S.

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CPERA."ING DATA REPCRT

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LCCKET NC. 50-280 DATE 04 CCT 82 C0MPLI7ED Sy VIVIAN H. JONES

."ELEPECNE 804-357-3:84

.C.E.Eh..A T..:.N..G S.T.A.T.U.S.

1. Uhl: NAYF SUREY UNIT 3
2. EEFCRTIhG PER:CD 9r382 TG 930e2
3. L:CEkSE:. EFRKAL PCWER (MWT) 244:

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4.

NA%EFL ATE R ATING (GROSS NWF) 847.5 l NOTES l

E. :ES:3.7 ELECTRICAL EA."ING (NET NVE) 788 6.

VAXTYUM DEPENDABLE CAPAC:."Y (GRCSS NWE) 821

7. NAX:VUX CEPEd:A5LE CAFACITY (NET RWT) 775
8. :F CEANSEC CCCUR IN CAPACITY RAT:NGS N/A (ITE\\S 3 TEROUGH 7) SINCE LAS*

EEFCET, G:VE REASCNS

9. FCWER LEVEL TC WEICE REFTEICTE, :F ANY N/A (NIT W )
10. EEASCNS FCE RESTh:CT:0NS, :F ANY N/A TEIS MONTE YR-TC-DA."E CUXULA."ZYF

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1. ECUES IN REFChTING PERIOD 720.0 655

.0 85679.0

'62.

NUVSEh CF ECUhS REACTOR WAS CR:."ICAL 720.0 6088.2 52:22.7

13. EEACTCR RESERVE SEUTCOWN ECURS 0.0 0.0 3731.5
14. ECURS GENERATOR GR-LINE 720.0 6036.9 5:093.7
15. UN:

RESERVE SEUTD0Vh' ECURS 0.0 0.0 3736.2

16. GRCSS TEERNAL ENERGY GENERATES (NWE) 1746999.8 1432t:586.5 138657852.9
17. GRCSS ELECTRICAL ENERGY GENERATED (MWE) 5453:5.0 4498615.0 38337928.0
18. NET IIECTRICAL ENERGY GENERATED (NWE) 536339.0 4262702.0 36339938.0
19. UNIT SERVICE FACTCR 300.0 */*

91.8 e/o 59.6 */ e

20. UNZ." A VAILA EILI."Y FACTOR 100.0 e/o 91.8 e/o 64.0 */*
21. UNIT CAPACITY FAC."CR (USING NBC NE.")

92.5 e/o 84.0 ele 54.7 */*

22. UNIT CAPACITY FACTCR (USING DER NET) 93.0 e/o 82.6 e/o

$3.8 ele

23. UNIT FCECED CUTAGE RA"E 0.0 3.5 */*

23.4 */=

24. SEUT00VNS SCHEDULET GVER NEXT 6. SNTES 2/1/83 - 74 days - Refueling /10 yr. 151

(."YEE,[ ATE AND DURATION OF EACE)

25. :F SEUT [Cn'N A." END OF REPGRT PERIGD, EETIY A:E DATE OF STARTUP
26. UNITS IN TES." STATUS FORECAST ACHIEVED (PR:CR TO COX.VERCIAL GPERA."ICN)

Ib1TIAL CRITICALITY INITIAL ELECTRICI.*Y CCMMEnCIAL GPERATION

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e GPERATING DATA REPGRT FCCKET NC. 50-281 TATE 04 GCT 82 CON?LETET By VIV1AN M. JONES TELEPECNE 804-357-3164 CFTh4 TING ETATUS

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1. UNIT NAki SURh! UNIT 2
2. hEPORTING PERIOD 90182 TO 93082
3. L: CENSED TEFEMAL PGWER (NWT) 2441 l~~~~~~~~~~~~~~~~~~~~~~~~l 4.

