ML18139B313

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Monthly Operating Repts for Apr 1981
ML18139B313
Person / Time
Site: Surry  Dominion icon.png
Issue date: 05/06/1981
From: Dunn S
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139B312 List:
References
NUDOCS 8105190130
Download: ML18139B313 (44)
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Text

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-i VIRG HUA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 81-04 APRIL, 1981 f8.1 (1} 519 O\-;<:::>:

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- CONTENTS Section Operating Data Report - Unit Ill 1 r**

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 Enviromnental Restrictions - Unit ill 5 Load Reductions Due to Enviromnental Res tr ic tions - Unit il2 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 H Facility Changes That Did Not Require NRC Approval (MARCH CORRECTED COPY) l:2 Facility Changes Requiring NRG 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 Experiments 16 Chemistry Report 17 Description of All Instances Where Thermal Discharge Limits Were Exceeded 18 Fuel Handling 19 Procedure Revisions That Changed the Operating Mode Described In The FSAR 20 Description of Periodic Tests Which Were Not Completed Within The Time 21 Limits Specified In Technical Specifications Inservice Inspection 22 Reportable Occurrences Pertaining to Any Outage or Power Reductions 24 Maintenance of Safety Related Systems During Outage or Reduced Power 25 Periods - Unit Ill - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 31 r Periods - Unit 112 - Mechanical Maintenance

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  • e Section Page

,- Maintenance of Safety Related Systems During Outage or Reduced Power 34

( Periods - Unit #1 - Electrical Maintenance

  • Maintenance of Safety Related Systems During Outage or Reduced Power 37*

Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 39 Periods - Unit #1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 41 Periods - Unit #2 - Instrument Maintenance Health Physics Summary 43 Procedure Deviations Reviewed by Station Nuclear Safety and Operating 44 Committee After Time Limits Specified In T.S. .J

... e OPERATING DATA REPORT DOCKET NO. 50-280 DATE 06 MAY 81 COMPLETED BY SUED, DUNN TELEPHONE 804-357-3184 OPERATING STATUS 1, UNIT NAME SURRY UNIT 1

2. REPORTING PERIOD 40181 TO 43081 3* .LICENSED THERAJAL PWER (/,!i,/T) 2441 1------------------------1
4. NAMEPLATE RATING (GROSS MwE) 847. 5 I NOTES
  • I
5. DESIGN ELECTRICAL RATING (NET MWE) 788 6, MAXIMUN DEPENDABLE CAPACITY ( GROSS loME) 740
7. MAXIMUM DEPENDABLE CAPACITY (NET MW'E) 704
8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS
9. Pa,,JER LEVEL TO WHICH RESTRICTED. IF ANY NIA (NET /.ME)
10. REASONS FOR RESTRICTIONS, IF ANY NIA THIS MONTH YR-TO-DATE CUMULATIVE
11. HOURS IN REPORTING PERIOD 719.0 2879.0 73247.0
12. NUMBER OF HOURS REACTOR ~'AS CRITICAL o.o o.o 42538.5
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 o.o 3731. 5
14. HOURS GENERATOR ON-LINE o.o o.o 41668.8
15. UNIT RESERVE SHUTDCMN HOURS o.o o.o 3736.2
16. GROSS THERMAL ENERGY GENERATED (WH) o.o 0.0 96389401.0
17. GROSS ELECTRICAL ENERGY GENERATED (M,IH) o.o o.o 31301743.0
18. NET ELECTRICAL ENERGY GENERATED (MIH) o.o o.o 29699924.0
19. UNIT SERVICE FACTOR 0.0 o.o 56.9 o/o
20. UNIT AVAILABILITY FACTOR o.o 0.0 62.0 o/o
21. UNIT CAPACITY FACTOR (USING MDC NET) o.o o.o 57.6 o/o
22. UNIT CAPACITY FACTOR (USING DER NET) o.o o.o 51. 5 o/o
23. UNIT FORCED OUTAGE RATE o.o o.o 26.4 o/o
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,,lMTE,AND DURATION OF EACH)
25. IF SHUT DOWN AT END OF REPORT PERIOD, JULY 1, 1981 ESTIMATE DATE OF STARTUP
26. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

. e e OPERATING DATA REPORT DOCKET NO. 50-281 DATE 06 MAY 81 COMPLETED BY SUED. DUNN TELEPHONE 804-357-3184 OPERATING STATUS

1. UNIT NAME SURRY UNIT 2
2. REPOR'rING PERIOD 40181 TO 43081
3. LICENSED THERMAL PCJ,/ER (M,/T) 2441 1------------------------1
4. NAMEPLATE RATING (GROSS t,f,/E) 847. 5 I NOTES I
5. DESIGN ELECTRICAL RATING (NET M,,/E) 788
6. MAXIMUM DEPENDABLE CAPACITY ( GROSS MWE) 811
7. MAXI!.fUM DEPENDABLE CAPACITY (NET MwE) 775
8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
9. PCJ,/ER LEVEL TO WHICH RESTRICTED. IF ANY NIA (NET MIE)
10. REASONS FOR RESTRICTIONS, IF ANY NIA THIS MONTH YR-TO-DATE CUMULATIVE
11. HOURS IN REPORTING PERIOD 719.0 2879.0 70127.0
12. .NUMBER OF HOURS REACTOR WAS CRITICAL 484.8 2636.0 40420.0
13. REACTOR RESERVE SHUTD(l,,IN HOURS o.o o.o o.o
14. HOURS GENERATOR ON-LINE 480.5 2617.6 39754.2 15.* UNIT RESERVE SHUTD(l,,IN HOURS o.o o.o o.o
16. GROSS THERMAL ENERGY GENERATED (MwH) 1139732.0 6339007.0 92793668.0
17. GROSS ELECTRICAL ENERGY GENERATED (H,/H) 370225.0 2070685.0 30309679.0
18. NET ELECTRICAL ENERGY GENERATED (MwH) 350761.0 1963484.0 28741972.0
19. UNIT SERVICE FACTOR 66.8 olo 90.9 olo 56.7 o/o
20. UNIT AVAILABILITY FACTOR 66.8 olo 90.9 olo 56.7 o /o
21. UNIT CAPACITY FACTOR (USING MDC NET) 62.9 o/o 88.0 o/o 52.9 olo
22. UNIT CAPACITY FACTOR (USING DER NET) 61.9 olo 86.5 olo 52.0 olo
23. UNIT FORCED OUTAGE RATE 0.5 olo 1.0 o/o 18.8 olo
24. SHUTDOi,,rNs SCHEDULED OVER NEXT 6 MONTHS OCTOBER 2, 1981 (TYPE.DATE.AND DURATION OF EACH) FALL MAINTENANCE - 10 DAYS
25. IF SHUT D(l,,IN AT END OF REPOR'r PERIOD, ESTIMATE DATE OF STAR'rUP
26. UNITS IN TEST STATUS FORECAST ACHIEVED

