ML19320C569: Difference between revisions

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PROCEDURE REVISIONS THAT CHANCED THE              ' ~
PROCEDURE REVISIONS THAT CHANCED THE              ' ~
OPERATING MODE DESCRIBED IN THE FSAR JUNE, 1980 None during this reporting period.
OPERATING MODE DESCRIBED IN THE FSAR JUNE, 1980 None during this reporting period.
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!                Maintenance of Safety Related Systems During Outage or Reduced Power Periods 4
!                Maintenance of Safety Related Systems During Outage or Reduced Power Periods 4
l                                            UNIT #2
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,                                                    HEALTH PHYSICS JUNE, 1980
,                                                    HEALTH PHYSICS JUNE, 1980

Latest revision as of 20:56, 18 February 2020

Monthly Operating Repts for June 1980
ML19320C569
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/07/1980
From: Dunn S
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139A450 List:
References
613, NUDOCS 8007170391
Download: ML19320C569 (41)


Text

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Ag VIRGIIIIA ELECTRIC A';D POWER COMPANY SUPaY PO'4ER STATION MONTIILY OPERATII!C REPORT FIPORT ?!O. 80-06 JGE , 1980 i

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APPROVED:

_h' A jYM M RuiAGER 1

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80 0 717 0 39l

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  • ' CONTEUTS Page Section 1

Operating Data Report - Unit #1 2

Operating Data Report - Unit #2 i

Unit Shutdowns and Power Reductions - Unit #1 (Corrected Copy) 4 Unit Shutdowns and Power Reductions - Unit #1 5

Unit Shutdowns and Power Reductions - Unit #2 6

Load Reductions Due to Environmental Restrictions - Unit #1 7

Load Reductions Due to Environmental Restrictions - Unit #2 8

Average Daily Unit Power Level - Unit #1 9

Average Daily Unit Power Level - Unit #2 10 Su--ary of Operating Experience 11 Amendments to Facility License or Technical Specifications 12

Facility Changes Requiring NRC Approval 12 Facility Changes That Did Not Require NRC Approval 14 Tests and Experiments Requiring NRC Approval 14 Test and Experiments That Did Not Require NRC Approval 15 Other Changes, Tests and Experiments 16 Chemistry Report 17 Description cf All Instances Where Thercal Discharge Linits Were Exceeded 18 Fuel Handling Procedure Revisions That Changed the Operating Mole Described In 20 The FSAR 21 Description of Periodic Tests Which Vere Not Completed Within The Tine Limits Specified In Technical Specifications 22 Inservice Inspection 23 Reportable Occurrences Pertaining to Any Outage or Power Reductions Maintenance of Safety Related Systems During Outage or Reduced Power 24 Periods - Unit #1 - Mechanical Maintenance

11 CONTEI!TS Page Section 26 Maintenance of Saf ety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 29 Maintenance of Safety Related Systens During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 31 Maintenance of Safety Related Systens During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 34 thintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance 36 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance 38 Health Physics Su nry 39 Procedure Deviations Reviewed by Station Nuclear Safety and Operating Committee Af ter Time Limits Specified in T.S.

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O?ERATING DATA RE?O?2 DOCEET !;O. 50-280 DLTE 02 JUL So COMPLETED EY sus D. Dy';N TELE?!!ONE 804 351-3184 OPERATDG ST/2US u........ ......

1. UilIT liAME SURRY UNIT 1
2. EE?OliTit;G ?ERIOD 60180 TO 63080
3. L1CEliSED ThEEMAL PO'!ER liGT) 2441 \~'*~"~'~~~'~~~~~l
4. hANE? LATE EAT 1tiG (GROSS /GE) 841.5 l NOTES l
5. DESIGN ELECTRICAL RATING (!!ET lGE) 922 l l
6. NAXIi:UN DE?EtiDABLE CA?ACITY (GRCSS !GE) 140
1. laAXINUN DE?EADABLE C/2ACITY (!;ET lGE) 104
6. IE CnAhGES CCCUR Itl CAPACITY EATINGS MAXIiWM DE?. C/2ACITY(GnOSS~ NET)

(ITEMS 3 THROUGH 1) SINCE LAST RATING CHANGED UJE TO is3 BLADING hE? ORT. GIVE REASCh5 kbMOVED FROM B2?H L/? I:CTORS.

5. ?OJER LEVEL TO W!iICH EESTRICTED. IF Ally li/A (NET IGE)
10. i:EASONS FOR EESTEICTIONS. IF ANY li/A Tii!S MOf.Tii YRrTO-DATE C*iMULATIVE
15. h0URS Ik lie?OhTING PERIOD 120.0 L36I.0 65551.0 1'2. TiUMBER OE li00R5 RE/,CTOR WAS CRITICAL 105.1 2209.1 40961.3
13. REACTOR EESERVE SiiiiTDOWl; ROURS 0.0 1S2.6 3131.5 14 HOURS GENERATOR ONeLI!;E 101.5 2153.1 40098.1
15. UNIT RESERVE SSUTDOdN HOURS 0.0 193.6 3136.2
16. GEOSS THEiri;AL ENERGY GEhERATED tlUti) 1693155.0 5265505.0 52383611.0
11. Gh0SS hLECTRICAL El;Ei:GY GENERATED (103) 50/500.0 1631460.0 20311958.0
18. i;ET ELECTRICAL EliERGY GE!l\ ATED ((Gli) 415BB6.0 1545355.0 2S112185.0
19. UNIT SERVICE FACTOR 91.4 olo 50.2 olo 60.8 olo
20. UNIT AVAILABILITY FACTOR 91. h clo 54.L e/o 66.5 olo
21. UNIT CAPACITY FACTOR (USING 1:DC NET) 9 ', . 7 * / o 50.3 olo 62.0 olo'
22. UNIT CA?AClTY EACTOR (USING DEE NET) St.1 olo 43.1 olo 53.1 olo
23. U!;IT F0itCED OUTAGE RATE 2.6 o/* B3.6 olo 46.1 olo
24. SHUTDCdNS SCHEDULED OVER NEXT 6 MONTHS 09-15 50 - S/G RE?LACEMENT (TY?E.DATE.AND DURATION OF EACE) OUTAGE REFUELING o 1 YEAR
25. IF SliUT DCali AT EbD OF REPORT ?ERIOD.