KANTFLATE RATING (GROSS MVF) 847.5 l NOTES l

5. :ESIGN ELECTRICAL RATING (NET NWE) 788
6. NAX:\\UY TEPENTABLE CAPACITX (GROSS 4WE) 8:1
7. NAX:%lUY TEPENDABLE CAPACITY (NET WWE) 775 D. IF CEAVGES GCCUR Zh CAPACITY RATINGS N/A (ITEVS 3 TERCUGH ?) SINCE LAST REPORT. GIVE REASONS
9. PCo'Eh LEVEL TO WEICE RESTRICTED, IF ANY N/A (NET NWE)
10. RFASONS FOR RESTRICTIGNS. IF ANY N/A TEIS MGHTH YR-TC-: ATE CUNULATIVE

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  • 1. ECUh5 IN REPORTING PERICD 720.0 6553.0 82559.0 1
2. NUN 5ER OF ECURS REACTOR WAS CRITICAL 720.0 5996.1 50856.8
13. REACTOR RESERVE SEUTDOWN HOURS 0.0 0.0 0.0
14. EGURS GENERATOR ON-LINE 720.0 5925.2 50036.9
35. UNIT RESERVE SEUTDOWN ECURS 0.0 0.0 0.0
16. GROSS TEERNAL ENERGY GENERATED (MVE) 1740572.6 33593469.3 116890755.0
17. GROSS ELECTRICAL ENERGX GENERATED (MWE) 568135.0 4375525.0 38052704.0
18. NET ELECTRICAL ENERGX GENERATED (MWE) 538620.0 4335015.0 36063730.0
19. UNIT SERVICE FACTOR 100.0 */*

90.4 */*

60.6 */*

20. UNIT AVAILAEILITY FACTOR 100.0 */*

90.4 e/*

60.6 */o

21. UNIT CAPACITY FACTOR (USING NDC NET) 96.5 */*

81.4 e/o 56.4 */*

22. UNIT CAPACITY FACTOR (USING DER NET) 94.9 */o 80.3 e/o 55.4 e/o
23. UNIT FCRCED GUTAGE RATE 0.0 4.9 e/o 28.6 e/o 24 SEUTTOWNS SCEEDULED CVER NEXT 6 MONTES FALL NAINTENANCE 12-8 2-10 DAYS iTIPE.DATE.AND DURATION OF EACE)
25. IF SEUT DOWN AT END OF REPORT PERIOD.

ESTINATE DATE OF STARTUP

26. UhITS IK TEST STATUS FORECAST ACHIEVED (PRICR TO CGNVERCIAL CPERATION)

' INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL GPERATION e

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i 50-280 DOCKET NO.

UNIT SitUTDOWNS AND POWER REDUCTIONS UNIT NAME Surry 1 DATE 10-07-82 REPORT MONTH Sept. 1982 COMPLETED gy Vivian H. Jongs TELEPHONE (804)357-3184x477 i

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Licentee

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Cause & Correcilve k

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NONl : DURING THIS REPORT. NG PERIOD.

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Method:

Exhibit G lastructions F: Fenced Reason:

S: Scheduled A-Equipment Failure (Emplain)

1. Manual for Preparaske of Data B. Maintenance of Test 2-Manual Scram.

Enity Sheets for Licensee C Refueling 3 Automatic Scram.

Eveni Report (LE RI File (NUREG-D Regulatory Restriction 4-Other (Emplain) 0161)

E Operator Training & Ucense Enaminathm 5

F Administrative Exhibit I - Same Source G. Operational Error (Emplain) l'8/77)

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i 50-281 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Surry 2 DATE 10-07-82 Sept. 1982 COMPLETED gy Vivian H. Jones REPORT MONTil TELEPflONE (804) 357-3184 x477 i an 3 5

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ce,se a co,,,cig,,

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Date

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Action to F

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1 82-34 9-5-82 S

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4 Reduced power to load follow on orders of the l

System Operator i

82-35 9-6-82 S

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4 Reduced power to load j-follow on orders of the I

System Operator.

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F: Forced Reason:

Method:

Exhibit G. Instructions S: Scheduled A Equ6pment Failure (Emplain) 1-Manual for Preparation of Data 8-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C ReIveling 3 Automatic Scram.

Event Report (LER) File (NUREG-D Reguistory Restslction 4-Oiher (Explain) 0161) l E-Operatur Training & tJcense Examination F-Administrative 5

i G. Operational Error (Explain)

Eihlbit i. Same Simsce t'8/77 )

Il-Other (Emplaini 1

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LOAD REDUCTIONS DUE TO ENVIRONMENT /L RESTRICTIONS MONTH:

S*Pt., 1982 UNIT NO. 1 DATE TIME HOURS LOAD. W REDUCTIONS. W MWH REASON NONE DUltING THIS REPORTIN'; PERIOD.