.(PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

DOCKET NO. 50-280 UNIT SHUTDOWNS AND POWER REDUCTIONS

.*. UNIT NAME Surry Unit l t DAJE .1!!!V, 1981 COMPLETED 8'\'

REPORT MONTI! April, 1981 TELEPHONE ~tt849.:3~y~~I84 C,

Licensee C

cuv, C cu Cause & (urredive No. Date C.

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81-4 4-1-81 s 719.0 A 1 e

Continuation of shutdown for steam generator replacement outage which commenced 9-14-80.

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  • Instructions S: Schrduled A-Equipmenl Failure (Explain) I-Manual fur Preparation of Data B-Maintenance or Test 2-Manual Scram. Enlry Sheels fur Lkensee

( -Refueling 3-Aulomalic Scram. Event Report (LER) File (NURF.G-D-Regulalory Restriction 4-0lher (Explain) 0161)

F.-Operator Training & License Examination F-Adminisl ral ive 5 G-Operation,al Error (Explain) Exhibit I

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1'1/77) 11-0ther (Explain)

DOCKET NO. 50-281 UNIT SflUlTIOWNS AND POWER Rl!PUC.JlONS UNIT NAMI~ Surr~ Unit II l>ATE May , 1981 COMl'I.ETED UY Sue D. Dunn RErortT MON"lll April' 19 81 TEI.El IIONE ( 804 )-35 7-3184

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81-3 4-6-81

- F 2.5 H 3 Reactar tripped as a result of a spurious II C" primary loop low flow signal when the lnstrtunent Technicians valved in channel 2 flow transmitter after repairs.

81-4. 4-18-81 s 236.0 D 1 Scheduled shutdown for snubber inspection and TMI-2 design change i1,1s tall11tions. I

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('. ilc fueling J-Aulumallc Scram. Evcnl ltcpml (1.1:ltl File (NUlll:G-

. 1>-Hci:11la1111y llcs11lcll1111 4-0lhcr (Explain) 0161)

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LOAD REDUCTIONS DUE TO ENVIRONMEl\'TA:.. RESTRICTIONS UNIT NO.l MO~'TH: April, 1981 DATE TUIB HOURS LOAD 1 MW REDUCTIONS 1 MW MWH REA.SON 1 None during this repor, ing perii d.

MONTHLY TOTAL

.,- .. --- -----~- ------- --------

LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTH: April, 1981 TIME HOURS LOAD 2 REDUCTIONS 2 MW MWB REASON DATE

- - MW

  • None ~uring this report ling perio ki.

MONTHLY TOTAL

e DOCKET NO 50-280 UNIT SURRY I DATE 5-1-81 COMPLETED BY SU:E D. DUNN AVERAGE DAILY UNIT POWER LEVEL

!12!!12!..: APP.IL 81 AVERAGE DAILY POWER LEVEL AVERAGE DAILY P(J,IER LEVEL DAY (MIE-NET) DAY (/tfr/E-NET) 1 o.o 16 o.o 2 o.o 17 o.o 3 o.o 18 o.o 4 o.o 19 o.o 5 o.o 20 o.o 6 o.o 21 o.o 7 o.o 22 o.o 8 o.o 23 o.o 9 o.o 24 o.o 10 o.o 25 o.o 11 o.o 26 o.o 12 o.o 27 o.o 13 o.o 28 0.0 14 o.o 29 o.o 15 o.o 30 o.o DAILY UNIT PC,.,,,ER LEVEL FORM INSTRUCTIONS ON THIS FORM, LIST THE AVERAGE DAILY UNIT P(MER LEVEL IN M,/E-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTP.ICAL RATING OF THE UNIT. THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 o/o LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT PCNIER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

e DOCKET NO 50-281 UNIT SURRI II DATE 5-1-81 COMP LETED BY SUE D. DUNN

-MONTH: APRIL 81 AVERAGE DAILY P(l,/ER LEVEL AVERAGE DAILY P(l,,!ER LEVEL DAY (Aft.IE-NET) DAY (MwE-N'F:T) 1 752.8 16 753.0 2 752.3 17 727.0 3 751.0 18 38.8 4 749.8 19 o.o 5 755.3 20 o.o 6 525.7 21 o.o 7 748.5 22 0.0 8 750.5 23 o.o 9 751.2 24 o.o 10 751.4 25 o.o 11 750.2 26 o.o 12 753.2 27 o.o 13 755. 9 28 ,543. 6 14 749.4 29 753.0 15 751.6 30 751.0 DAILY UNIT PCJ,lER IEVEL FORM INSTRUCTIONS ON THIS FORM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN WE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES 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 MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 o/o LIN!! (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLA.rN THE APPARENT ANOMALY.

e e

SUMMARY

OF OPERATIN:; EXPERIENCE Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents.

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

APRIL 4 The "C" steam generator secondary hydrostatic test was completed satisfactorily at 0145.

APRIL 7 The "A" steam generator secondary hydro was completed satisfactorily at 0156.

APRIL 8 The "B" steam generator secondary hydro was completed satisfactorily at 2339.

APRIL 15 The "C" primary loop hydro was completed satisfactorily at 1830.

APRIL 21 The "A" primary loop hydro was completed satisfactorily at 1440.

APRIL 30 This reporting period ends with the unit at cold shutdown for steam generator replacement and major design changes.

