ML18139B168

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Monthly Operating Repts for Feb 1981
ML18139B168
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/05/1981
From: Dunn S
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139B167 List:
References
NUDOCS 8103170338
Download: ML18139B168 (42)


Text

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e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 81-02 FEBRUARY, 1981 APPROVED: ~ ~ M -

  • MANAGER 1s*1os 170J31S*

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e e CONTENTS Section Operating Data Report - Unit i!l 1 Operating Data Report - Unit 112 2 Unit Shutdowns and Power Reductions - Unit ill 3 Unit Shutdowns and Power Reductions - Unit 112 4 Load Reductions Due to Environmental Restrictions - Unit DI 5 Load Reductions Due to Environmental Restrictions - Unit 112 6 Average Daily Unit Power Level - Unit ill 7 Average Daily Unit Power Level - Unit i/2 8 Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 10 Facility Changes Requiring NRC Approval 11 Facility Changes That Did Not Require NRC Approval 11 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 16 Exceeded Fuel Handling 17 Procedure Revisions That Changed the Operating Mode Described In The 19 FSAR Description of Periodic Tests Which Were Not Completed Within The 20 Time Limits Specified In Technical *specifications Inservice Inspection 21 Reportable Occurrences Pertaining to Any Outage or Power Reductions 23 Maintenance of Safety Related Systems During Outage or Reduced Power 24 Periods - Unit ill - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 28 Periods - Unit #2 - Mechanical Maintenance

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" . e CONTENTS Section Maintenance of Safety Related Systems During Outage or Reduced Power 30 Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or .Reduced Power 32 Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 34 Periods - Unit ill - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 36 Periods - Unit #2 - Instrument Maintenance Health Physics Summary 38 Procedure Deviations Reviewed by Station Nuclear Safety and 39 Operating Committee After Time Limits Specified in T.S.

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.OPERATING DATA REPORT DOCK3T NO. 50-280 DATE OS MAR 81 COMPLETED BY SUED. DUNN TELEPHONE 804-357-3184 OPERATING STATUS

1. l/NIT NAME SURRY UNIT 1
2. REPOR'1'ING PERIOD 20181 TO 22881
3. LICENSED THERMAL POWER (WT) 2441 1----------
4. NA&'i'LATE RATING (GROSS MIE) 847.5 INOTES
5. DESIGN EI&CTRICAL RATING (NET WE) 822 I
6. MAXINllM D'3PENDABLE CAPACITY ( GROSS MWE) 740
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 704
8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA

'l-(ITEMS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY NIA (NET MwE)
10. REASONS FOR RESTRICTIONS. IF ANY NIA THIS MONTH YR-TO-DATE CUMULATIVE
11. HOURS IN REPORTING PERIOD 672.0 1416.0 717.84.0
12. NUMBER OF HOURS REACTOR WAS CRITICAL o.o o.o 42538.5
13. REACTOR RESERVE SHUTDCMN HOURS o.o o.o 3731.5
14. HOURS GEN'3RATOR ON-LINE o.o o.o 41668.8
15. l/NIT RESERVE SHl/TDCMN HOURS o.o o.o 3736.2
16. GROSS THERMAL ENERGY GENERATED (MWH) o.o o.o 96389401.0
17. GROSS ELECTRICAL ENERGY GENERATED (WH) o.o o.o 31301743.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) o.o o.o 29699924.0
19. UNIT SERVICE FACTOR o.o o.o 58.0 olo
20. l/NIT AVAILABILITY FACTOR o.o o.o 63.3 ~lo
21. UNIT CAPACITY FACTOR (USING MDC N~) o.o o.o 58.8 olo
22. l/NIT CAPACITY FACTOR (USING DER N!!T) o.o o.o 50.3 olo
23. UNIT FORCED Ol/TAG:: RATE o.o o.o 26.4 o/o
24. SHUTDCNNS SCHEDULED OVER NEXT' 6 MONTHS (TYPE.DATE.AND DURATION OF EACH)

./

25. IF SHUT DCNN AT END OF REPORT P3RIOD. Juir .1}Stts1~.*

ESTIMAT3 DATE OF STARTUP

26. UNITS IN TEST STATUS FORECAST ACHIEVED

"(PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

  • ------- ------------- .r:----* '