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MONTHLY TOTAL

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O LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTE:

S*Pt., 1982 DATE TIME HOURS

_ LOAD. NW REDUCTION 2. W MWE REASON NONE DURIUG THIS REPORTING PERIOD.

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MONTHLY TOTAL

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DSCEET NC 50-260 UNIT SURRY Z DA."E 30-1-82 CCYPLITED BY VIVIAN H. JONES AVERAGE TA:LY UNIT PCWER ZEVEL

%:).7.T : SEP"EYBER e2 AVERAGE DAILY PCWER LEVEL AVERAGE CAILY PCWER II"El

[AY (5'E-NET)

DAY

(%'E-NE.")

1 711.0 26 706.5 2

724.4 17 729.4 3

726.8 28 726.9 4

716.5 19 738.2 5

720.0 20 720.2 6

722.0 21 720.3 7

723.6 22 735.0 8

724.8 23 715.2 9

723.2 24 726.3

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10 722.3 25 716.4 11 720.8 26 717.5 12 738.7 27 73 6.2 23 733.5 26 7:4.3 14 706.0 29 713.9 25 707.3 30 738.9 LAILY UNI." PCJER LEVEL FORY INSTRUCTIONS GN TE:S FORN. LIS" TEE AVERAGE DAILY UNIT PCWER LEVEL IN n'E-NE." FOR EACE DAY IN TEE MPOR"ING MCNN. MESE FIGURES WILL BE USED TC PLO." A GRAPH FOR EACH REPOR"-

ING NCNN.1.C'E 2AT BY UEING MAXIMUM DEPENDABLE CAPACITI FGR GE NET ELECTHCAL RA"IEG 0F 3 E UNIT, 3ERE MAY BE OCCASIONS WEB K E DAILY AVERAGE PCWER EXCEEDS TEE 100 */*. LINE (GR 3E RESTRIC.ED PG'ER EZYEL LINE). IN SUCE CASES, ME AVERAGE DAZZZ UNIT l'CHER CUTPUT SEEET SHCULD BE FCOTNC."ED TO EXPLAIN NE APPAENT ANGNALY.

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DCCEET NC 50-28:

U:::: SUEhY ::

DATE 10- -82 C(yp5ETEr Ey VIVIAN H. JONES A"EEAG: :A:LY US:T PWEF LE.'EL h.'1TEs S.'? TEA:hER 82 AVERAGE :A:LY PWEh LEV =L AVERASE DA:LY PNER LEVEL C47

(%'E-NET)

TAY

( WE-NE.")

1 751.6 16 750.7 2

753.3 17 752.4 3

749.5 28 752.0 4

744.7 19 749.6 5

693.9 20 749.5 6

681.8 21 747.1 7

755.7 22 753.4 8

754.9 23 756.0 9

757.7 24 755.3

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10 757.0, 25 755.1 il 754.0 26 12 752.7 27 756.8 23 750.0 28 751.2 14 745.5 29 755.9 15 748.1 30 754.3 CA:LY 04:" ECWER LEVEL FGRA: INSTnUCT:GNS CN 31S FJRn', LIST THE AVERAGE DAILY UNIT PWER LEVEL IN 5'E-NET FOR EACE CAY IN THE REPCR"ING MON 3. 3ESE FIGUEES WILL BE USED TG PLCT A GRAPH FOR EACE REPCR"'-

ING NCNN. NOTE 3AT BY US:NG XAXINUN DEPENDABLE CAPACITY FCn 3E NE."' ELEC"E: CAL hA':NG OF 3E UNIT, 3ERE MAY BE CCCASICNS WEEN ME TA:LY AVERAGE PWER EXCEEDS TEE 3 C0 e/7. LINE (CR WE RESTRICTED PRER LEVEL L:NE). :N SUG CASES, NE AVERAGE CAILY UNIT PWER CUTPUT SEEET SECULD BE FG0"NCTED TO EXPLA:N 35 APPARENT ANCMALY.

SUMMARY

OF OPERATING EXPERIENCE September, 1982 k.

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 September 1 This reporting period begins with unit at 100% power.

September 12 2319 - Turbine runback to 735 MWe/97% power. The runback was caused by a spike on Channel III over-temperature AT Protection with Channel I in trip due to a problem with excore detector N-41.