ESTlNATE DATE OF STAETU?

26. UNITS IN TEST STATUS FORECAST ACHIEVED

(?R10R TO COMMEi:CIAL O?ERATION)

LAITIAL CH1TICALITY lu1T1AL ELECTRIClTY -

CO:NcEXCLAL OPERATION

OPEhATING DATA hE? ORT DOCi(ET NO. 50-231 DATE 02 JUL 80 COM?LETED BY suz y, pugs TELE?dO"/E 804-351 3164 O?EEATB.;G STATUS

1. UNIT (;AME SUhRY UNIT 2
2. AEPOATR;G TERIOD E0180 TC 63080
3. L1Ct;NSED THERMAL POJEn (NAT) 2441 \'~~~~~~'~~'*'**'I 4 NJ:iE? LATE EATIbG LGEOSS !NE) 641.5 l NOTES l
5. DESIGl. ELECTEICAL EATIGG (!iET RdE) 822 l l
6. MAXIMUN DE?EuDABLE CAPACIT! tGEOSS lGE) 611 l l
l. MAXDGM DEFENDABLE CA?ACITY (NET KdE) 115 l +r . . .. - t.- ~<vr c

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6. IE Ci!A.;GES OCCUR IN CA?ACITY R/ TINGS li/A (ITEMS 3 TilnCUGH l} SINCE LAST REPORT. GIVE EEASONS S. ?OJEn LEVEL TO WnlCli EESTRICTED. IF ANY N/A (NET XJE)
10. REASOtl5 FOR RESTRICTIOil5. IF ANY li/A TilIS M0!;Til YR-TO-DATE CUMULATIVE
11. liOUES IN EEFORTIllG PERIOD 120.0 4351.0 62 01.0
12. NUMBER OF fiOURS REACT 0E WAS CFlTICAL 0.0 0.0 34436.5
13. EEACTOR EESERVS SH*iTDCAN liOURS 0.0 0.0 0.0
14. iLOURS gel.ERATOR ON-LINE 0.0 0.0 33996.2
15. li&IT EESEEVE ShUTDOdli HOURS 0.0 0.0 0.0
16. GROSS TiiEEiAL ENERGY GENERATED (!GH) 0.0 0.0 15154033.0
11. Gh0SS ELECTRICAL ENERGY GENERATED (!Gli) 0.0 0.0 25668844.0
16. NET ELECTEICAL EliEEGY GENERATED (!GH) 0.0 0.0 24536605.0
19. UtiIT SERVICE FACTOR 0.0 0.0 54.1 olo
20. UNIT AVATLABILITY FACTOR 0.0 0.0 54.1 */o
21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 0.0 50.4 olo
22. iiNIT CA?ACITY FACTOR (USIuG DER NET) 0.0 0.0 41.5 */*
23. U:iIT FOR:ED OUTAGE RATE 0.0 0.0 20.1 olo 2L $E*iTDOdh5 SCHEDULED OVER NEXT 6 MONTHS (TY?h,.DATE.AUD DURATIOi. OF EACE)
25. IF S?iT DOdN AT EliD OF EE? ORT ?EFlOD. 1/10/B0 ESTI!< ATE DATE OF STARTU?
26. UNITS IN TEST STATUS FORECAST ACHIEVED (Fi: EOR TO COMMERCIAL O?EliATION)

LVITIAL CRITICALITY INITIAL ELECTiiICITY CON:iERCIAL OPERATIOli .

CORRECTED COPY DOCK ET NO. 50-2Bn UNIT 51101110WNS ANI) POWElt itEDUCTIONS UNI f N AM E _Surry nuit.-.1_ -

D ATE htly_1,_lS00--

COMPl.ETEO IlY Sire D. Dunn ItEPullT MONI!! !!AY - 19R0 I El.EPIIONE _ f Rn4) ts7 1134

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CJuse & Corrective

-, .23 3 .$ ' litrHsec ['t., '1, Attion lo No. Dale g gg d Jj g 5 Event u] n. ]

l'~ jE $ 35:

Itcpori it diu v

!O Present itecurrente 1

6 80-018 Continuation of shutdown for piping 80-7 5-1-30 F 260.9 D 1 restraint modification and turbine rotor inspectiin which began 2-19-80.

3 itcactor trip caused by f eed flow / steam 80-8 5-11-80 F 1,9 C flow mismatch with 1.o S/G Icvel signal while feeding S/G's in manual during escalation of power Inadvertant boration of primary system 80-9 S-12-80 F 0 G 4

' when "B" mixed bed dcmineralizer was placed in service without verifying boron concentration of effluent was equalized with primary system boron concentration. Inadvertant boration caused Aff to remain outside target band for greater than one hour la a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period necessitating power re-

<1nctinn t n < ifiZ._ power nn t.11 Af uirhin y targetbangfor24 hours.