',. e OPERATING DATA IBPOKr DOCKET NO. 50-281 DATS 05 MAR 81 COMPUTED BY .ijlJE D. DUl~N

  • TELEPHONE 804-357-3184 OPERATING STATUS
1. UNIT NAME SURRY UNIT 2 2
  • R:!.""POKrING PERIOD 20181 TO 22881
3. LICENSED THERMAL POWER (Mr/T) 2441 .1--------, *
4. NAMEPLATE RATING (GROSS WE) 847.5 !NOTES I
5. DESIGN ELECTRICAL RATING (NET WE) 822 I I
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MIE) 811 I I
7. MAXIMUM DEPENDABLE CAPACITY (NET WE) 775 I I
8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE LAST REPOKr. GIVS REASONS*:
9. PrNER LEVEL TO WHICH RESTRICTED. IF ANY NIA (NET WE)
10. REASONS FOR RESTRICTIONS. IF ANY NI A THIS MONTH IR-TO-DATE CUMULATIVE
11. HOURS IN REPORTING PERIOD s12.o 1416.o* 68664.o 12 *. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 ~416.0 39200.0
13. REACTOR IBSERVE SHUTDOWN HOURS o.o o.o o.o
14. HOURS GENERATOR ON-LINE 672.0 1416.0 38552.6
15. UNIT RESERVE SHUTDalN HOURS* o.o o.o o.o 16 ~ GROSS THERMAL ENERGY GENERATED (WH) 1637682.0 3452663.0 89907324.0
17. GROSS ELECTRICAL ENERGY GENERATED (WH) 536035.0 1130160.0 29369154.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 508432.0 1072035.0 27850523.0
19. UNIT SERVICE FACTOR 100.0 o/o 100.0 o/o 56.1 o/o
20. UNIT AVAILABILITY FACTOR 100.0 o/o 100.0 o/o 56.1 o/o
21. UNIT CAPACITY FACTOR (USING MDC NET) 97.6 o/o 97.7 o/o 52.3 o/o
22. UNIT CAPACITY FACTOR (USING DER NET) 92.0 o/o 92.1 o/o 49.3 o/o
23. UNIT FORCED OUTAGE RATE 0.0 0.0 19.* 2 o/o
24. SHUTDrNNS SCHEDULED OVER NE'X!r 6 MONTHS SNUBBER INS~CTION & SPRING ..

(TYPE.DATE.AND DURATION OF EA~) MAINTENANCE -.'APRIL, 1981 - .*10 DAYS

25. IF SHUT Da!N AT END OF REPORT PERIOD.

ESTIMATE DATE OF STARTUP

26. UNITS IN TEST STATUS FORECAST ACHIEVED.

(PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION


~---*- ----*--- ____ .,....._._ -----------*

UNIT SIIUIDOWNS AND POWER Rl!PUCTIONS DOCKET NO. __,,___s-.o_-2=8:;.;;o____

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l>ATE March 4. 1981 ~

REPORT MON111 February COMl'I.ETED IIV SUED. DUNN TELEI IIONE 357-3184

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REPORT MON111 February

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- I I 81-1 2-24-81 F 0 A 4 At 1415.* while performing a periodic test  !

on excore detector N-43, the control pow-er fuse failed causing a NIS turbine.run-back. The turbine was placed in manual f

control stopping the runback at 57%

reactor power, Trouble-s.hooting failed I

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- and no problems were found in the detec-tor channel. At 1553 a power increase i began and the unit was at 100% power at I I

2000.

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e e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: February REASON.

DATE TIME HOURS LOAD 2 MW REDUCTI0NS 2 MW HWH None during this reporting ptariod.

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MONTHLY TOTAL

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.. e e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT N0.2 MONTH: February, 1981 LOAD 1 MW REDUCTIONS 1 MW MWH REASON DATE Tllfi: HOURS --

None dt ring this reportiI g period.

