ML20065D027

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Monthly Operating Repts for Jul 1982
ML20065D027
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/12/1982
From: Costello O, Dunn S, Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20065C980 List:
References
NUDOCS 8209240372
Download: ML20065D027 (41)
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s e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 82-07 JULY, 1982 APPROVED BY: N %A Station Manager 4

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\ 6209240372 820012 l PDR ADOCK 05000280 R PDR I

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i E I Section a Page, Operating Data Report - Unit il 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 Lead Reductions Due to Environmental Restrictions - Unit #2 6 Average Daily Unit Power Level - Unit #1 7 Average Daily Unit Power Level - Unit #2 g Summary of Operating Experience g Amendments to Facility License or Technical Specifications 12 Facility Changes Requiring NRC Approval 13 Facility Changes That Did Not Require NRC Approval 13 Tests and Experiments Requiring NRC Approval 15 Tests and Experiments That Did Not Require NRC Approval 15 Other Changes, Tests and Experiment's 16 Chemistry Report 17 Description of All Instances Where Thermal Discharge Limits Were Exceeded 18 Fuel Handling 20 Procedure Revisions That Changed the Operating Mode Described in the FSAR 21 Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 22 Inservice Inspection 23 Reportable Occurrences Pertaining to Any Outage or Power Reductions 24 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 25 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 27

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Section Page Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 29 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 31 Maintenance of Safety Related Systems During 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 4

Health Physics Sunsnary 37 Procedure Deviations reviewed by Station Nuclear Safety and Operating Committee after Time Limits Specified in T. S. 38 i

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CCKET NO. 50-280 DATF C6 AUJ E2 C&VFLETE: EY SUE :. :UNN TELEPECNE 804-357-3'84 CEEMTILJ SIATUS
1. UbIT HAFE SURRY UNIT 1
2. EEP:RTIha PERIC: 70182 TC 73182
3. IJCEJSE: TEERNAL PGe'ER (%'T) 2441 l l
4. KAYEPUZE EATINJ (JECSS &'E) 84.5 lNCTES l
5. :ESIJJ ELE:TRICAL RATINJ tNET 5'E) 788
6. KAXTYUP :EPEN:AELE CAPACITY (JROSS n'E) 811
7. KAXIMUV :EPEN:ABLE CAPACITY (NET n'E) 775
8. 17 CEANJES CCCUE IN CAFACITY RATINJS N/A (ITE.15 3 TdRCUJE 7) SINCE LAST REP:RT, JIVE REASCNS
9. Ple'Es1 LEVEL TC WE12 RESIRICTE:, IF ANY N/A LUCI !&E)
10. REAS)RS FCR RESTRICTIONS, IF ANY N/A THIS NCNTE YR-TG- ATE CUMULATIVE
11. ECURS Ib REFORTINJ PERTC: 744.0 5087.0 84215.0
12. NUS:BER CF ECURS REACT &R WAS CRITICAL 736.6 4637.1 50671.6
13. EEACTOI: RESERVE SEUIDOWN ECUES 0.0 0.0 3731.5
14. ECURS JENEEATCR CN-LINE 725.7 4569.3 49644.1
15. UNIT RESERVE SEUT:CWh ECURS 0.0 0.0 3736.2
16. JECSS TdERNAL ENERJY JENERATE (INE) 1751564.0 10857907.0 115191173.4
17. JhCSS ELECTRICAL ENERJY JENERATE: (5'E) 543530.0 3419760.0 37238973.0
18. NET ELECTRICAL ENERJY JENERATE (5'E) 514302.0 3242167.0 35319403.0
19. l?.'IT SERVICC FACTCR 97.5 e/o 89.8 */* 58.9 */*
20. bEIT AVAILABILTTY FACICR 97.5 e/o 89.8 e/e 63.4 */e
21. UNIT CAFACITY FACICR (USINJ N:C NET) 89.2 */e 82.2 */e 54.1 */e
22. UNIT CAFACITY FACICR (USINJ DER NET) 87.7 */e 80.9 */e 53.2 el*
23. UNIT FChCE: GUTAJE RATE 2.5 e/e 4.2 e/e 23.9 e/e
24. SEUIWAS SGE:ULE: GVER NEXT 6 NGNTES FALL MAINTENANCE - 2n_ng ag_ 14 ggy, (TYPEATE.AN: :URATICS GF EAG)
25. IF SEUT CGWN AT EN: OF REPGRI PERIC:,