Itcason: Method: Exhibit G - Instruttions F: Forced fue Preparation of naia A Equipment Failure (Explain) 1 -Manual

5. Sched" led Entry Shects for 1.iccince il. Maintenance of Tesi 2 Manual Scram.

3 Automatic Scrarn. Event Itcposi (1. Ell) File INtill! G-CJtefueling 4.Other ( Ex plain) 01611 D Regulatory Restriction E. Operator Training & IJcense Examination 5

F Administrative G Operational Error (Explain) 1.Thihii 1. Same Source

  • l's/77 ) Il-Olhe r (E xplain)

. . . _ . . . . _ . _ _ - _ _ . . _ . . _ _ _ _ _ _ _ _ . __ _ _ ~ , . _ . _ _ .. . . _ . ._ _ . . - . . -

DO KET 0. 50 280 UNITS!!U1 DOWNS AND POWElt REDUCTIONS DATE July 7, 1980 COMPI ".TED IlY S"e D- D"""

REPORT MONTil JUNE, 1980 TELEPl!ONE (80/0-357-3184-

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- ;, .! ? $ I Licensec 54, . Cause & Corrective No. Date & Eg j=

i!! ,8 s 5 Event 3,*g mU p Action to I- $ j f3 Report # gf Present Recurrence 6

80-10 6-3-80 F. 18.5 A 3 80-29/03L-0 Experienced a turbit runback, reac-tor trip-turbine trip and safety injection initiation upon loss of power to the I-IV Vital Bus. The loca of the I-IV Vital Bus was 4

caused by an- clectrical fire in the sola transformer supplying pow-er to it.

i I 2 3 4 F: Forced Reason: Method: Exhibit G. Instructions S: Scheduled A Equipnient Failure (Explain) 1-Ma iual for Preparation of Data D. Maintenance ai Test 2-Manual Scra m. Entry Sheets for Liecnsee i C. Refueling 3 Autornatic Scram. Event Report (LER) Fde (NURI.G-D Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & License Examination F Administrative 5 -

- G-Operational Error (Explain) Exhibit I Same Source P)/77) 11-0t her (Explain)

. DOCKET NO. 50-281 UNITSliUTDOWNS AND POWER REDUCTIONS UNIT NAME Surry 1: NIL 2_,

DATE July 7, 1980 COMPLETED fly Sue D. Dunn REPORT MONTig JUNE,1980 TELEPIIONE : (dol t ) 357-3184 e,

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,$E 3 *E Licensec ,E3, t Cause & Currective Date 3g )s3 Event 3,7 j3 gu- Action to

. No.

H L @ E j] gg c u) u Prevent Recurrence yE c2 e g Reportst uo O

80-6 6-1-80 S 720 D 1  : Continuation of shutdown for refuel-ing and steam generator replacement, which began on 2-4-79. Work still underway on piping restraint modi-fications required prior to unit recovery.

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I 2 3 4 i F: Forced Reason: Method: Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of [hta Il hNntenance of Test 2 Manual 5 cram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (1.l!R) rue (NilREG-D Regulatory Resttietion 4 01her (Explain) 0161)

E-Operator Training & License Examination F Administrative 5 G. Operational Er ror (lixplain) Inhibit I Same Source pl/77) ll Olher (Explain)

l LOAD REDUCTIONS DUE TO E!!VIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: JU'E , 1980 DATE TIIE HOURS LOAD, MW REDUCTIONS, !f4 FfG REASON No:le during this repc rting period.

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MONTl!LY TOTAL

LOAD FIDUCTIONS DUE TO ENt/IRONMENTAL RESTRICTIONS UNIT No. 2 MONTH: JUNE, 1980 LOAD, MW PIDUCTIONS, MW IfId REASON DATE TI!F HOURS Nc ne during this reporting period.

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MONTHLY TOTAL

DOCKET NO 50 280 UNIT SURRY I DATS 7 1e60 COMPLETED BY syg g, pyyy dEEBAEE RAILE EEIZ EGEER LEEEE EQEEE: JUNE 80 AVERAGE DAILY ?OWER LEVEL AVERAGE DAILY POWER LEVb DAY (MWE NET) DAY (MWE. NET) 1 G60.9 16 688.1 2 670.3 17 695.1 3 60.0 18 692.1 4 672.3 19 694.7 5 679.2 20 697.0 6 676.0 21 695.7 7 677.7 22 695.3 8 686.6 23 690.0 9 691.9 24 680.8 10 695.8 25 681.8 11 E95.4 26 690.7 12 694.4 27 691.7 13 693.9 28 690.0 14 ,

693.3 29 689.1 15 686.9 30 688.7 DAILY UNIT POWER LEVEL FORM INSTRUCT'ONS ON THIS FORM. LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWEeNET FOR EACH DAY IN THE REPORTING MONTE. THESS FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORTe ING MONTU. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING F THE UNIT. TBERE VaY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 =/o LINE (OR THE RESTRICTED ?OWER LEVEL LINE). IN SUCH CASE.S, THE AVERAG5 DAILY UNIT POWER CUT?UT SHEET SHOULD BE FOOTNOTED TO EX? LAIN THE APPARENT ANOMALD

DOCKET NO 50=281 UNIT SURRY II DATE leta80 COMPLETED BY Suc D. buna '

dEEddEE EdILL EEEE EEEEE LEEEE EQEEE: JUNE 80 AVERAGE DAILY ?OWER LEVEL AVERAGE DAILY POWER LEVQ DAY (MWE NET) DAY (MWE NET) 1 0.0 16 0.0 2 0.0 17 0.0 3 0.0 18 0.0 4 0.0 19 0.0 5 0.0 20 0.0 6 0.0 21 0.0 1 0.0 22 0.0 8 0.0 23 0.0 9 0.0 24 0.0 10 0.0 25 0.0 ,

11 0.0 26 0.0 12 0.0 27 0.0 13 0.0 28 0.0 14 0.0 29 0.0 15 0.0 30 0.0

, DAILY UNIT POWER LEVEL FORM INSTRUCTIONS ON THIS FORM. LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORTe 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 e/o LINE (OR THE' RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGE DAILY UNIT POWER CUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALE

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SUMMARY

OF OPERATING EXPERIENCE JUNE, 1980 Listed below in chronological sequence by unit is a su==ary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents.

UNIT 1 June 1 - This reporting period begins with the unit at reduced power (97%) due to sodium carryover in the main uteam system. Increased reactor power to 98% at 0135.

June 2 - Increased reactor power to 100% at 1345.