MONTHLY TOTAL

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e DOCK.BT NO 50-280 UNIT SURRY I DATS 3-1-81 COMPL:!.""'TED BY . .SUE D. -i>UNN AVERAGE DAILY UNIT ~ LSVEL MONTH: FEBRUAHr 81 AVERAGE DAIU P(MER LEVEL AVERAGE DAIU PQi/ER LEVEL DAI (/r!ilE-NE'r) DAI (ftNE-NE'r) 1 o.o 15 o.o 2 o.o 16 o.o 3 -o.o 17 o.o 4 o.o 18 o.o 5 o.o 19 o.o 6 o.o 20 o.o 7 o.o 21 o.o 8 o.o 22 o.o 9 o.o 23 o.o 10 o.o 24 o.o 11 o.o 25 . o.o 12 o.o 26 o.o 13 o.o 27 o.o 14 o.o 28 o.o

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DAILY UNIT POWER L'SVEL PORN INSTRUCTIONS ON THI£ ~ORM, LIST THE AVERAGE DAIU UNIT POWER LEVEL IN WE-NE'r FOR EACH DAY IN THE IBPORTING MONTH. THESE FIGl/RSS WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT B:t USING MAXIMUM DEPENDABLE CAPACITY FOR THE NE'r ELECTRICAL RATING OF TBS UNIT. THERE NAY BE OCCASIONS WH?N TH'S DAILY AVERAGE PrMER EXCEEDS THE 100 °/ 0 LINE (OR THS RESTRICTED PCMER LEVEL LIN'S). IN SUCH CASES. THE AVERAGE DAIU UNIT P(MER OUTPUT SHEET SHOULD BE FOOTNOTED TO SXPLAIN THE APPARENT ANOMALY *

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e e DOCKET NO 50-281 UNIT SURM II DATE. 3-1-81 COMPL:.--PED BY $W: ;D. D~_;

AVERAGE DAILY UNIT POWER l&VEL MONTH: FEBRUARY 81 AVERAGE DAILY POWER LEVSL AVSRAGg DAILY POWER LEVEL DAI (WE-N'!:'r) DAY (NilE-NE'l')

1 758.5 15 757.0 2 756.3 16 757.9 3 758.9 17 756.5 4 759.7 18 758.6 5 758.9 19 755.6 6 759.3 20 752 .4

  • 7 760.6 21 752. 7 8 760.2 22 757.5 9 759.3 23 756.4 10 759.7 24 730.3 11 759.9 25 757.2 12 758.8 26 757.0 13 757.9 27 756.8 14 756.1 28 754.8 DAILY UNIT POWER. LEVEL FORM INSTRUCTIONS ON THIS FORM. LIST THE AVSRAGE DAILY UNIT P(JWER LEVEL IN WE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGllRES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT. THERE MAI BE OCCASIONS IIHEN THE DAIL! AVERAGE PCMER EXCEEDS THE 100 °/ 0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGE DAILY UNIT PCMER OUTPUT SHE'!:'r SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

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~RY. OF OPERATING EXPERIENCE February, 1981 e

Listed below in chronological sequence by unit is a summary of operating experiences for this month ~hich required load reductions or resulted in sign-ificant non-load related incidents.

UNIT 1 February 1 This reporting period begins with the unit at cold shutdown for steam generator replacement and major.design changes.

February 28 This reporting period ends with the unit at cold shutdown for steam generator replacement and major*.design changes.

UNIT 2 February 1 This reporting period begins with the unit at 100% power.

February 24 At 1415, while the Instrument Technicians were performing a periodic test on excore detector N-43, the control power fuse blew causing a NIS turbine runback. The control room operator piaced the turbine in manual control stopping the runback at 57% reactor p*ower. At 1420 a power increase began and was halted at 1528 with the unit at 70%'

power. The instrument technicians went through their "trouble-shooting" procedure to determine the cause of the blown fuse. They found no problems in the detector channel and.: at .. 1553 a power increase began.

The unit was at 100% power at 2000.

February 28 This reporting period ends with the unit at 100% power.

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AMEIID?IBNTS TO FACILITY LICENSE OR TECHNICAL SPE ICATIOUS February, 1981 The Nuclear Regulatory Commission issued, on December 18, 1980, Amendment Uo. 63 to the Operating License for Surry Power Statiqn, Units No. 1 and No. _2. The December 18, 1980 Condition of the License has been designated as Technical

  • Specification Change No. 69.