2325 - Started increasing power to 100% - at 3% per.

hour.

September 13 0030 - The unit reached 100% power.

September 17 0745 - Chemist reported feedwater pH of 7.5.

Commenced reducing power in preparation for going to Hot Shutdown in accordance with Abacrual Procedure

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33 due to low pH of the feedwater.

0754 - Chemist reported feedwater pH of 8.1.

Stopped ramp and returned unit to 100% power. The cause of the low feedwater pH was found to be that the ammonia injection pump had tripped off.

September 30 This reporting period ends with the unit at 100% power.

UNIT TWO September 1 This reporting period begins with the unit at 100% power.

September 5 0102 - Commenced reducing power to load follow on orders of the System Operator.

i 0350 - Stopped reducing power at 525 MWe/65% power on l

orders of the System Operator.

0703 - Started increasing power on orders of the System Operator.

0900 - The unit reached 100% power.

1 September 6 0038 - Commenced reducing power to load follow on orders of the System Operator.

SUMMARY

OF OPERATING EXPERIENCE PAGE 2 0340 - Stopped reducing power at 450 MWe/55% power on

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orders of the System Operator.

0549 - Started increasing power on orders of System Operator.

1130 - The unit reached 100% power.

September 30 This reporting period ends with the unit at 100% power.

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f AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS September, 1982 None during this reporting period.

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I FACILITY CHANGES REQUIRING NRC APPROVAL September, 1982 None during this reporting period.

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FACILITY CRANGES THAT DID NOT REQUIRE NRC APPROVAL September. 1982

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D/C 80-22 (orpholine and Hydrozine Injection Into the Bearing 1&2 UNIT Cooling System This design change replaces the addition of chromates in the bearing cooling system with filming amines to comply with State Water Control Board discharge limitations to provide corrosion protection. This required a tap off of the present chemical feed pumps discharge with the line tied into the bearing cooling system.

SUMMARY

OF SAFETY ANALYSIS The modification does not affect the station or the operation of any safety related equipment.

D/C 80-51 Post-Accident Monitoring and Control Panel 1

This design change provides Post-Accident Monitoring Indication and Control in the control room as required by TMI-2, NREG-0578 and subsequent clarifications contained in the NRC letter dated October 30, 1979.

SUMMARY

OF SAFETY ANALYSIS f

This modification does not affect norms.1 station operation of

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any safety related systems. The Technical Specifications and FSAR are not affected by this design change.

D/C 80-62 Storm Drain Radiation Sampling System 1&2 l

This design change added recording flow meters and automatic waste water samplers to four storm drain release points. The water is sampled to ensure that radioactive contaminants are not inadvertently discharged into the river.

SUMMARY

OF SAFETY ANALYSIS The addition does not affect the operation of any safety related equipment nor will it affect the implementation of any station procedures.

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D/C 80-74 Manual Lineup of Air Ejector Vent 1&2 This design change eliminated the requirement of additional effluent monitors for the extended range capability.. The condenser air ejector discharge lines shi.ll be rerouted having new connections upstream of the Ventilation Vent Stack high range effluent monitor for use during accident conditions.

SUMMARY

OF SAFETY ANALYSIS The modification does not affect the operation of any safety-related equipment. It provides greater flexibility in system operation under high radiation or loss of normal effluent monitoring.

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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL PAGE 2 UNIT D/C 81-12 Liquid Waste Monitor RM-LW-108 Relocation 1&2 This design change relocated liquid waste monitor (RM-LW-108). The radiation monitor was giving false indications of radiation levels due to high back-ground, internal contamination and crude build up.

SUMMARY

OF SAFETY ANALYSIS The modification will improve the performance of liquid waste disposal system. Relocation of piping to allow monitoring of the effluents from a low backgroud area will not violate the intent of the Technical Specifications nor the FSAR.

D/C 81-19 Machine Shop Replacement Facility 1&2 D/C 81-19G Machine Shop Relocation Facility-Sprinkler System portion was implemented.

SUMMARY

OF SAFETY ANALYSIS

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The addition of the MSRF does not minimize the safety of operating units or effect the operation of safety-related equipment.

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TESTS AND EXPEM MENTS REQUIRING NRC APPROVAL

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September, 1982 None during this reporting period.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL September, 1982 Special Test No.