June 3 - Experienced a turbine runback turbine trip reactor trip and safety injection (SI) actuation at 0004. The cause of the above trip and SI was an electrical fire in the sola transformer supplying Vital Bus I-IV, Lost power to Vital Bus I-II at 0015 while attempting to parallel BUSSES I-II and I-IV. This resultr.4 in a re-initiation of the SI lystem. Returned the vital busses to nor=al at 0944 with Vital Bus I-IV supplied by a sola transformer and Vital Bus I-II supplied from an inverter. The reactor was taken critical at 1422 and the turbine generator was on the line.at 1836.

June 4 - The unit reached 100% power at 0600.

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

UNIT 2 l

June 1 - This reporting period begins with the unit at cold shutdown with maintenance, piping restraint modifications and design changes continuing.

June 30 - This reporting period ends with the unit at cold shutdown with maintenance, piping restraint modifications and design changes continuing.

RiENDf!ENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIO?iS .,

JUNE, 1980 Tone during this reporting period.

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FACILITY C11ANGES REQUIRING * -

NF.C APPROVAL JUNE, 1980 None during this reporting period.

FACILITY CHANGES THAT DID NOT. REQUIRE NRC APPROVAL The following facility changes were i=plemented during the month of June:

Unit Design Changes DC/77-27 Installation of Sight Glasses in RCS Hizh Point Vent 1&2 1.

Spool Pieces This change ental's the installation of sight glasses which will allow the operators the opportunity to determine core readily when the RCS loop is full and free of any air or entrapped gasses.

So-mnry of Safety Evaluation During full power or hot shutdown conditions this modification will have no effect upon the plant or any safety related equipnent. At cold shutdown the saf ety cargin is enhanced along with the reliability of the RCS vent system.

DC/78-09 Domestic Water and Drains SGR Decon Building 1&2 2.

This modification adds domestic water to the new decon building and pipes waste water from sink and shower drains to the conte "ated waste drains permitting the use of this building for decontn-inntion of containment workers during steam generator outages.

Su=sary of Safety Evaluation .

No changes to Technical Specifications or the F.S.A.R. are precipitated

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with this design change.

DC/78-30 Security System Tie-in at 480V Load Center 1&2 3.

This design change provides for the security system require =ents by using the 480V load centers to supply the electrical needs. Since the loads l

were non-safety related they are fed from norm 1 load centers.

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S e arv of Safety Evaluation This codification will not affect the station operators on the operation of any safety related equipment.

. Facility Changas That Did Not R: quire NRC Apprcval (Continued)

Unit

4. DC/79-S22 Containnent Sump and Steam Dump Isolation on SI 1&2 This modification changes the actuation of TV-MS-109/110/209/2,0 from CLS Hi Hi to Safety Injection. To prevent possible contantnntion of Secondary systems and hot-well in the events of major tube leakage.

Snm nry of Safety Evaluation This design change improves the containment isolation system and will further enhance safe operation of the plant.

5. DC/80-41 Instrument Air / Service Air Soft Seated Valves This design change replaces the present bronze to bronze seated valves with those of bronze to composition surface > in an effort to reduce the leakage problem previously experienced.

Summary of Safety Evaluation The replacement valves are of superior quality and weigh less than those originally ,

installed. In this case the safety of the system will be enhanced and the seismic. load-ing of the lines will be altered conservatively.

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u TESTS AND EXPERIMENTS REQUIRING URC APPROVAL JUNE, 1980 None during this reporting period.

TEST AND EXPERLTITS THAT DID NOT REQUIRE NRC APPROVAL ST-78 UNIT 2 Engineered Safety Features Functional Test was completed on June 12, 1980.

This test performed a system-level initiation of the ESF systems as near emergency conditions as practicable. Function of actuated equipment was demonstrated along with emergency power supply load capacity.

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OTHER CHANCES, TESTS AliD EXPERIMENTS ,

JUNE, 1980 None during this reporting period.

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SURRY POWErl STATION CHEIIISTRY REPORT

. TINE ,, 19, 6O T.S. 6. 6.3.d PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERACE Gross Radioact., UCi/ml p_, _

_ gp_3 3 ., g y _ ,, p_,

Suspended Solids, ppm 0.1 0.0 0.1 0.7 0.0 01 Cross Tritium, pCi/ml 8.39E-2 4.63E-2 6.05E-2 - - -

Iodine-131, UCi/ml **2.30E-1 6.20E-3 1.77E-2 - - -

I-131/I-133 .5398 .2678 .3909 - - -

Hydrogen, cc/kg 48.2 26.3 39.5 - - -

Lithium, ppm 1.7* 0.21* 0.99 - - -

Boron-10, ppm + 70.17* 12.35 22.53 441.784 388.668 415:219 1 Oxygen-16, ppm

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.000 .000 .000 2.8 .1 1.4 Chloride, ppm < .05 < .05 < .05 < .05 < .05 < . 05 pH G 25*C 7.76 6.50 7.34 5.80 4.75 4.97

+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T. S . 4.13. A. 6 j Phosphate Boron 790 Sulfate 834 Chromate .04 50% NaOH 1050 Chlorine Remarks: *Added 1700 crats of L.0H to #1RCS on 6-13-80

  • Reflects Boration that occurred due to #1RX tr'.o on 6-3-80
    • Reflects 6-3-80 #1RX trio Added 8 gallons of N;H between 6-26-80 and 6-28-80 to #2RHR (1) These invM e n c chemicals should nresent no mjor adverse environ-entn1 1-nnet.

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DESCRIPTION OF A2.L INSTANCES WHERE * '

THER!iAL DISC 11ARGE LIA11TS WERE EXCEEDED JUNE, 1980

. On June 3,1980, the temperature change at the station discharge exceeded 3 F per hour when Unit No. I reactor tripped on a loss of power to Vital Bus I-IV. This event was allowable in accordance with Technical Specification 4.14.

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UNIT 1

  • - FUEL HAiTDLING .

JUNE, 1983 e ,

None during this reporting period.

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UNIT 2 FUEL HMIDLING . . .

JUNE, 1980 None during this reporting period.