The change implements a requirement to follow a guard training and qualification plan in accordance with 10 CFR 73.55(b) (4). Of significance, paragraph 3.K of the Surry Unit No. 1 and Uo. 2 Operating Licenses is amel;ld:ed to r.ead as follows:

"3.K The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Nuclear Security Personnel Training and Quali-fications Program, including amendments and changes made pursuant to 10 CFR 50.54{p) *. The approved Nuclear Security Personnel Training and Qualifications Program consists of a document withheld from public disclo-sure pursuant to 10 CFR 2.790(d) identified as "Surry Power Station Nuclear Security Personnel Training and Qualification Program" dated.September 15, 1980. The Nuclear Security Personnel Training and Qualifications Program shall be fully implemented in accordance with 10 CFR 73.55(b) (4), within 60 days of this approval by the Commission. All security personnel shall be qualified within two years of this approval."

The Nuclear Regulatory Commission issued, on February 9, 1981, Amendment No. 64 to the Operating License for Surry Power Station, Units No. 1 and No. 2. The changes have been designated as Technical Specification Change No. 70.

Of significance, the changes incorporate a clarification of the definition of "operable" and add general Limiting Conditions for Operation with general action statements. In addition, paragraph 3.B of the Operating Licenses is amended to read as follows:

"B. The Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment ~o. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the "Technical Specifications."

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~CILITY CHANGES REQUIRIUG NRC APPROVAL e February, 1981 None during this reporting period.

FACILITY CHAUGES THAT DID NOT. REQUIRE NRC APPROVAL UNIT D/C 77-19 Make-up Water Treatment Modification 1,2.

The filter backwash settling pond (77-19G) portion of this design change has been implemented.

Summary of Safety Analysis:

There are no safety implications for the proposed changes as _the operation of safety related equipment will not be affected.

D/C 78-08 Fire Protection Modification 1,2

'!'he 78-081 portion involving the installation of a heat detector in the gaseous waste charcoal filters to alarm in the security building control room was implemented.

Summary of Safety Analysis This modification increases surveillance of the gaseous waste charcoal filters to reduce the chances of a £ire related accident.

D/C 78-10. Condensate Polishing Addition 2 Another po~iion of this design change involving maj.or mechanical Installation and erection of pipes and hangers (78-lOK) was implemented.

Summary of Safety Analysis This modification neither constitutes an unreviewed safety question nor requires a change to Technical Specifications.

D/C 78-44 Steam Generator Blowdown Treatment System 1,2 The piping portion (78-44B) of this design change has been implemented.

Summary of Safety Analysis The overall safety reliability and performance of the steam generator b"lowdown system will be improved by this modification. The design specifications will meet or exceed the specifications of the existing

. system *

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e Facility Changes That Did Not Require NRC Approval (Continued)

UNIT D/C 79-65 Construction Site Sewage Treatment NA This design change disconnected the construction site's sewage line from the septic tank and drainage fields. The sewage line is not tied into the plant sewage treatment system.

Summary of Safety Analysis This modification will not affect any operation of safety related equipment.

D/C 79-75 Emergency Egress Lighting 1,2 Emergency lighting fixtures with the following features have been provided:

a) Self contained power packs, including permanently sealed lead-acid battery and solid state charge.

b) Directionally adjustable high efficiency halogen lamps.

c) Solid state monitoring circuits which automatically connect lamps to battery upon failure of a C power.

d) Front mounted test and control switches indicating lights and battery voltage indicator.

These fixtures, strategical~ placed, provided adequate lighting for fire fighting efforts and safe personnel egress from the affected area.

Summary of Safety Analysis This modif~cation enhances the fire fighting effort and safe egress of personnel and does not create an unreviewed safety question.

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  • 'TS AND EXPERIMENTS REQUIRING W NRC APPROVAL FEBRUARY, 1981 None during this reporting period.

TEST AND EXPERIMEUTS*THAT DID NOT REQUIRE NRC APPROVAL None during this reporting period.