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

APRIL 6 The reactor tripped at 1047 on a low reactor coolant flow signal from "C" loop caused by a spike on channels 1 and 3 flow trans-mitters.* The spike occurred when Instrument Technicians valved in the channel 2 flow transmitter after repairs. The reactor was critical at 1205. The generator was synchronized and placed on-the-line at 1305. The turbine-generator tripped at 1307 on a spurious ant:imotoring trip signal. The generator was synchronized and placed on-the-line at 1315 and a power escalation commenced.

APRIL 7 The reactor ~eached the 100% power level at 0200.

APRIL 14 At 1357 the Electrical Department reported 2 redundant channels of a heat tracing (HT) circuit inoperable. After a review of the HT circuits involved, it was determined that this constituted a violation of Technical Specification 3.2 and a unit shutdown began.

The Emergency Plan was initiated with the classification of "unusual event". At 1455 one channel of the HT circuit was re-turned to service. Emergency Plan activity was terminated and a power escalation started at 1455. The unit reached the 100%

power level at 1553.

APRIL 17 Started unit shutdown for Snubber Inspection and TMI-2 modification outage at 2110.

e AMENDr*IBNTS TO FACILITY LICENSE OR TECIDUCAL SPECIFICATIONS APRIL, 1981 None during this reporting period.

e FACILITY CHANGES REQUIRING CORRECTED COPY NRC APPROVAL March, 1981 None during this reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL UNIT D/C 77-32A Containment Cooling System Modification l Containment Cooling System Modification installed the new chilled water units and piping into the new system.

SUMMARY

OF SAFETY ANALYSIS There is no change in the operation of safety related equipment as a result of this design change.

D/C 78-lOE Condensate Polishing Addition 1,2

  • This portion of the design change involving Auxiliary Boiler Breeching and Steam Piping Relocation was implemented.

SUMMARY

OF SAFETY ANALYSIS

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

D/C 78-35 LHSI & ORS Pump Bellmouth Modifications 1 This design change installed a crossvane type extension for both pumps to insure radial flow into the pump suction to eliminate excessive vortexing.

SUMMARY

OF SAFETY ANALYSIS This modification requires no change to the Technical Specifications, FSAR requirements, and does not create "An Unreviewed Safety Question."

D/C 78-44 Steam Generator Blowdown Treatment System 2 The electrical portion (78-44C) of this design change has been

/

implemented.

SUMMARY

OF SAFETY ANALYSIS The overall safety reliability and performance of the Steam Generator Blowdown System will be improved by this modification. The design specifications will meet or exceed the specifications of the existing system.

e FACILITY CHANGES REQUIRING e

NRC APPROVAL APRIL, 1981 None during this reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL Unit D/C 76-14 - Containment Instrument Air System Modification 2 This design change installed new compressors of larger capacity.

The location of the new compressors is in the lower elevation of the safeguards building i.3., 11'6" elevation. Access for the suction and discharge piping to the contaimnent penetrations will be through an existing hole between Auxiliary and Safeguards buildings.

SUMMARY

OF SAFETY ANALYSIS This modification requires revision to the FSAR and no changes to Technical Specifications. There are no safety implications as a result of this design change.

D/C 79-60 - Containment Pressure Indication 2 This design change installed a redundant pressure transmitter that will be capable of measuring a pressure range of three times the containment design pressure, 0-180 psig. The transmitter will provide a continuous indication of contaimnent pressure in the control room.

SUMMARY

OF SAFETY ANALYSIS This modification does not effect the operation of any safety-related equipment; therefore, there are no safety problems caused by this modification.

D/C 80-44 - Redundant Wide Range Pressure Loop 2 This design change upgrades the existing reactor coolant system wide range (0-3000 psig) pressure transmitter which is located in the reactor coolant loop C. In addition, a redundant reactor coolant system wide range (0-3000 psig) pressure transmitter was installed into reactor coolant loop B. The transmitters are a safety grade Category I, Rosemount 1153 Series D, Pressure Transmitters.

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

UNIT SUMMA.RY OF SAFETY ANALYSIS:

The addition of the reactor coolant system wide range pressure loop provides the operator with two independent s~urces for indication of reactor coolant system wide range pressure 1neasurement making it pos-sible to provide redundant inputs of this measurement to the sub-cooling monitors.

D/C 80-86D Modification of Masonry Wall 2C-47-4-20 2 lbis design change replaced existing block wall with precast concrete

-panels to comply with IE Bulletin 80-11.

SUMMARY

OF SAFETY"~ALYSIS:

'llle completed modifications will have no effect on the operation

-0f safety-related equipment.

, D/C 80-88 Isolation of Steam Driven Aux. Feedwater Turbine 2

. This design change gives positive isolation required to permit repair work at steaming conditions.

SUMMARY

OF SAFETY ANALYSIS:

This modification has no effect on station operation or the operation of any safety related equipment.

D/C 81-15 Removal Pressurizer Cubicle Wall C-47-4-20 2 To permit the installation of a seismic Class I wall to comply with IE Bulletin 80-11, a portion of the biological shield wall had to be removed. The replacement wall is covered under a separate design package, D/C 80-86D.

SUMMARY

OF SAFETY ANALYSIS:

'llle removal and replacement of the wall does not have any adverse safety implications.

e e TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL APRIL, 1981 None during this reporting period.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL ST-123 Main Steam Monoball Pipe Support Special Test Program UNIT (Supports Outside Containment), Unit 1, was completed 1 on 02-25-81. The purpose of this special test program is to gather data from a representative sample of Unit l Monoball sliding pipe supports to provide supplemental input for the determination of the final recommendation(s) for all monoball pipe supports (Units 1 and 2) to resolve

  • problems that have been observed to date. Instructions are included for disassembly, inspection, and reassembly of the selected supports. While this procedure provides reassembly instructions, the implementation of the final recommendation(s) may require later disassembly and/or alteration of the sample supports. Also, no resolution will be made "on-the-spot" to any problem discovered during the implementation of the procedure. Resolution of such problems will be in the form of the final recom-mendation(s) and/or non-conformance resolutions.