ESTIMATE : ATE CF STARTUP

26. UNITS Ib TEST STATUS FORECAST ACEIEVE:

(PRTGR TG CChWERCIAL CPERATIGN)

INITIAL CRITICALITY INITIAL ELECTRICITY CO.V.YERCIAL CPEEATICN

2 GPERATIlia :ATA hEPORT

0CKET NO. 50-281
ATE 06 AUJ 82 COMPLETE: BY C.J. COSIELLO TELEPECNE 804-357-3184 (FEM TIhJ STATUS
1. VI.IT HAXE SURRY Ul;IT 2
2. LEPORTII. PERIO: 70182 TG 73182
3. LICENSi;; THERVAL PCWER (5'I) 2441 l -l
4. NANEPLATE RATINJ (JROSS X.;E) 847.5 lNCIES l
5. :ESTJU ELECTETCAL RATIN: (ET 5'E) 788
6. l.:AXi.4UM :EPEN:ABLE CAPACITY (JROSS &T) 811 7.1'AXi.<Ub' :EPEN:AELE CAPACITY (KET ST) 775
8. IF CEAhJES OCCUR Ib CAPACITY hATII;as b/A (ITEVS 3 ZEROUJE 7) SINCE LAST LEPOR?, JIVE REASONS
9. PCWE.7 LEYEL TO VEIG ESTRICTE:. IF ANY N/A (liET INE)
10. hEA50HS F3R RESTRTCIIGh5, IF ANY N/A TEIS MONTE YR-TO- ATE CUMULATIVE
11. ECURS In E PORTINJ PERIO: 744.0 5087.0 81095.0
12. h7]NBER CF EOURS REACTOR WAS CRITICAL 744.0- 4532.1 49392.8
13. REA: TOR RESERVE SEUT:0WN 20URS 0.0 0.0 0.0
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. ECURS JENERATOR ON-LTNE 744.0 4461.2 48572.9

15. Ul;i? ESERVE SEUT:0WN EDURS 0.0 0.0 0.0
16. Jh0SS 2EERNAL ENERJY JENERATE: (AVE) 1805997.5 10042177.5 113339463.4
17. anCES ELECTRICAL ENERJY JENEM TE: (bME) 580480.0 3223905.0 36901084.0
18. GT ELECTRICAL ENERJY JENEMTE (bHE) 550489.0 3043453.0 3497216B.0
19. L7.IT SERVICE FACTOR 100.0 */* 87.7 e/* 59.9 */*
20. UKIT AVAILABILITY FACTOR 100.0 */* 87.7 e/o 59.9 e/o
21. UNIT CAPACITY FACTOR (USINJ bDC NET) 95.5 e/o 17.2 e/o 55.6 e/o
22. UNIT CAFACITY FACTOR (USINJ :ER s!ET) 93.9 e/o 75.9 */o 54.7 */*
23. Ul;IT FCRCE: GUIAJE RATE 0.0 3.7 */* 16.2 e/o

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24. SEUI: TWAS SGE:ULE: OVER GXT 6 MONTES FALL NAINTENANCE . ^11-05-82--10. Days ~

(ZYPE DATE,AN: :URATION OF EACE)

25. IE TEUT :SWN AT EN: OF REPORT PERIC:,

ESTIMATE : ATE CF STARTUP

26. UhITS Ih TEST STATUS FORECAST ACHIEVE:

(PRIOR TC COMYERCIAL OPEMTICN) 1NITIAL CRTTICALITY IhIIIAL ELECTRICITY CCA:YERCIAL GPERATION

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCK ET NO. 50-280 UNIT N AME surry 1 DATE hucust 9. 1982 COMf'LETED ny Vivian 11. Jones REPORT MONT11 July 1982 TELEPHeNE tand) is7-11R4 ext. 477 n.