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~ 0Tillll'CHANGES, TESTS AND EXPERIMENTS~

February, 1981 None during this reporting period. -.*

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  • Sl:RRY PO.*:ER STATION CHEr1ISTRY REPORT e

February , 19__fil,_

T.S. 6.6.3.* d PRIMARY COOLANT UNIT NO. l UNIT NO. 2 ('BJ ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAG:

Gross Radioact., µCi/ml Note (A) 2 *.68E-1 S.SlE-:2 1.68E-Suspended Solids, ppm 0.1 0.1 0.1 Gross Tritium, µCi/ml 2.86E-1 2.60E-1 2.68E-Iodine-131, µCi/ml 3.52E-3 1.SOE-3 2.29E-1-131/I-133 Hydrogen, cc/kg

- .8417 54 .o. (c)'

.5983 33.6 42.1

.7344 Lithium, ppm 2.30 1.95 2.14 Boron-10, ppm+ 125 115 121 Oxygen-16, ppm 0~000 0.000 0.000 Chloride, ppm 0.05

- - 0.05 0.05 pH@ 25°C 6.98 6.84 6.91

+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL

~ RELEASES , POUNDS T.S. 4.13.A ...p,;"

Phosphate O* Boron 309 Sulfate 50% NaOH 0

0 Chromate __;::;,.,:.;~-----

0.36 Chlorine *~_ __:0::....__ _ _ __

Remarks~ (A) Unit 1 at*csn, defueled and drained for SGRP.

(B) Reactor run-back to 39% due to blown fuse in instrumentation.

(C) ReQuested Operations reduce H2 pressure on VCT.

These levels of chemicals should present no major adverse environmental impact.

-. -~ '-~. - ,----~~. . *-. ------

,, ,, .. A D~IPTION OF ALL INSTANCES WHERE W THERl1AL DISCHARGE LIUITS WERE EXCEEDED February, 1981 Due to the impainnent of the circulating water-* system on the following days, the thermal discharge limits were exceeded .as noted.

0 February 1, 1981 Exceeded 150 F llT across station February 2, 1981

  • Exceeded 150 F llT ..,,across station February 3, 1981
  • Exceeded 150 F llT across station February 4, 1981
  • Exceeded 15 F llT across stat.ion February 5, 1981
  • Exceeded 0

15 F llT across station.

February 9, 1981

  • Exceeded 0

15 F llT across station February 10, 1981

  • Exceeded 0

15 F llT across station February 11, 1981.

  • Exceeded 15°F llT across station February 12, 1981
  • Exceeded 15°F llT across station February 13, 1981
  • Exceeded 15°F llT across statio.n February 14, 1981
  • Exceeded 15~F l:lT across station February 15, 1981
  • Exceeded 15 F llT across station February 16, 1981
  • Exceeded 0

17.5 F llT across station February 17, 1981

  • Exceeded 15°F llT across station
  • Indicates dates where station fj.T was less than 15.0°F across station for sometime during the day.

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

On February 24, 1981 the temperature change at the station discharge exceeded 3°F per hour due to a NIS turbine runback on Unit 2.

These events were allowable in accordance with Technical Specification 4.14.

There were no reported instances of adverse environmental impact *

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FUEL HAlIDLmG UNIT No. 1 February, 1981 *.

None during this reporting period.

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I ' FUEL HAlIDLIHG UNIT N0.2 February, 1981 None during this reporting period *

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PR~DURE REVIS;~~~ THAT CHANGED TH~

OPERATING MODE DESCRIBED IN THE FSAR February, 1981 None during this reporting period.

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DESCRieON OF PERIODIC TESTS WHICH WERJ. .

COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS February; 1981 PT 24.4J Fire Protection Systems (Trailers). Monthly, was performed on January 21, 1981. This PT devi~tion was incorrectly routed straight to station records and thus the deviation was bypass-ed and is late. Personnel involved have been instructed to be alert for deviation review requirements.

-..-. _--~-=~~~-

INSERVICE INSPECTION e February., 1981 UNIT 1 -.

The Westinghouse program for inservice_inspection is still in progx::ess with no major indications being noted. An inspection of ASME CLASS III han-gars and component supports is still being*conducted. An ultrasonic inspec-tion was completed on all major bolting .associated with the LP and HP turbines also other inspections are being .conducted to assist in the maintenance work associated with the turbine overhaul.