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OTHER CHANGES, TESTS .AND EXPERIMENTS None during this reporting period.

e 51.:RRY PO~II.:K STl,TIOl, CHEl11STRY REPORT

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T.S. 6.6.3.cl PRIMARY COOLANT UNIT NO. 1 (C) UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml 1.35EO 4.13E- 4 2.94E-l Suspended Solids, ppm 0.2 0.1 0.1 Gro~s Tritium, µCi/ml 1.44E-l 5.34- 2 l.lOE-l Iodine-131, µCi/ml 2.38E-l(B)

  • 1.65E-2 1.83E-3 1-131/I-133 .8563 .4861 .6132 Hydrogen, cc/kg 44.10 4.4(, (A} 8.94 (A Lithium, ppm 1.9 . 0.76 1.31 Boron-10, ppm+ 289.10 90.36 184.25 Oxygen-16, ppm '

0.8 (AA) 1 .000 .05 Chloride, ppm 0.11 < .-OS <.OS pH @ 25"'C 7.06 6.14 6.63

+ Boron-10 = Total Boron x 0.196 -

NON-RADIOACTIVE CHEMICAL (1)

RELEASES, POUNDS T.S. 4.13.A *. p,,-

Phosphate 39 lbs. Boron 425 Sulfate Chromate 0.0 50% NaOH Chlorine O.0 Rem arks: #2 RX Trip@ 1049 4-6-81 (AA) on RHR system< 2S0°F (A) Reflects start-up & shutdo'lim conditions.

(B) Reflects Iodine Spike because of 1S% Pwr. change, (C) Unit Ill Shutdown for Steam Generator Replacement*

(1) These levels of chemicals should reuresent no major adverse environmental impact.

e e DESCRIPTION OF ALL INSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED APRIL, 1981 Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.

April 2, 1981

  • Exceeded 15 °F "T across station t.:;. .

April 5, 1981

  • Exceeded 15°F "T across station t.:;. .
  • Indicates dates where station 6T was less than l5.0°F across station for sometime during the day.

The 6T excursions were allowable under Technical Specification 4.14.B.2.

There were no reported instances of adverse environmental impact.

On April 6, 1981, the temperature change at the station discharge exceeded 3°F per hour due to a reactor trip on Unit 2. On April 6, 1981, the temperature change at the station discharge exceeded 3°F per hour while increasing unit power following recovery from the reactor trip earlier that day. On Agril 18, 1981, the temperature change at the station discharge exceeded 3 F per hour while decreasing power for a scheduled shutdown. On Agril 28, 1981, the temperature change at the station discharge exceeded 3 F per hour while increasing power following the reactor startup after the scheduled outage.

The April 6 and 18 3°F temperature changes were reported by VEPCO letters s-erial numbers 250 and 277 of April 16 and Mayl, 1981. The other event was allowable in accordance with Technical Specification 4.14. There were no reported instances of adverse environmental impact.

FUEL HANDLING UNITS 1 & 2 APRIL, 1981 None during this reporting period.

  • ~ e e DESCRIPTION OF PERIODIC TESTS WHICH WERE NO~

COMPLETED WITHIN THE TIME Lll1ITS SPECIFIE:l IN TECHNICAL SPECIFICATIONS APRIL, 1981 PT-18.4 Boron Injection Tank Unit The boron injection tank level check was not performed 2 during the week of March 10, 1981. This test verifies that_ the boron injection tank remains full during plant operations. PT-18 .. 4 was performed the next week, April 17, 1981, and was found to be satisfactory.

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

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Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT f/1 Mechanical Maintenance

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I R.ffSERVD'f SIS CONP NARK.NO SUNH/IR1 JIKPF.RF U IIR fOTIJltrrN I ,,

-*-oii/02/et***- l:ii*-**
  • vAiVE -- .... t-cR-195 _ _ _ RSPLACE BOLTIIIG*- RF.PLACED STUDS----------***---1-o102u~u--*- 3'.U -- -*----*--*-*----------*'

1

.. 011/02/lill CR VALVE 1-CR-188 RF.PLIICE BOLTIIIG REPLACED STUDS 1 010231728 323 (:,

! 011/02/81 CR VALVE 1-CR-191 R!PLAC! BOLTIIIG R."1',PLIICED STIJDS

..... *---*--*----*-*-** REE'iAc,r;oiJ STUDS ... ----*- --- .. ***-*-*-*

1 010231729

**-r*--* Oio23i736 323

__.. 323 ......... .

Olf/02/81 .. CR VAiVE .. -*. i-CH-239. - - - REPLACE BOLTING .

I* I .

Olf/02/111

      • oii/03/lii-st F'C VALVE 1-F'C-29
    • -*vALvr-- i,;.si-12i J

R!!.PLACE BOLTI1'G

RtPLACS BOC.TS ---*-----*-----REPLAC!!: STUDS --------------1--otooJhlf'I REPLACED sruos--- - ----* 1*** 012091129 "

  • 011/03/81 011/0~/Af SI

.<:r VALVE I/AT.I/Ti:

NOV-1890A Mnl/ -1 A<tOr.

REPLACE WJLTS R~Pr.Ar.r;: mr.r.r; REPLACE STUDS Rfl:P(.AC.~ ,,;r11n.r; 1

1 OJ.0011363 otnntr '.1f;II Olf/03/111 CR rALVJJ' 1-cN-98 ilt.PLAC!. BOLTING REPLACED IJOLTS 1 010231613 55 011/03/81 CR VALVE 1-CH-102 REPLIICE WJLTING - - - - - - - - RF.PLIICED STUDS AIID NUTS Ilf VALV!.S 1 0102316J.11 3135 011103191

  • CH--VALvi*--
  • 1-cH-211 *---Ri:PiACE iiiiTiwc * - REPLACE STUDS ----------- *--*- i 0!07319111 ,;n- . -
  • . Olf/03/81

, - - 011/03/ili *-

BR BR --*-

VALi'!

VALVE Et:V-BR-131t R!PLACE BOLTING NOV-BRioiif ___ REPiilcE BOLTING .. - - - -

REPLACED STUDS

--R.C:PLACF.D STUDs*-------------1 -*c,ut9l93ii --- ~~

0 1 011191553 33

  • l t, 1. 011/03/111 RR VAT.VT'. NOV-BR101A l Rf.PLACE BOLTING REPLIICED STUDS 1 011191939 31
  • 1 ,,  :-- 011/03/81 011/03/111 SI CH VA£V!'