.! E 3g Eh Licensee E c, Cause A Corrective N. e . Date h 3g jjE Event uY b"L Action to F

$E E Report # N0

}.;gg fU Prevent Recurrence c5 82-19 07-13-82 F 18.'3 G 3 82-02/03L-0 "B" Reactor trip bypass breaker was not racked in properly prior to Instrument Dept. testing of Train "B" Reactor Trip signals. '1his caused a Reactor Trip. Operators have been s.,

reinstructed on proper procedures for racking in reactor trip bypass breakers and verifyinci, pr,oper insertion of breaker in cubicle.

t I 2 3 4 F: Forced Reason: Method: Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Dat B-Maintenance or Test 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & Ucense Examination F Adninistrative 5 G-Operational Error (Explain) Eshibit I- Same Source l'r/77) Il-Other (E xplain)

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

UNIT NAME Surry 2 -

4 DATE Aucunt 9. 1982 COMPLETED RY Vivian II. Jones REPORT MONT11 Julv 82 TELEPHONE f an41 1s7-11nd ext. 477

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.$ E 3 h Ef Licensee Eg E"1, Cause & Corrective No. Date k 3g i jgg Event p Action to H

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RepwI 8r v) U f Prevent Recurrence 82-33 7-6-82 S 0.0 F Reduced power to load follow on orders of the System Operator.

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  • Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparailim of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3-Automaile Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E Operator Training & Ucense Examinalism F-Adninistrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source t*8/77) Il-Other (Explain)

5 LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: July, 1982 i

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DATE TILE HOURS LOAD, W REDUCTIONS, ifW WH REASON f

NONI DURING 1HIS REPORTING PERIOD.

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MONTHLY TOTAL

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6 LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTH: July, 1982 DATE TI!E HOURS LOAD, E' REDUCTIONS, ifW 53 REASON i

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NONI DURING THIS REPORTING PERIOD.

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I MONTHLY TOTAL

7 DOCKET NO 50-280 UNIT SURRY I DATE 8-1-82 COMPLEI C BY & J COSTELLO AVERAJE SAILY UNIT PNER LEVEL 6:3:15: JULY 82 AVERAJE EAILY POWER LEVEL AVERAJE CAILY POWER LEVEL

AY (WE-NFT) DAY (WE-NET) 1 730.1 17 718.8 2 718.8 18 720.5 3 723.6 19 730.1 4 725.2 20 717.6 5 729.6 21 716.0 6 730.0 22 717.4 7 729.0 23 717.9 8 718.9 24 713.1 9 707.7 25 711.4 10 723.7 26 709.6 11 726.5 27 705.8 12 725.3 28 706.4 13 420.5 29 710.6 14 228.4 30 705.8 15 670.9 31 713.5 16 718.2 DAILY UNIT P0w'ER LEVEL FOR4 INSTRUCTIONS -

GN HIS FORM, LYST THE AVERAGE DAILY UNIT POWER LEVEL IN WE-NET FOR EACE DAY IN THE REPORTIh3 MONTE. GESE FIJURES WILL BE USD TO PLOT A GRAPE FOR CACE REPORT-INJ NONE. NOTE GAT BY USINJ MAXIMUM DEPENDABLE CAPACITY FOR HE NET ELECTRICAL RAT:NJ OF TEE UNIT, HERE MAY BE CCCASIONS WEEN HE DAILY AVERAGE POWER EXCEE:S THE 100 e/o LINE (CR TEE RESTRICTE: POWER LEVEL LINE). IN SUG CASES, SE AVERAJE

AILY UNIT POWER CUTPUT SEEET SEGULD BE FOOTNOTE: TC EXPLAIN TEE APPARENT ANOMALY.

8 CGCKET NC 50-28i UNIT SUERY II DATE 8-1-82 COMPLETE: BY & J COSTELLC AVEhAJE DAILY Ui/IT PGWER LEYCL NOTIE: JULY 82 AYERA3E DAILY PCWER LEYEL AVERAJE DAILY POWEE LEYEL CAY (RdE-NET) DAY (X*E-NET) 1 746.3 17 741.1 2 745.5 18 742.3 3 745.4 19 746.3 4 745.6 20 734.6 5 748.1 21 740.2 6 708.6 22 739.4 7 744.8 23 738.5 8 743.0 24 - 735.8 9 743.1 25 726.0 10 747.2 26 735.0 11 746.6 27 738.4 12 742.6 28 738.7 13 741.7 29 732.3 14 740.0 30 740.5 15 740.3 31 744.6 16 740.1 CAILY UNIT PCWER LEVEL FORY INSTRUCTIONS CN TEIS FORN, LIST TEE AVERAJY DAILY UNIT PCWER LEYEL IN WE-NET FOR BACE DAY ZN THE REPORTINJ MONYd. IEESE FIGUEES WILL BE USED IG PLOT A JRAPE FOR EACE REPORT-INJ NCNTE. KCTE EAT BY USINJ MAXIMUN DEPENDABLE CAPACITY FOR BE NET ELECTEICAL RATING OF HE UNIT, GERE MAY BE OCCASIONS WEEN BE CAILY AVERAJE PCKER EXCEC:S TEE iC0 */e LINE (CR IEE RES?RICTE POWER LEYEL LINE). IN SUG CASES, TdE AVERA3E CAILY UN1? PCWER OUTPUT SEEET SECULD BE FCOTNOTE: TO EXPLAIN TEE APPAEENT ANOMALY.