Conducted a random eddy current inspection of feedwater heater exchangers lA & lB, 2A & 2B, 3A & 3B, 4A & 4B, SA & SB, 6A & 6B. From this inspection, the only reportable indications were found in heat exchangers SA, 6A and 6B.

A further investigation will be conducted after startup testing of the conden-sate system.

Conducted a raaiographic inspection on_6 welds in /fl safeguards on main steam piping; indications were noted as corrosion and turned over to mechanical maintenance for resolution and disposition.

Conducted eddy current on the new steam generator lower shell tubing to complete the data baseline.

UNIT 2 Conducted an ultrasonic examination of 6 welds in ft2 safeguard on main 1 steam piping - no indications were reported.

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RE Ill TABLE OCCURRENCES PERTAINING T -

ANY OUTAGE OR POWER REDUCTIONS February, 1981 None during this reporting period.

4 .

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Maintenance of Safety Related Systems During

  • outage or*Reduced*Power Periods

(\...... UNIT f/l Mechanical Maintenance c.

't 1

2 NAR 11

  • 2121J PM PAGE 1

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2 NAR 111

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2 NAR 11 *. 2121f l'N PAGE 3

. UIII2'1* 3/02/81 *

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  • e Maintenance of Safety Related Systems During Outage or Reduced Power Periods tTNIT 412 Mechanical Maintenance

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February, 1981 None during this reporting period

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Maintenance of Safety Related Systems During Outage or Reduced.Power Periods UNIT #1 Electrical Maintenance

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2 NAR 11 2t21t PN PAGJ If

  • o (NAiffDARCI OF SAF!rl'l SLAl'!lD SlS'rHNS
  • IJURIIIO OUl'AOB OR IBIJUCSD p(Jj!R PBRIODS) 11 --mSBRVDr-*-s;s"--CONP-" .. .IIARXlio_______,SUNNARf .-- ___,___________ ,______, ------- . ~KPBKP-~---*-** -------*- ------- u 0'

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02/07/81 SI In' Plr£-2-CKl'-21fA BAD HEAi' l'RACIIO CIRCUIT ANPS CH~KS OK 1 102061352 If I -----*02/07/B1--BI- *-Br .... --.. - PN£2 crT..21CC.--BAD aar..rRAc1110 .. _. __ .. ___ ..._____ ,_____ RSPLACED BEAi' . !tRAC!l..f'AP.!l.. s 1020&1353 ____ !1

r. . 02/10/111 BS OJ'RIR 1-RS-UR-1C RSPACE 11(60R ON SPAC~ NEAHR REPLACED IIOTOR 1 002031915 19 . i:.:

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  • In' CKl'-28-PIILI REPLACE BAD HAI' l'RAC!l RSPLAC!lD HEAT f'AP.!1' 1 1021211135 If  !,*.,.,
  • . --*--*02/11t/11 ..... l'f/_ VALVI --- N0v,,w. .. 2&0B.---DISCONR!/Cl'*REC0NRBCT..l'OR.. raca.. NOV.TEB'rED SAl'ISFACrtJRl. t 1011u201---1t..  !:*.1 1

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02/15/81 CC 02/11/81 SS SP£ PNP lt/R 1-CC-P-18 VALVS BREAKERS f'V-SS-101Ut REPAIR DANAG!lD COIIIIIJUir VA£VB' JIOff OPBI

- - - 02/21/11 ---VS--.DA11PJ'R,--1"VS,,103A---ST121..CONDUGT .f'O .Dff. .. SPOR..8A1£UB--INSTA£1ED. N5Tl .NO'ZOR____

02/21/81 PERFORN 2'EP5 .