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PROCEDURE REVISIONS THAT CHANCED THE ' ~

OPERATING MODE DESCRIBED IN THE FSAR JUNE, 1980 None during this reporting period.

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DESCRIPTION OF PERICDIC TESTS WHICH WERE NOT . .

COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS JUNE, 1980 Unit 1 & 2 P.T. 22.5 Visual Inspection of Hydraulic Shock Suppressors was not completed on Unit 2 when scheduled (443-80). The test requires a visual inspection of 9 snubbers on Unit 2 which have not yet been converted to seal caterial compatible with the operating environ =ent every 31 days. The snubbers were inspected and found operable on May 6,1980, four days beyond the 25% grace period permitted by Technical Specifica-tion, 4.0 Unit 1 & 2 P.T. 24.4A Visual Inspections of Hydraulic Shock Suppressors was not completed on Unit 2 when '

scheduled (5-11-80). The test recuires a visual inspection of 9 snubbers on Unit 4

2 which have not yet been converted to seal material compatible with the operating environment every 31 days. The snubbers were inspected and found operable on May 21, 1980, three days beyond the 25% grace period permirrM by Technical Specifica-tion 4.0 Unit 1 & 2 P.T. 34 ,

Visual Inspections of Hydraulic Shock Suppressors was not completed on Unit 2 when scheduled (05-29-80) . The test requires a visual inspection of 9 snubbers on Unit 2 which have not yet been converted to seal material compatible with the operating environment every 31 days. The snubbers were inspected and found operable on June 6,1980, four days beyond 25% grace period permitted by Technical Specification 4.0.

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INSERVICE It!SPECTION . .

JUNE, 1980 Visual inspections on the Unit 1 & 2 hangar modifications and installation are in progress.

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REPORTABLE OCCITRRDICES PERTAINING TO ' *

  • ANY OUTAGE OR POk'ER REDUCTIONS JUNE, 1980 None during this reporting period.

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9 Maintenance of Safety Related Systems During Outage or Reduc'ed Power Periods f UNIT #1 Mechanical Maintenance

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- 25-1;o maintenance was perfomed on safety related systems during octages or reduced power periods.

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. . - :6-Maintenance of Safety Related Systems During Outage or Rcduced Power Periods j UNIT #2 Mechanical Maintenance

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s DEIT NECH 1 JUL 80

  • 10s59 AM PACE 1 ,

CMIT2 1101/80 (MAINTSNAKE Di SAFETE kELATED SYSTEMS NRING OUTAGE OR SEPUCiv tvVER TER10DS) ,

U NR N TlWNTN *i RETSihvPT STS Ctwr NAkKNO SWIMARY WkrLRF 06/02/a0 St INSTR HCV 2936 OIArNRAM I611' TUNE RErtACE hEGULATOR 2 00%181439 10%

06/03/80 tV PUMi' 2.W o re 3 A OUTBOAkD CACAING LEAK 1NSTALMU TEtLON PACUM 2 00%180432 %9 06103180 EE DIESLL EE.lG.2 TAkE REQUlhl0 HEADING TOCK REQUIRED READEM S 2 005211600 29's 06/0%l80 Si VALVE hve28%5A DEFICIEK T NNCH LIST RLMOVEU CM 2 0021314%6 1%5 06/0%l80 RC VALVE ISOLATION VALVES TIGHTLNED FACKING 2 00%16t%3% %G 06/0"**3 1A rir1M 2 lA.621 KEFAIR BROASN AIR LINE FEPAlRLD LINE 2 00%2%I020 Bil 06/0%)a0 AM NONITOR RM259/260 LOV FIDV AL.4hN INSTALL 10 klV liiMP 2 005050158 551 .

06/0%f80 RS VALVE 2 RS=%% AfrACK AND CLEM IIX VALVE AN PACUM 2 00515082: 3 06/04/80 RS VALVE 2.RS.45 REPACK AND CMM FlK VALVE AN . P K M NG 2 005t50828 3 06/0%/80 SS VALVE 2 RSo%6 hErKK ANV CLEM FIR VAll? AN. PKUNG 2 005150829 3 06/0%)a0 55 VALVE 2.RS %I REPACK ANU CMIN Fil VALVE AN. FACUNG 2 005U0830 3 hirACK AND CLEM ill VALVE AN. PACUNG 2 0051;?831 3 06/0%)a0 RS VAINE 2.hS.%8 '

06/0%/60 RS VAINE 2.RS.49 RbrACK AkV CLEM Fit VALVE AN. PKKlM 2 005150832 3 06/04/80 RS VALVE 2.hS.50 SEPACK AND CLEM Fit VALVE AN. FACKIM 2 005150833 3 06/0%f80 RS VALVE 2 SRS.52 RETACK AhD CLEM E!K VALVE AN. PKUM 2 005151128 3 1

06/0%)80 kS VALVE 2.RS.53 ELYKK Ahv CLEM F R VAINE AN. FACUM 2 005151129 3 06/0%l80 h3 VALVE 2.RS.5% bhrACK AND CLEM ill VALVE AN. FACUM 2 005151130 3 g 06/0%l80 RS VALVE 2.kS 55 hEFACK AND CLEM Fil VALVE AN. FACKIM 2 005151131 3 FUT FUKITALLEC GASKET + BOLTED Ur 2 0052%0923 %i N1 06/04980 RS NOV NOV NS 256A AllGN ELA%ES 06/0%la0 RS NOV MOV hS.2566 ALIGN FLAMES PUT FIEtiTALLIC LN AND NADE Ur FIBG 2 00524012% %5 I

06/0%l80 BS OTHER AIR LINE NOT N00KE0 Ur REPLACE 0 AIR LINE 2 006011%59 %0 2 VS.F.19 CHANCEV FILTERS 2 9082%01%5 66I3 9 06/0%/80 VS F1LTER FILTERS NEEDS TO DE CHAKED 2 00%152235 696

  • 06 55 / a 0 K VALVE RCVe25198 2 BOLTS MISSING BOLTS INSTALMO

NANAT LEAUM REPLACEV GASKET 2 005281* 16 061ubla0 RC TANK 2.RC.E 2 06/05/80 DA VALVE 3.DA.2008 TRIP VALVE HAS BIDCKME hEFillSHED LINE 2 00602151u 2 >

06/09/80 kN VALVE RCV.21%2 VALVE LLAKS BT REPLKEU VAIME INTERNAM 2 0050%2201 152 06/10/80 RS ItX 2*RS.E.18 INSTALL hvDBER GASKhT ENSTAT, LEU RUBBER CASKLTS 2 005291%01 286 .