VALVB NOV-1890-B 1-CH-210 R!E'LACE BO£TI1IC REPLACE 80LTI1'G REl'iACE STUDS R.S:PLACED BOLTS 1

1 017051105 012081208 1SII 31 N I

,}

011/03/111

--- Oit/03/81 - CR CH NOV NOV-1310

--*- NOV .. ---*--* NoV~i289A RF.PLACE IXJLTING kEE'LACB W1£TIIIO-- ---**------

REPLACE STUDS 1 101081233 "R.~PiACE STiins**-----.-------1-*-1010&1231i ---*- go 60

°'

. l C) Olf/03/81 CR NOV NOV-12998 REPLAC.'!. WJLTING R.S:PLACE STUDS 1 101081235 60 0

Olf/03/81 011/011/81 Olf/Olf/111 011/0'4/91 IA RR CR fJI PIPING VALVl:

NOV VALv.!

1-IA-X 1700

. HCV-1303A 1-ffi'-279

  • COUW NOT 'l'EST FOR PT 16,'4 OISASSE:NBi! VAivi j{JRiiiSPECTioti REPLACE IXJLTIIIG REPLACE VALVE IIIT~RNA£S .

INSTALLED T!ST C0,,11!'.C'/'IOII iiisPi:CTP.D "VAivf."iiiTkiiW,a RF.PLACE OOLTS CONPLF.TE l

l 1

103131522 1 009i7i351f 101081213 103191930 3'11 3150 .

1959 370

! , - - Olf /Olf/81 ci: - VAi"--- -- rv-cc-ioiA_ _ _iJ:AKS 81 RIIR ix: isoLATioi-vA°tvi~ iNSTAtikD A.ii.!ii"Ui§if S°i!A,--------- 908261050 .. - 325 .. - -***---. .. ... ....

  • 1* ()

0' 011/011/81 St/ VALVE 1-91-156 CHECK v.ALVE STUCK OPF.lf OPENl'.D FOR IRSP!CTIOII OF CTZAIIUIIJSS 1 910161255 2111 011/05/111 80 VALV.! l'V-80-1008 COUPLING BLOCK £00Sf. . f'IGHTF.11.'!:D BLOCK l 1011051333 . II I

~::~:r-::--*

i 0

.,;-t
~t
;B*--~:~::2t";NS1~~L- ;~;PORT :z;~!i~ ::/:!t!P'-R 8

SKlff'CII +.PROCtrW  !  ::!!!:::: -~::~-------------- --

Olf/07/81 CR VALV! 1-CR~2,1 REPLACE BOLTIIIG R~PLACED STUDS 1 UlU'l:tH3"f 10:t

() *I Olf/07/81 CR VALVLf 1-CH-291 RfPLACE BOLTING REPLACE STUDS 1* 0102318'4'4 157 0 011/07/81 CH VALVE 1-G'R-30'4 REPLACfl: BOLTIIJG RF.PLACED BOLTS 1 0102318116 139

i- 010231916---*-*150"-***-------------*-*--***

011/07/111 *-Rt*- VALi'! i-RL-25 . ii8i>LAc!i iXJLTIIIC .. *-----* -ili!:PLACP.iJ STUDS --

Olt/07/81 C1I NOV RCV-119& REPLIICE BOLTIIJG R.~PUC!.D BOLTS 1 1010111202 157 Cl 0

011/07/lll CR .. NOV f'CV-1122 REPLACE BOLTING -RF.PLACED BOirs 1 101081222 159 157 C

Oll/07 /8i ___ CR 011/01/Af r.r.

NOV VALi'!

i:cv-111sif-- - R"fl:PLACi BOLTI1'G 1-CC-1011 VALVE LHAK 81

. **- . *- - -------* REPLAC.~D BOLTS *----*--------*- * *---*--*--1-*io1oe12J&

RF.PLACED VALVE 1 909092215 613 .\o:

--*- -------***--------- I 0

--**oitio11s1 Olt/10/111 CR cc VALVl l'f/Hf' RV-G'R-120111 t-<:C-l'-28

~Utr.f' VALVE U'.AKitrr. TO AT/lfO.'i PUHP VER1 IIOIS1 JIRF.11 S'f'ARTED rw.r.HHAl/r,tr.n VAC.V~

REBllILT PUNP

---*---1 1

l 917192000 0091't06't0 9J.

o: f

-~--- oii/io/ili ilt VALVE i-Ri-21 ilEPiAtt llOiTIRG -* ---* *-*** -.. il.~PtActo IJol'fS. . *-* . . . -.. 010231911 IIIJO 0  ! 011/10/111 BR VALVA' 1-BR-211 RF.PLACE BOLTIIJG R!PLACfl:D STUDS 1 01l191SJO 22 ()I l

f.

~.

~,

~ - i :

  • - HA1 81
  • 11112 AH PA~ 2
  • l/NITl- 5/0q/81 (HAIIIT!lfA~! OF SAFF:TI REl;ATF.D SISTF.NS Dll~~G OUTAGF. OR R'-Dl/CF.D P<MER PERIODS)

. RF:TSF.RVDT SIS CONP NAR1Clf0 SUHNARI JIICPF.RF u NR TO'l'IJIIITH  :

-*-oti/10/81 BR VALvt. *-. i-BR-2os***----li!.l1lACI!. liOi'filiG .. -* *-------- -------**1Rt.PLACF.D STUIJS *-- -*-- -----'* **---*1*-0111!1151f9 *-- 208 Oq/10/81 BR VALVE 1-BR-10'1 RSPUIC!. IXJLTING RPPUICED BOLTS 1 0111916oq 22 oq/10/81 BR VALVE l-BR-216 REPUIC"!! BOLTING REPUICf. STUDS 1 011191620 22 Oq/10/81 - BR VALVt *- 1-BtHU ... --**-- RF:PUCt. BolTING . **-**-** --* -- RF.PlACED BOLTS -- -*- -* --- ***- . -* -- *- 1-0111916311

  • 22 r* Olt/10/81 BR VALVE 1-BR-115. REPUIC"!! IXJI,TING REPC,AC,'lf:D STUDS 1 011191650 22 oq/10/81 BR VALVE l-BR-61 REP£/ICE BOLTING REPLACF.D STUDS l 011191820 21122