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SU)01ARY OF OPERATING EXPERIETECE July, 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 CNE July 1 This reporting period begins with the unit at 100% power.

July 2 1154 - Turbine runback to 92t power on overtemperature AT signal. The runback signal was a result of OTAT setpoint reduction due to reduced primary pressure. The primary pressure reduction was a result of a problem encountered with a pressurizer spray valve.

1220 - Started power increase at 3% per hour.

1715 - The unit reached 100% power.

July 13 1400 - The reactor tripped as a result of instrument depart-ment testing of the "B" Train Reactor Trip signals with the "B" Reactor Trip Bypass Breaker improperly racked into the breaker cubicle.

1612 - The reactor is critical.

1828 - Chemist reported dose equivalent 1-131 was greater than 10 microcuries per cc. Started six hours clock for having unit shutdown.and cooled down to less 5000F.

2253 - The reactor was manually shutdown.

2330 - The reactor coolant system was less than 500oF.

July 14 0145 - Chemist reported dose equivalent. 1-131 was less than 10 microcuries per cc.

0405 - The reactor was critical.

0819 - The generator was placed on the line.

0842 - Stopped power increase at 35% power to verify secondary chemistry was in specification.

0900 - Secondary chemistry is in specification. Started increasing power at 3% per hour.

July 15 1335 - The unit reached 100% power.

10 July 21 2200 - The supply breaker for the 2G Screenwell Transformer tripped de-energizing four (4) of the seven (7) operating circulating water pumps. Power was reduced to 95% to allow throttling the circulating water flow through the main condenser.

2210 - Cross-tied the IG and 2G buses and restarted the circulating water pumps fed from the 2G bus.

2220 - Started increasing power at 3% per hour.

July 22 0100 - The unit reached 100% power.

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

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

July 6 0100 - Start power reduction at 150 MWe per hour Lc load follow on orders of the system operator.

0236 - Stopped load decrease at 69% power on orders of the system operator.

0438 - Started load increase on orders of the system cperator.

0700 - The unit reached 100% power.

July 20 1745 - Both RWST temperature indicators indicate 460F. Started 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> clock for hot shutdown based on exceeding maximum RWST

, temperature of 45 F.

1932 - Started power decrease at 150 MWe per hour.

2033 - Both RWST temperature indicators indicate 450F.

Stopped power decrease at 89% power.

2108 - Started increasing power.

2215 - The unit reached 100% power.

! July 21 2210 - Decreased load 25 MWe due to loss of four (4) of seven (7) operating circulating water pumps.

2239 - Increased power to 100%.

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l July 25 2115 - Decreased power 15 se due to . vacuum problems encountered while cleaning condenser waterboxes.

July 26 0518 - Increased power to 100%.

July 31 This reporting period ends with the Unit at 100% power.

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e AIENDM? .iS TO FACil.ITY 2.ICDISE OR' TECHNICAL' SPECIFICATIONS July, 1982 J .1

< I The Nuclear Regulatory Commission, on June 17, 1982, issued Amendment Nos.1 and 2' respectively. The changes have been designated

  • as Technical Specification change No. 88.
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These amendments revise the Technical' Specificat[ons to limit control rod misalignment to no more than + 12 steps indicated positions.

This change is consistent with the Standard Technical Specifications.

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Also, on page 3.16-2, a typographical error was corrected from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. *

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Accordingly, the paragraph 3.3 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. 78, 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 Spt.cifications contained in Appendix A, as rev.' sed through Amendment No. 79, are hereby incorporated in the .'.icense. The licensee shall operate the facility in " ,

accordance with the Technical Specifications."