06/10/80 RS HK 2.SRS.E.1C INSTALL hUUMR GASAET INSTAllhD MUDER GASAETS 2 005291402 216 1 06'112/00 KS PUMP 2.nS.C.28 DEFICithCT WNCH LIST CHECKl0 MAD OUT ON SHATT 2 005291331 33

'06)1%)a0 RS HR 2 55=E.10 INSTALL MBMR GASALT ENSTALMV GASAETS*1%MvhMED IT 2 005291%03 360 06/141R0 LA FirtNG L A LINE CLOAEM RbrARRfD AIR LINE 2 006130130 30 9 06/16980 FM PUMP RMS 25992GD REBUILT W MF MbulLT NMP 2 0060G1516 3 06916180 VS PUMP 1 VS.r.1C LACESSIVL PACUNU MAK ON EWP MPAlklU MAK 2 00G010110 20 06/19180 CN VALVE hCV.2186 FACKING LEAK REPACKED VALVE 2 0032I5201 %3 9 06919160 RC VALVE F.2=%25 ISOLATION VALVES !EAK RhrAIRED MAK 2 00%111530 6 ,

06918900 SE DIESEL EDG 2 CMM Oil BATH SIGHT GLASSES CMANED FILTERS 2 00G1%1300 21 2 C#.r.1C 114fr NAS SEAL MAK RETAIREP TUNr 2 00%'31001 8%0 1 06919160 C# TUMP 06/20180 A3 is GW#ACT fUSK S4467 MA4 00hMCT 1U8E S4 EAT MAK NONJfD# 2 003170609 552 06/20980 BD VALVE lE-M.202C 5007 VALVE MDS 5EPACWG MFACKW VALVE 2 00%101%33  %)

OGl20fa0 55 ririNG RS.256A AN HANGER ANUSTED HANGbR 2 00G181800 21 s 06920180 RS ViriNG hS 2568 AN NAMLR ANUSTED RANGlR 2 006111802 21 l lilCONNECTED LINE 2 00%2%0G35 305 06122180 CS ViriNG 2.CN.12 CISCONNECT hlCONhbCT 06/22180 CS VALVE 2 CS.12 LEAKS TUR0(IGN LArl%D DISC

  • REPACKED 2 005031%%2 298 06922180 Si ihr MTR 2 31=r.1A UNC00rLE NOTOR FR@l PbMr VNCOUFMO MOTOR 2 006130950 211 e 06/23/do CC VALVE hv.CC.2128 MAKS BT V1SASSENbMU*LArlWD VLV SEAT
  • DISC 2 005030959 153 s 06/2%IB0 NS VALVE 2.MS.3sg Ktg VORK 19R MAK TIGHThtSS V010 NR 200G180628 COVERS THis NH 2 0031t090% 0 . .

06/2%I80 CC TV*CC.209A AIN P1 LOT VIN MMUS CIAANIM MTLKE SEATS 2 005101540 648 -

  • VALVE Ii

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  • 10:59 AM TME 2 vs s UNIT 2. Il01/80 1 MAINTENANCE OF SAFETT RELATED SYSTEMS DURING OUTML OR RwUCLD IWER PERIODS)
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FETSthvPT STS CWP NARAN0

SUMMARY

WkrERF U NR NTWhTM

  • ' 06/2%l80 EE CONT'RESS 2 C@lrRESSOR EDES NOT FUNr REPLACEV HEAD GASAET '2 00G200t%6 5 06/25/80 Si VArv5 2 51=%8 VALVE HAS SCORED STEM EDLESHED SHAFT 2 00522193% 55 06/25100 NS VALVE 2 NS.81 LAP JM SEAT LArrio VALVE DIS
  • SEAT 2 006180800 181 2 006180801
  • 06/25/80 NS VALVE 2.MS 120 , LAP JN SEAT LAPWD/MMRINE DISC
  • SEAT tot 06/25160 NS VALVE 2.NS.158 LAr IN SEAT LArWD+MKHENt; DISC + SEAT 2 006180802 tot GGl25/80 MS VALVE 2.NS.318 LAP 1NSt;AT SEAT
  • DISC VAS LAPWD 2 006180808 111
  • 06/25/B0 N VALVE 2.W*238 AlrAIR NANW HEEL AND STEM REPLACE 0 GASKET 2 006181100 %G 9 06/25/80 CH VALVE 2=CN.191 GRINNEL VALVE LLAKS CmrLLTw 2 006230%50 33 06/25/80 CH VALVE 2-Ch 189 ChlNNEL VALVE LEAKS CONrLETEU 2 006230451 33

^* 06/25/80 RS hl 2-liS=l.1 A BOLT Nh wS TIGHTEN T1GNTEN FOLT 2 00G2%18%8 1  %

06/25180 SW PiriNG 2.SW.61 BOLT NISSING REPLACEO DOLT 2 0062%18%9 1 06/25/a0 SW VALVE 2 SW 68 STEM DENT STRAIGHTEN w STEM 2 0062%1852 1 f 0G/25100 CH NCY NOV.SE.2210A PACKING MARS ANUST PACAlhG 2 912051%05 5 )