[ - - 011/10/81 BR VAC.Vt. *-- l-BR-106----R.ri:Pc.ACE BOLTING --- ---------------- RF.PLACED IJOlTs**-*--*-*-------*-*--1-0lU918111f 22

~ 011/10/81 BR VAI,Vf. PCV-BR126 RF.PLACE BOLTING RP.PLAC.~D STUDS 1 011191935 22 I

011/10/81 FC VALVE 2-E'C-1q REPLACE BOLTING REPLACED BOLTS 1 012081103 27

Olf/10/91 l1C VALV!. . . HCV-ISS&B -*--***- REPLACt. IJOLTING .. - --*- *-*-*-*----- REPLAC.~D STUDS . - -*- --- *--- --* *-**--1--0121011100 188 i:

~ 011/10/81 RC VALVE HCV-1551C RF.PLACE BOLTING RF.PLACED BOLTS 1 0121011101 188 -rp r,,:

011/10/81 RC VALVE HCV-1556C Rr.PLACF. BOLTING RF.PLACED BOLTS 1 0121011102 189 ,.

--*-* Olt/10/81 -* l1C. **--vALVt. --* HCV-1551A *---REPLACE BIJLTING -- R!PLACEO STUDS -** .

  • 1--*01 no11112 1118

, f' 011/10/81 RC VALVE IICV-1556A R"!!PLACE BOLTING REPLACE STUDS l 012101110 188 011/10/81 RC VALVE HCV-1551B REPLACE BOLTING RF.PLACED BOLTS 1. 012101111111 188

,--- fiq/10/81 si - *- GAGS . *- .. t-1-$.i-106A ___ GAW. IS WCKF.D *-**--*--------- RF.li/:l/F.I) GLASS. -**-------*-*-*--- -----1-1o*i061901 1111 0'1/10/81 CH VALVE NOV-12818A BODI-BONNET LEAK TIGIITEN fLANGr. 1 10'4070120 78 oq/10/81 ff/ PUNI' 1-flt'-P-3A PACKIWG £SAKS 80TB ElfDS ADJUSTED PACKING 1 10'1070800 69

- 0'1/io/lii *- tii - -* MP*--- '2-tli-P-iC ___oit. l!AK 'l'lCll'i'F.N IJNf(JN - 1---io1aonon30 - - - 33 -----------****i 011/10/81 RN PUMP RC-VG-109 REPLACE VENT RF.Pl.ACED PUMP 1 1oqo92200 36 -..J *.

Olt/12/81 SC VALVE 1-SI . REPLACE BOLTS R.O:PLAC~D STUDS 1 OlOOJ.1331 91 I

Oq/12iaC""c" VAiVJ - - . i-cil-236 ----~iit.Pt.Act. BOiTtiio ilei'iAct.jj STUDS .. . .--010~31S19 **-*--* !171

~ *,

  • i n*ll?IAl CR VALVE rv-120, REPLACE OOLTING R.11.PT.ACF.n ,t;TI/D!t 1 01023181fll

, --Oit/12/111 BR VALW: l-BR-192 REPLACE BOLrIN(l .. ~ RF.E'tAC! Sft/DS . -------- i 0111g153'i *--,u2 ---- - - - - - *

  • 011/12/81 011/12/81 BR SI VALVJ VALV!

l-BR-197 RV-1859 RF.:l'LACB

, . ~Pc.ACE BOLTING OOLTilfC .

REPLAC!! STUDS REPLACED IJOLTS .

  • 1 01119ti;35 1 *012os1u2 6

6 I

. 011/12/lii -- llC **-. VALV!' *- .. l'l':V-1it5SA*~-- htPLAtE BOittitG **-:---------------* REl'lACEO BOLTS -------------1-ot210lli09 6.

~ 011/12/81 RC VALV! l-RC-125 Rl':PLACF. DIAPHRAH RF.PLACED DIAPIIRACN l 10lf08131t5 68 I fl, I 0"/12/11 RC VALVE 1-RC-119 REPLACE DIAPHRAN OVERHAUL VALVF. l 1011081350 68 *

--o ..,u,u -*nc--vAtvJ*-*** *t-Rc.:.w, "REPLACE DIAPNRAN *------* OVERHAULED VALvr.-- 1-1oq0913511 ..... 611 ------**---***--- .. -*

  • oq/12/81 011/12/11 RC RC VALVE VALVE 11-RC-112 1-RC-109 REPLACE RF.l'LACE DIAPHRAH DIAPHRAH REPLACED DIAPNRACH Rr:PLACED DIAPIIRAGH 1

l 1011081356 1011081357

  • 81 89 1
--- Olt/12/81 *- l1C *-* VALVE ---* 1-RC-108 *-*-*--Rtl'LIICB DIAPURAN . -*-- -*-**-------* RI!PLAC!!D DIAPHRAGN*-**-*---*-*-*-- *-*-----1*--101'1081359 69
  • / 011/12/81 RC VAL.W l-Rt'-151 REPLACF. DIAPHRAN RgP£ACF.D DIAPHRAGH 1 1011081-0l 88
nrill ?IRl RC VALVE 1-l<<:'-113 REPLACE DIAPHRAH RF.PLAC.C:D DlAPRRAGH 1 101101111103 68 i 0-/13/8i BR VALW: 1-BR-319 VALVE HAND ~HF.EL fRETINR!!~LS R!!PUICED BOlfNET 1 009181516

- * - 01111~/AI -- r.c .... VALV! . rv-cc-101 -*-::.-.-:-*.-vALV!. FAIUD TIPJ r: TR.t:'l' .. ---------*--R.~PAin VAT,VP. . -****----*-----:*-*-***--1-1011011101:1

,I

HS SNUBB!R 1-SI-HSS-21A R!PAIR AND TEST TESTED 1 10~101020 11 I o"/13/81

--*-**oit/U/lll . us -- . SNtJ8IJtR 1;.S1-HSS-'i1 B-ll~l'AIR ANIJ f'P.St ---*--*-----*-------*-* rtS'fEO *-**-- - - . *- ------- -- - - - - 1 *-*101i101021 .. 71