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13 FACZLITY CHANGES REQUIRINO NRC APPROVAL July, 1982 None during this reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL July, 1982 Unit D/C 80-76 Process Vent 1&2 This design change improves the performance and reliability of the process vent system. This was accomplished by the installation of a moisture trap on the inlet to the process vent to prevent water ingress to the filter media.

Summary of Safety Analysis The modification will not create any safety problems. It will remove the water entering the system through the system input and give an indication in the control room if water enters the filter banks.

D/C 81-19 Machine Shop Replacement Facility 1&2 D/C 81-19E Machine Shop Replacement Facility -

. Electrical Systems and D/C 81-19F Machine Shop Replacement Facility -

Electrical Power Supply were implemented.

Summary of Safety Analysis The addition of the Machine Shop Replacement Facility

.Soes not minimize the ' safety of operating untis or effect the operation of safety related equipment.

D/C 81-30 Surry Main Switchyard and Gas Turbine Area Fire Protection 1&2 This design change provides a water supply and fire fighting equipment to the gas turbine area, material storage area and switchyard area.

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1 14 Summary of Safety Analysis 4 The modification will not reduce the safety of operating units, and fire protection capabilities to safety-related equipment will be maintained.

D/C 81-109 Steam Line to Auxiliary Boiler Drum Heater 1t2 mis design change provides a tie in fran the Dailding Heating System to supply the new Auxiliary Boiler Drum Heating Units. A steam heating element was installed in the lower drum of each of two Auxiliary Boilers during their recent retubing. The elements provide heat to the boiler during periods when the boilers are idle in order to reduce boiler startup time and reduce boiler corrosion.

Summary of Safety Analysis The addition of the steam line from the heating steam system to the Auxiliary Boiler drum heating element does not affect the operation of any safety-related equipment.

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15 TESTS AND EXPER2MENTS REQUXR2NO NRC APPROVAL July, 1982 1

1 None during this reporting period.

2 TESTS AND EXPERIMENTS 'IMAT DID NOT REQUIRE NRC APPROVAL July, 1982 cpecial Test No. Unit Title Completed ST-52 1 RCS Flow Measurement Data 07-01-82 ST-89 2 Flow Coastdown Measurement 07-22-82 ST-90 2 S/G Water Level, Stability and Control Demonstration .

07-22-82 ST-105 2 S/G Water Level, Stability and Control Demonstration 07-22-82 ST-106 1 Containment Sump Penetrations No. 66 and No. 69 07-22-82 ST-109 1 Engineered Safety Features Functional Test 07-22-82 ST-ll5 1 Chemical and Volume Control System Hot Functional Testing 07-22-82 ST-120 1 S/G Water Imvel, Stability and Control Demonstration 07-22-82 ST-134 1 S/G Moisture Carryover Measurement 07-22-82 l

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16 OTHER CHA!!GES, TESTS A2'D EXPERIMENTS July, 1982 None during this reporting period.

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17 SURRY POPER STATION CHEMISTRY REPORT July 19 82 T.S. 6.6.3.d PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERACE (A) Eo (A) Eo (A) Eo E-1 E-1 E-1 Cross Radioact., UCi/mi 6.64 2.02 3.35 4.86 1,64 2.62 Suspended Solids, ppm 0.1 0.1 0.1 0.1 0.1 0.1 E-1 5-1 E-1 E-1 E-1 E-1 Cross Tritium, UC1/mi 1.31 1.19 1.25 2.22 2.08 2.15

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(A) Eo (A) E-2 [A) E-1 E-3 E-3 E-3 Iodine-131, UCi/ml 6.72 9.22 4.77 4.21 1.23 2.06 I-131/I-133 1.5026 .8830 1.1499 1.8776 .4451 .9087 (C) (C)

Hydrogen, cc/kg 54.8 25.7 32.6 58.0 20.1 33.2 (B) ,

Lithium, ppm 1.45 .54 .85 1.35 1.05 1.24

Boron-10, ppm + 101.53 71.15 79.32 138.96 127.40 133.17 0xygen-16, ppm .000 .000 .000 .000 .000 .000 Chloride, ppa <.05 <.05 <.05 <.05 <.05 <.05 pH @ 25*C 6.96 6.47 6.77 6.69 6.56 6.62

+, Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (D)

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

Boron 890

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y-3 Sulfate -

Chromate 0.0 A

50% NaOH -

Chlorine -

REMARKS:(A) Activity levels indicate possible failed fuel (B) Two separate LiOH additions made (7-8-82) &(7-22-82) (C) Hydrogen levels too high-recommended reduce pressure on the VCI -

Unit #1 Rx trip 7-13 unit startup 7-14-82 (D) The levels of these chemicals should create no adverse environmental impact.