OG/2Gino SI Firing 2.S1 32 U DCLT fikOKEN CONrMTEQ 2 003230502 2160 06/26/80 CH VALVE ECV.2113A PKKING LEAK AT VATNE ANUSTl0 PACKING 2 004120609 2 C 06/1G160 Si VAE 2.SI.112 TACKING l).4K C&ttlETED REPACKED VALVE 2 00%150%Q3 20 9 OG/26fA0 St VALVE 2.SI.111 PACKING LEAR CottrMTLD RErACAED VALVE 2 00%150%0% 21 06/26190 Si VALVE 2.S1 101 FACKING MAN REMOVLD CL PACKING

  • REPLACED W1TH NDI 2 004150%05 %1 t' OGl2Gl60 Si VALVE 2.S1 121 PAChihG LEAK RETACKw VALVE 2 004150%06 %1 9 1 EkrACkED VALVE 2 004150%01 00 0G/26/80 SL VALVAE 2.S1 116 P.4ChlWG LEAK %1 I

06/16180 RS ECMP  ?.RS.P.1 A VISCONhl.CT EUNr COUrLING REINSTALMD EUNP 2 00%181315 1656

( 0G/26160 RS FUNr 2.?~~r.18 DISCOhMECT IvNP COUPLING RE;lRP4 LIED EvMr 2 004181316 165G 9 06/26/20 SW VALVE MOV..d=205A. MAKS THROUGH ANUEfED SEATS TEST SAT AT %5 PSI SAT 2 00G100900 384 0G/26/80 MS VALVE 2 MS.311 LAP IN SF;AT AEL ENSTLCTION WERt; SAT 1STACTORT 2 006180809 192 I' 06/26190 CH Pl>Mr 1.CH.r 20 WILL NOT CLVEL0r HEAD REINSTALLED EvHP IN SYSTEM 2 006192200 161 9 3G/26/d0 Bk VALVE HCVeBR 106A hEPA1R ELANGE REV FLANGE GASklT+ PACK 1NG 2 006211208 50 0G/26/80 LA VALVL MOUNT SCLEN010 VALVES INSTALL VALVE ON HANGEES 2 00G2G0835 4 C 06/26/00 CH VALVE 2 CH.68 REPLACE DEATHRAGM KEPLACED UONNET MSENBLET 2 902161136 2%0 0 0G/29190 Si VA!NE 2.SL.86 FACRING LEAK REPACA1;D VALVE 2 004150%01 5 06/21/80 St VAINE 2 51 13% FACKING MAK hETACKLO VAlNE 3 004150409 58

'C 06/21180 hH PUNP 2*RH=P.18 lEAh!NG GASALT C@trLETED 3 0062G1830 1 >

06/29/80 LE VALVE 2.EC.12 AIR LEAK PACK 1MG TIGHTEN PACK 1NG NUT 2 005191%5G 48 OGl30180 SS VALVE TV SS 206A SOMN 010 CONSTAMTLT SELEn* J" V010 C0FtrLETED BT ELEC 3 006221310 0 t OGl30180 SS VALVE TV SS.201A S0lEN010 CONSTANTLT Bases Alk V010 C0FtrLLTED BT ELEC 2 006221311 0 }

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Maintenance of Safety Related Systems During Outage or Reduced Power Periods

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Electrical Maintenance i

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1 Jul, 80

  • 10 t 59 AM PACE 3 DEPT = &MC -

O UNIT 2= Il01/80 (NAINTt;MANCE OF SAFETY RELATED SYSTEMS 14/h1NG OUTAGE OR REDUCED It'WER TER10DS) hhTShhvDT SYS CMP MAkkMO

SUMMARY

WkrEhF U MR NTWNTM i 06/02/80 SS VAINE TVeSS.203 EMSTAl1, LIMIT SW11CHES MOVw LIMIT SW11CHt;S 2 002211%00 113%

06/02}a0 CH HT CAT 23DrNL8 RLTLK E HEAT TATE HEAT TAlt GOOD 2 00313U41% 49 0G/02/80 CH HT CkT23rNL9 REPLACE HEAT TATE HEAT TATE GOOD 2 001130n15 %9 O C6/02140 Si HT TWLt1CATL A UNEAKLN TNirS REPLKhD HEAT TAFE 2 0050I1%51 56 06/02/80 Si HT TRL10C CLA DRt:4AER TNirS HEAT TATE GOOD 2 0050It te 58 49 0G/02/00 Si lit TML11CG% CMAR ED ALAhM CMAht:0 In AI.Ahlt 2 0052405%2 19 f 06/02/80 Si itT TNL11CC1 CMAR ED ALAhM CLRCUIT CRt1UNVw 2 0052405%3 89 06/02/90 Si HT TNLt0CET1 CMAR ID ALAhM CMARED ED TLMr ALAhN 2 0052405%% 19 CMAhw (D ALARM 2 0052 %D5's 5 89 06/02/80 SE NT FML10CC5 CMAR ID ALARM 2 005240546 19 C 06/021a0 S1 HT TNL10C Q % CLEAR ED ALARM (MAhED ID ALAhN 06/02/80 DA VAE TV DA.2000 MPAIR LIGHTS ON VALVE ANUSTED 33 SWITCHES 2 0052%t015 31 06/02/00 IV MOV NOV-tWe2510 NOV iS SuvT UhEARER 1S orEN ANUSTw W11Ct; 2 005281601 18 4 06/02/90 VS MOV MOV.VS.200A NOV INS C @ ru Tw TNS ON MOV VS 200A 2 901251425 10351 OG/02/80 VS NOV NOV.VS.200C MOV INS C@trMTED INS ON NOV VS 200C 2 901251%29 103%9 06/0%)80 VS MOV NOVeVS.2000 NOTOR END Bhl,L CRACKw bhrLACED EhD Bt;LL SPARE TLSTw SAT 2 005152309  %%