Title Unit Date Completed ST-52 RCS Flow Measurement Data 1, 2 09-16-82 ST-145 Auxiliary Building Vent -

1, 2 09-30-82 Vent Delay Time Test

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1 OTHER CHANGES, TESTS AND EXPERIMENTS l

September 1982 None during this reporting period.

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f-SIERY FO'.'ER STATION CORRECIED COPY CHEMISTRY REPORT e

a August 19_ 82 T.S. 6.6.3.d COON UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MATIMUM MINIIRH AVEPACE Cross Radioact., UCi/ml

( A) 5. 73 1.74 3.13 8.60 1.62 2.39 Eo Eo Eo E-1 E-1 E-1 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 Tritiu=, UCi/ml 1.34 6.10 1.08 3.38 2.50 3.03

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Eo E-2 Eo E-J t-4 t-a Iodine-131, UCi/ml 8.20 8.24 1.28 9.27 7.92 2 14 I-131/I-133 1.6800

.8165 1.0900 1.6502

.3189

.7665 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 1.2b Boron-10, ppm +

118.97 57.43 68.21 127.40 115.25 122.89 (E)

Oxygen-16, ppm

.005

.000

.000

.000

.000

.000 Chloride, ppm

<,05

<.05

<.05

<.05

<.05

<.05 pH @ 25'C 7.12 6.54 6.85 6.99 6.64 6.74

+. Boron Total Boron x 0,196 NON-P.ADI0 ACTIVE CHEMICAL RELEASES, POUIGS T.S. 4.13.A.6 l

Phosphate 0.0 (F)

Boron 564 (F) y-Sulfate c.c (F)

Chromate 0.0 (F) 3 50% NaOH 04 (F)

Chlorine (F) oc REMARKS: (A) High activity level following reactor trip 8/24; (B) PC-4 not in service used NC-2; (C) Hydrogu level too low (following reactor trip); recommended increased 1

pressure on VCT.

(D) Four separate lithium additions 8/6, 8/10, 8/17, & 8/27; (E) follouirrg reactor trip; (F) The levels of these chemicals should create no adverse environmental impact.

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SURRY POER STATION CHDf1STRY REPORT l

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Sept.

19 82 T.S. 6.6.3.d PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVEPAGE Gross Radioact., UCi/ml 3.85 2.49 2.98 5.01 1.78-1 2.67

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-1 Suspended Solids, ppm 0.1 0.1 0.1 0.1 0.1 0.1

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Gross Tritium, UCi/ml 2.92 8.64 1.58 2.01 1.71" 1.90

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Iodine-131, UCi/mi 2.10-1 6.76~

9.73-2 4,91-3 9.83-4 2.25-3 I-131/I-133 1.8218

.5867

.9837 1.6538

.3442

.8066 (B)

Hydrogen, cc/kg 32.2 24.6 28.6 39.9 25.6 32.0 Lithium, ppm (C) 1.20

.67

.87 1.45

.97 1.22' Berca-10, ppm +

57.04 41.55 49.03 117.40 103.10 109.90 Oxygen-16, ppm

.000

.000

.000

.000

.000

.000 Chloride, ppm __

<.05

<.05

<.05

<.05

<.05

<.05 pH 0 25'C 7.17 6.90 7.05 6.85 6.62 6.72

+ Boron Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS

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T.S. 4.13.A.6 l

Phosphate (D)

Boron 772.

(D) l y-Sulfate (D)

Chromate 0.0 (D) 3 50% NaOH (D)

Chlorine (D) 1 REMARKS: (A) High activity level due to secured let-down flow (for 40 hrs) prior to this l

c eple. (B) Unable to sample hot leg for 10 days prior to this sample; recommended increase 1

in VCT pressure. (C) Five separate lithium additions unit 1; two separate addtions unit 2.

(D) The levels of these chemicals should create no adverse environmental impact.

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r DESCRIPTION OF ALL INSTANCES WHERE THER?tAL DISCllARGE lit!ITS WERE EXCEEDED September. 1982 s

Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.