, 011/13/81 HS SNUBBER 1~sI-RSS-26 R~PAIR AND T~ST TESTED 1 1011101022 71 ti*

011/13/81 RS SNUBB"!!R 1-SI-HSS-20 REPAIR AND TEST TESTED 1 1oq1010n 71

  • -**** 1-$I-NS$-2S *- . R.C:l'AIR ,!NI) t.r:s'I' r.irsr~v *-* *10 1;10,0211 71 oli/13/ili 1/S SNIJBB.~ll

,, 011/111/81 !I'!! DI!SF.r.  !:DG-1 l'"!!RFORN PffS Pf.RFORM!r.D PNS 1 0071109111 1128 0

r !r

~'

f.i)I' UNITl- 5/011/lli (NAINTL':NAlf~!: OF SAE'.rcrl RU.AT!.D SlSTF.NS OOHING OUTAG.r. OR R.":OOCP.D l'CM!?R PERIOnS)

II NAl 81

  • 11112 AN PAC!. 3
  • I R::TSF.RVur

- - oif/iit/lii srs t;,;

coHP VAiVt NARKNO SUNNARf JIKPTi:RF i-ai-75 ------>>~PiAt.C: BiiTtNG - -- -----------------*-fl.=:pe,AtR st/Jo$ ----------------- *-----1*---010231101 u NR TUl'rJINTN

--- 31 011/111/81

,__ .. 011/111/81 011/ill/el CH CR BR VALV.":

VALVF.

VALVE t-CH-201 RV-1209 RSP£AC~ l10LTING RF.P£ACf l10C.TING HCV-BR-i03-- ---- R.C:Pitic5: lXJLTil'iG REPLACED STUDS RC:PLAC.'!: STUDS

.. - **------------ R.li:PC,,ic.~o BOC.TS 1

1 0102317111J 0102318'19

-*-* - ----*-*-- **- *-. . ----1-*- 011181539 31 31 Atili I

I 011/111/81 011/111/81 FC FC VALVL':

VALV.":

l-FC-118 1-FC-32 RF.:PLAC.rz: BOLTING RF.:P£AC.": W}l,TING R!':P£AC:'!:D BOC.TS R.G:P£AC.~D BOT,TS 1

1 012081115 012081118 25 25

  • 011/111/81 . Fe. VALV.~ i-FC-33 -----R.~l'iACE WJl,TINc** *- - - - ----RF.PLACtr.n BOT,TS . -----------*-r-*012081119 25 e

I*

  • , 011/l'l/81 RC VALVE HOV-1536 RF.:P£AC! lXJl,TING R.'!:P£ACED BOC.TS 1 012101*106 37
  • . 011/llJ/81 RC VALV! HVV-1535 R!':P£ACE IKJLTING RF.PLACED BOT,TS 1 0121011107 37 r---- ::~::~:! ~ ~~f~: A:'V-1ii558 --*-R.S:E'£AC! EJOl,TING E\'..'V-1115SC R.S:Pl,AC.'!: BOl,TING
  • - -**- RF.P£ACF. STUDS RF.;Pl,AC.'!:D BOLTS

**---* -*-T- 0!2101 .. 011 1 012101.. 10 37 37

, OIJ/111/81 RC YAC.V!' E\'..'V-11156 REP£AC.S: BOLTING REE'C.ACF.D BOLTS 1 012101"11 37 011/111/81 . RC - VALVP. *--. rv-iSi9A _____ REl'MCE roiT.ItiG RF.PiAC~ STUDS -- l oi2ioii,1j 31

  • 011/111/81 CR NOV FCV-1160 RF.Pl,ACE BOLTING REPLACE STUDS 1 101081223 37

.! 011/111/81 C1I HOV tcV-1115A - REPLACE IJOLTING REPLACED BOl,TS 1 10108122" 31

  • Oll/i6/111 OIJ/16/111 1JI lJI 011/16/ili .. FC VALVI VALVL':

1-CN-10 --

1-LJl-1511 VAiVt - *- i-Fc-1z ______ RF.Pi,,ict RSP£AC1f.

R!.PLACE BOLTING 80LTING iJoiTtNG . -*. *--------

RP.P£ACL': BOLTS REPT,ACP.D BOLTS RP.PUC.'!: BOC.TS*----

1 1

011171027 0111710511 27 27 1.-01ioeit21 -*-,1i1g-- ----- *- - ...... I.

I

~ *

  • OIJ/16/81 011/16/81 FC FC VALVE VAC.VS

- - 0"/16iiii --*;;s--VALVE ----i-Hs-lio 2-FC-11 1-FC-11 RFE'£ACE RF.PLACE

"'iiP.iJiiito BOLTING BOLTING REPLACE IJ()LTS R!PLACE IKJT,TS 1

1 OR REPiA~-VAC,VL': m*IJ~,----REPLACED VALV... ---------~--1011010~02 - - is*----------------*----------

0120811115 Ol208111f6 21f19 249

  • f Oll/17/91 CR NOV OIJ/18i8l --- Di *- VALVE .

127SC 1-CN-21 VALVr. OPFRATIOII STIFF REPLACE BOl,TING -- -

. BIICIC'!':D OFF PACICING Ge.AID IIA/fUAC.C.1 OP !

--Rl.N."Jll-D BOLTS 1011150710 29

. -- .... ------ --- - . ---r-oii110958 -*- .. iii *- .... - --- . ---*.

011/18/81 BR YAC.VE 1-BR-182 REP£ACE BOLTING RF.PLACED STUDS 1 011191550 38 Olf/18/81 CR NOV 12758 VAC.VE OPERATION STIFF CAUStNG BACKED OFF PACICIIG Gr.AND 1 104150712 53

- - 011/ioiaC- cs VALV.! 1-CS-19 R!PiACF. 1J()l,TCNC ... --------* - RFPC,AC! sriios + oiiif>iiiWi l *010011101 - -

  • 18 - *------ ...