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AD.nJB'rED 9/I'l'CH PERFORMED f'SP-5 OR a, BREAKERS II INS 1 1

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. 1 10213191ft t 1020!11709_---7 10211t0105 9

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~ 02/22/81 l'f/ NOV IIOV-W-1510 PERFORN PNS PHS CONPLE'l'BD t 009070118 39 .* ;

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02/22/81 W NOV FOV-W-151B DISCONN!/CI' AIID RBCONN8Cr FOR BC8 CONPLE'l'!lD AS PBR !lNP-C-NOV 11 t 011191101 2255 l:, 02/22/81 Ill NOV 'NOV-W-1510 DISCONNECT AND RECON/fEC'r tOR NECN COHPIE'l'ED AS PBR BNP-C-NOV ti i 011191102 2255 **

/ ----02/22/81 .. , IPC,--BREAUR------- l1IlRFORN,2'BP~5 RERFOR!BD-f'Ee,,,5..!JII .. OI...BR!l.AUBS.. LBI/S 1 1021110021_ _ _1________ ii

.... 02/22/11 SP£ BRJAKER PBRFORII l'EP-5 P!lRFORNSD l'!P-5 ON CC BRBAKER ,/ BUS t 1021110026 2 r;

  • 02/23/81 BS Of'BBR 1ft RSLOCAl'B .nJNC'rIOII BOX BOX RBLOC'rED t 00121tl526 73 ' .. a t:.

j ._____ 02/23/81---*1/PL--- BRSAURS P1lRFORN,,'J!llP5 RJRFORNED-fEP.,,s.. a. ..cc..BR!lAm.ll..Bl/8 t 1021!10100..---2  ! ,.

l.,. 02/21f/H EPL BRSAKERS PERFORN f'!lPS PERFORNSD f'EP-5 011 RO BREAKER II BUS *.. t 10Wt001f1 7

  • PERFORNED f'!P-5 ON IA BREAK!lR B iJuS ' t I .....
  • 02/2lf/81 02/25/81 SP£ RC BREAKERS 02/25/11-*-RC*--*NOV*-----NO!t-1536 NOV IIOV-1535 PBRFORN !'EPS

'f!gRFORN~#S PERFORN PNS

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  • 02/25/11 ft'£ BREAURS 02/25/11--CC- *-VA£V.l'--~~..1011--:---~~RJl::.T.-VA£VB...60B-RBMJVAC.

PERFORN 2'!lP5 PERFORMED l'.JP-5 ON NS BREAIC!lR B INS

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Maintenance of Safety*Related Systems During

  • 0utage or Reduced*Power Periods UNIT #2 Electrical Maintenance

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February, 1981 None during this reporting period *

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Maintenance of Safety Related Systems During*

Outage or Reduced Power Periods UNIT Ill Instrument Maintenance

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,. I Ullff1- 3/02/at (NMli'r!JIIAtrCB OP SAF!Tl REi.ArEb S1STENS DIIRIIIG OU2'AGE OR R!fDUCBD P<MBR PERIODS)

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  • 1 U'1'SBRrl1l' 818 CONP NARICIIO SUNNAM ,i,a,JRF IJ HR 'IO'rlMlfffl I . . .

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' 02/12/11 C, illSl'R Pl-CV-10182 GAUGE IIIIJICA2'ES IIICORREct lm'£ACSIJ CAPS C2 3 It 6 1 8 9 t 01226011J5 76 8' i 02/26/11 RN IIJIIIrOR RN-CC-10& RIGII Ac.ARN SEPOIIIT GREATER f'IIAII 2.t Ii CRAIIG!D Sffl'OIIIT 1 102220730 62

_102/26/11 ----RN---NOIIIrOR - RN-CC-t08--RICII-A£ARN S1l'rl'Oill11S CRBATER-- - ---CHANGED SB'l'l'OilfT-------------1--102230215. -- . 62 --- . ---*-* --

  • I 02/26/11 RN NOIII'IOR RN-Sl-101 NOIIIl'OR RAS FAIUD REl'AIR~D CONNECTOR 1 102250310 --~~-
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  • Maintenance of Safety Related Systems During Outage or*Reduced Power*Pe'ti.ods UNIT f/2 C Instrument Maintelialice

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. ,4 e February, 1981 None during this reporting period *

    • , HEALTH PHYSICS

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February, 1981 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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';- .... ! ~-' *,; PROCEDU EVIATIONS REVIEWED BY STATION SAFETY OPERATING COMMITTEE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS February, 1981 None during this reporting period.