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18 DESCRIPTXON OF All XNSTAL'CES WHERE THEICIAL DISCliARGE LI!!ITS WERE EXCEEDED July, 1982 Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.

July 1, 1982 Exceeded 15 F AT across station

  • July 2, 1982 Exceeded 15 F AT across station July 3, 1982 Exceeded 15 F AT across station
  • July 5, 1982 Exceeded 15 F AT across station
  • July 6, 1982 Exceeded 15 F AT across station
  • July 7, 1982 Exceeded 15 F AT across station July 8, 1982 Exceeded 15 F AT across station July 9, 1982 Exceeded 17.5 F AT across station
  • July 10, 1982 Exceeded 15 F AT across station
  • July 12, 1982 Exceeded 15 F AT across station July 13, 1982 Exceeded 15 F AT across station
  • July 14, 1982 Exceeded 15 F AT across station
  • July 15, 1982 Exceeded 17 5 F AT across station
  • July 16, 1982 Exceeded 15 F AT across station
  • July 17, 1982 Exceeded 17 5 F AT across station July 18, 1982 Exceeded 17 5 F AT across station
  • July 19, 1982 Exceeded 15 F AT across station
  • July 20, 1982 Exceeded 15 F AT across station July 21, 1982 Exceeded 15 F AT across station July 22, 1982 Exceeded 15 F AT across station July 23, 1982 Exceeded 17.5 F AT across station July 24, 1982 Exceeded 17 5 F AT across station
  • July 25, 1982' Exceeded 17 5 F AT across station July 26, 1982 Exceeded 15 F AT across station
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July 27, 1982 Exceeded 17 5 F AT across station July 28, 1982 Exceeded 17.5 F AT across station July 29, 1982 Exceeded 15 F AT across station

  • July 30, 1982 Exceeded 15 F AT across station *
  • lndicates 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 30F per hour on July 13, 1982, due to a Unit I reactor trip. This event was allowable in accordance with Technical Specification 4.14.B.1. There were no reported instances of adverse environmental impact.

The temperature change at the station discharge exceeded 3 F per hour on July 21, 1982, due to a loss of four (4) of seven (7) operating circul-ating water pumps. The four (4) circulating water pumps were temporarily out of service due to an electrical malfunction. This event was reported in accordance with Technical Specification 4.14.C.I.

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20 FUEL HNTDLI!!G July, 1982 Units One and Two tione during this reporting period.

21 PROCEDURE REVISXONS TdAT CHANCED THE OPEPATYNG 110DE DESCRIBED YN THE FSAR July, 1982 None during this reporting period.

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23 DESCRIPTION OF PERXODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECIC;ICAL SPECIFICATIONS l

July, 1982 I

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23 INSERVICE INSPECTION July, 1982 i

No Inservice Inspections were performed on Units One or ?do.

24 REPORTABLE OCCURPINCES PERTAINXNG TO ANY OUTAGE OR PO*n'ER REDUCTIONS July, 1982 Hone during this reporting period.

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i Maintenance of Safety Related Systems During Outage or Reduced Power Periods July, 1982 i

None during this, reporting period.

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Instrument Maintenance D

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. HEALTH PINSXCS July, 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 10CFR20.

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38 PROCEDURE DEVIATIONS REVICTED EY STATION 17JCLEAP.

SAFETY AND OPERATING CO:D;ITTEE AFTER TUE LIMITS SPECIFIED 11; TECIMICAL SPECIFICATIONS I ~

July, 1982 Date Date SUSOC Procedure No. Unit Title Deviated Reviewed PT-18.2 2 Safety Injection System Tests 12-22-81 07-22-82 PT-17.2 1 Containment Inside-Recirculation Spray Pumps Tests' 07-09-82 07-30-82 a

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