Exceeded 15'F AT across station

  • September 1 Exceeded 15'F AT across station
  • 2 Exceeded 15'F AT across station
  • 3 Exceeded 15'F AT across station
  • 4 Exceeded 15'F AT across station
  • 5 7 -- Exceeded 15'F AT across station
  • Exceeded 15'F AT across station
  • 12 Exceeded 15'F AT across station 13 Exceeded 15'F AT across station
  • 14 Exceeded 15'F AT across station
  • 15 Exceeded 15'F AT across station
  • 16 Exceeded 15'F AT across station
  • 18 Exceeded 15'F AT across station

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19 Exceeded 15'F AT across station 20 Exceeded 15'F AT across station 21 Exceeded 15'F AT across station 22 Exceeded 15'F AT across station

  • 23 Exceeded 15'F AT across station
  • 24 Exceeded 15'F AT across station
  • 25 f

26 Exceeded 15'F AT across station

  • Exceeded 17.5 F AT across station
  • 28 Exceeded 15'F AT across station 29 Exceeded 15'T AT across station 30
  • Indicates dates where station AT was less than or equal to 15.0*F across station for some time during the day.

These AT excursions were allowable under Technical Specification 4.14.B.2.

There were no reported instances of adverse environmental impact.

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FUEL MANDLING s

September. 1982 The originally installed cask drop pad, designed to absorb the impact of a shipping cask dropped in the Spent Fuel Pit, was removed September 28, 1982 in preparation for the installation of a cask drop pad of more modern design.

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UNIT 1 FUEL HANDLING DATE NO. OF ANSI NO.

NEW OR SPENT FUEL SHIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL NONE DURING THIS R1; PORTING PERIOD.

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1 UNIT 2 SEPTEMBER, 1982 FUE MLIE DATE NO. OF ANSI NO.

NEW OR SPENT FUEL

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SHIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL i

NONE DURING THIS REPORTING PERIOD.

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PROCEDURE REVISIONS THAT CHANGED TH_E OPERATING MODE DESCRIBED IN THE FSAR i

SEPTEMBER, 1982

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None during this reporting period.

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DESCRIPTION OF PERIODIC TTSTS WHICH WERE NOT COMPLETED' WITHIN

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THE TIME LIMITS SPECIT'.ED IN TECHNICAL SPECIFICATIONS i

.SEPTEFEER - 1982 o

r PT-18.4 Boron Injection Tank Level Check - was not completed as scheduled on 7-27-82 for Unit 2.

This PT is to verify that the boron injection tank remains full during plant operations. Station deviation report S2-82-219 was sWbmitted and the test was completed satisfactorily on 8-1-82.

i PT-2.27 Core Cooling Monitor - was not completed as scheduled on 8-5-82 for Unit 2.

This PT provides a step by step functional test of the Core Cooling Monitor.

Station deviation report S2-82-235 was submitted, and the test was completed satisfactorily on B-18-82.

PT-2.26 Reactor Coolant System Pressure (Functional Test) and (P-1-403) Testing of PORV (Unit 1) This test is to periodically stroke valves to (P-1-458) monitor proper valve operation. Mov-1535 and MOV-1536 were not cycled

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sithin 90 days as specified in this test and station deviation report SI-(2-322 was submitted. On 6-19-82 the valves were cycled.

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PT-16.5 containmont Personnel Air Lock Test (Unit 1) - was performed 10-4-81 and scheduled to be performed again 4-4-82.

However, the test was not performed within the + 25% grace period, and station deviation report Sl-82-291 was

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submitted. The test was completed satisfactorily on 6-4-82.

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INSERVICE INSPECTION l

SEPTEMBER, 1982 None during this reporting period.

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1 REPORTAB7E OCCURRENCES PERTAINING TO ANY OUTAGE OR POWER REDUCTIONS SEPTEMBER 1982 None during this reporting period.

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MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 INSTRUMENT MAINTENANCE September, 1982 None during this reporting period.

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g 8 J HEALTH PHYSICS

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SEPTEMBER, 1982 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 10CRF20.

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PROCEDURE DEVIATIONS REVIEWED BY STATIO1111UCLEAR SAFETY AND OPERATING C0mi1TTEE AFTER TI!!E LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS DATE SNSOC PROCEDURE NO.

UNIT TITLE DATE DEVIATED REVIEWED PT 2.1 1

Overpower - Overtemperature 08/18/82 09/02/82 (T-1-432)

Delta T Protection (T-1-412, 422, 432)

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