011/20/111 BR YALV!' 1-BR-265 REPLACE BOl,TING R.11:PLAC!'D BOl,TS 1 011181531 2085 Olf/20/81 BR VALV! 1-BR-268 RP.PLACE BOLTING RSPC.AC!'D BOLTS 1 011181532 2085 oii/20/81 BR YAC.VE 1-BR-69'.----RF.:PLACE: IJOl,TING *---*-- --- R!r.PLACF: STUDS - --- - - - 1 011191737 17

      • i OIJ/20/81 . BR 04/20/81 FC YAC.V!

VAl,VE 1-BR-1111 l-FC-19 RF.PUCE BOLTING REPLACL': BOLTING R_.!PLAC8 STUDS R!!PLAC,P.D BOl,TS 1

1 0111917311 012091131 17 2519 Olf/20/81 RC VALVL':*-

  • l-RC-1111 REPLACE DIAPHRAN--------------- CHANGED DIAPHRAH------------f-10IJ081351 256 ---**-* ------- ---**---

Olf/20/81 RC VAl,VJ 1-RC-152 REPLACE OIAPHRAN CHANGED DIAPHRAGN l 104081353 256 oii/21/81 CR VALVE 1-CH-232 REPLACE BOLTING REPLACE STUDS 1 010231520 lf8 011ht/B1 cli VAC.V" ..... 1-CR-ifr_________ Rtl'£AC.C: BOl,TING . *-* ---*-. ------- - - - - - *--*R.F.PiAci.iJ STUD..t; . --- .. ---- --* *- *----r-** otoni 52i "8

~ *! OIJ/21/81 CH YALV.'!.' 1-CR-231 R!'.P£ACt. IJ()l,TING REPiAC1. STUDS 1 010231S22 118

. 011/21/81 CH VALVE l-CR-2011 R.'!.'PLACE BOLTING _ . REPLAC.'!.' STUDS 1 010231815 lf8

  • -oifi:Hi8i'- CR --VALVK - 1-CR~230 _________ R!P£ACE lXJT,TING ***- *-------*-----------REPLACE STUDS ---- --*-----------------i otont11*12 118 -----*--* *- -------**- --

0 Olf/21/81 BR YALVI 2-BR-91 REPLACE BOtTING REPLACE STUDS 1 011181536 lf8 Olf/21/81 BR VAT,VL': l-BR-91 REPLACL': IXJLTIIG RF.:PiACE STUDS 1 011191921f 48

-*- -*- Oii/2i/iii HS VALV! 1-ilcV-N$-161C ... - RF.PAtR f.IHITORQtlE ... ktPAtRRIJ lINITOllQIJf. -* 1 .. 10305HOO 10011 I. .:

1

(> oii/21/81 RC VALVE REPLACE DIAPHRAN CHANGED DIAPHRAGM 1 10lf081Jlf7 280 () ;

-~

&.I If HA1 81

  • 11112 AN PAGE -

UNIT1- 5/0lf/81 (HAill'1'!11Af!CE OF SAF!TI RELATED SYST.ri:HS IJURING __OIITAG! OR REWCED PCflER_PERI_ODS)

  • R!TSFRVIJ'I S1S Olf/21/iit CO#P RC . YA£VE NARKNO SUHHARI 1-RC-153 --*fitlit,Ac.~ iJIAPHRAN JIKPF.RF

. -*** ****- -*****-- tllANGE/ibtAPHRAN -* **--***** .. *-* -*******-1*-*1oi.011131f8.

u HR TOTCNNTH 2110 Olf/21/81 Olf/21/81 oq/21/81 RC RC NS YA£Y!

YA£Y!

VAC,V.!

1-RC-120 1-RC-11S REPLACr. DIAPHRAH RP.PLACr. DIAPHRAN TV-NS-10111 -***--- llEPACIC iJ!FOR.~ STAlrt-lJP' CHANGED DIAPHRAGM CNANG:~:D DIAPIIRAGH

..... *---* *-**' ll!f:PACk.r::D VA tr.~ . . - . -*-**.

1 1

10lf08131f9 10lf0813S2

.. -**** *****-* I*-* -*101t1310:30 280 280 166 Olf/21/81 HS YALV! TV-HS-101C R!PACK BF.FORP. START-UP $REPACKED VALVE 1 10lf131031 166 ~

Olf/22/81 CH YA£YF. 1-CH-SO REP£ACE 8QLTING REPLACFD BO£TS 1 010231509 2057 Olf/22/81 .. CH ... VALV!. 1-Cll-65 . ----RF.PUC.'!. BOLTING . **-***-* ---------*RF.PUCED BOLTS . ---*-*-------1-01onts11 .. 2057 Olf/22/81 CH YA£VI': 1-CN-60 R.C:PLACP. 8QLTING R.':PLACEO HOLTS 1 01023180'f 2057 ~

Olf/22/81 CN VALVE 1-CH-66 RF.PLACE 80£TING REPLACED BOLTS 1 01023180S 2057

-* .. Olf/22/U RL .. VALV.! .. t-RL-6 *--- REPLACE IJ()LTINC --*------** RF.PUCP. STUIJS **-***-*---***** -***----- 1**-ot023l9111 *1273 Olf/22/Bl Olf/22/81 BR BR VA£V!

YALVF.

1-BR-252 1-BR-3" REPLACE WJLTING RF.PLAcr IJ()LTING REPLACED 80£TS R'!.PUICF.O BOLTS 1

1 01119161f8 011191736 lfO lfO *

-**- Olf/22/Bl *-* CR .. VALV.... - -* ccv--cn-u1s.r-noD1 TO IJONNP.T £EAK*sr=1r, RP.PLACFO CASKET 1-912171537 *---*-* 18 *----**-*

Olf/23/Bl Olf/23/81 Ff/

CR HOV VALVr.

NOV-flt'-160A l*CN-52 VALVY. JIILL NOT OPE/f REPLACE OOtTING COHPLF.TP.

R.t::PLACF.D OOLTS 1

1 006120630 010231507 "6

2091 *

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HEALTH PHYSICS APRIL, 1981 lhere was no single release of radioactivity specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20.

There was one (1) individual '!:7ho received single radiation exposure specifically associated with Unit #1 & 2 outage, which accounted for more than 10% of the* allowable annual values in 10CFR20.101.

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- PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR SAFETY AND OPERATING COMMI'lTEE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS APRIL, 1981 None during this reporting period *

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