9

$ 06/0%I80 IV MOV NOVoIV 251F MuV INS CWirMTw AS LER ADOVE PROCEltlRES 2 90125t%11 11521 06/05/80 53 ENSTR 2.RS.AM.1A CALibhA1E AMNhTER CmruTE 2 004241520 t l 06/05/80 RS CAllHhATE ApfMETER C att u TE 2 005131532 1 f 06/0l/80 CH INSTR HT 2 RS.AMe1D FML10*11CkTl MTAIR OR REPLACE hErLKED MAT TATE 2 005151500 115 N9 06/01/80 CH HT TML8CRT6A Ckt DKR FO K G GA TRirr1NG OUT REPLACED REAT TA E*TIIERNOSTAT 2 005181513 122 g 0G/09/80 Erb BREAGR 2%H2 EM PNEAU;N COMrs.ETE 2 004111%30 62%

i 06/09/80 1;ri, Bht;AKER 24H% !N DhEAAER Catru TED IMS 2 00%111%32 586 06/09/80 EFL Sht;AAER 2%H5 IN Unt.AA!;R CafrMTE 2 00411193% 552 0G/09/80 trL BREAKER 2%HI TM BREAKER CONrMTE 2 00%111435 552 N 0G/09/80 SI Mov MOV*2862A CUECK LIMIT W11 CMS ANUSTw LIMIT Swi1CHES 2 005150219 45G 9 06/09/80 IA Ch1ER AIR DhlER COMPRESS DOES RUM MPAIRED FAN 2 00G0I0820 1 INSTALI,1,lMIT SWITCH C@trM1E 2 0031Il349 138%

06/10/80 TH OTHER 2 00%231001 1109 9 f 06/10/80 NE OTHER REPLACE WESTINGHOUSE BFD MLATS C&lrMTED TESIGN CIIANGE 06/10}B0 BC  ; PVE HCV*255fC TEST 1NG HCVe255lC VM1Flw OIERATIONS 2 0052909%8 25 06/10100 hC *:ALVE HCVe255IA TESTING IICV 2t$1A VERIFlw OlERATIOKS 3 005290949 25 C 06/10/80 RC VALVE ICf.25GGC 1ESTING HCV '6C VERIFlw OCERATIONS 2 005301102 25 0 0G/10/40 DD VALVE 11.BD.2000 WILL NOT Sk DSK ANUSTw LIMITS 3 006050820 33 06/10/80 SS VALVE SY SS 2000 ANDICATLS OPEN A!,1,THE TIME ANUSTw L1MITS 2 006060)$$ 56

( 06/10/80 CH HT CkT1ArNL10 MPLACE DAMKb liEAT TRKE hlrLACEO liAD MAT Tart C1hCULT SAT 2 0060G1001 81 o NOV IMS COMPLETt;D AS IER EMrer.Nove%5 AND 19 2 901251501 IIG 0G/10180 CH MOV LCV.CH.21150 2 005051%00 2 06/11/80 RS INSTR RTD.RS.256A MENSTALI, FTD TIGHTEN LOR CIDSER CLEANhD PASTS 06/11/90 TH AI. MOVE ELACTOR CAVITY UNDEWATw LLC bEMOVw*MPLACw LICHTS 2 005230954  %%0 o

( OTHER M SIGN CHANGE COfl u TE 2 00524t829 88 06/16180 Si 1NSTR IMrukEhT D/C 89 S22 06ft6}40 K ANSTR IMruMENT DlC 80 535 Ut; SIGN CHAMt. CmrLLTE 2 0052%1430 15 06/16/80 SI INSTR iMruMENT DlC 80.S35 DFSle:N CHANGE Carru TE 2 0052%1831 85 ,

( INSTALuv SCRt.LN 2 005291413 16%

06/16/80 CS srMr MTR 2 CS.retA REPLACE CR AEPAIR NOTOR RhrLACK HEAT TAPE 2 00G061002 121 06/16/a0 Cet NT CAT 5ArNL10 hkrLACE BAD liEAT TATE 0G/16/B0 CH HT CKTSBrNL11 MPLACE 01,0 TRACT; WITH Nt.W REFLACE HAAT TATE 2 006100I51 121 g

06/16180 CH IIT C C5BrNL10 hErlACE OLD TRACE WITH NLW 5krLACE HEAT TATE 2 006100858 123 VALVE TMhMALS OUT WNEN OIENING COFtrMTE 2 006122206 8%

06/16980 CH MOV Move 21150 2 004181220 189 0G/11/80 CW JNSTR THhRM NO 1 SHOW3 NO M ADING NO PROULFit IOUND t

THERMOCOUTLE 15 OM;M MPLACE CMCAw T/C OK NO THODMM 2 006111%16 3's *

. 06/1tla0 CC LMSTk T/C.CC 225

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C' RETSLRVPT STS CWP NARANO SUMMART WKNRF U NR NTivhTN f 06/11/80 CH Nr NTR 2*CHere1C AUX OIL INr JUNCTION B01 SECUAE;0 CONEWIT 2 006122220 1t 06/11/80 LE BATT 2B2 MWATIVE GROUNO LIGHT OUT LIGHT 011 RATE 2 0061515%I 9 06/11/00 CH P171% 2.CHe3%2*152 CHECK HEAT TRACING HEAT TAPE SAT 2 006161830 2%

litr NTR Th0CEDURE StorNU JOU VORAEU NR S200 2 908211305 1205 C. 06/11/60 RH 2enn.r=10 01SC0hntrT NOTOR AND RECONNLCT 2 00523162G 22 06/18180 it OTHER Ae3 FEPLACE CONNECTOR hEPLACl2 CONNECNR 06/18/s0 SI VALVE 1YeS1 2010 VALVE WILL NOT STAT OWN ANUSTED SWITCH 2 00616115% 22 f 06/19180 RH PNr I*TR 2*RHr.1B KLMVE UPNR THRUST DE ARING NOT2R RF.TUkhED TO SFhYICE 2 003051815 2%89 '

06/20/00 CS 1NSTR L% 200A StrAIR OR hAFLACE 12iElo 3 11YNES INSTAluD KtW SW11CHLS 2 906251011 1569 06/23/80 RS TNr NTR 2.hS.r.1A DISC 0kNLCT IDR NhCHAN!CS NOTOK O NRATIONS NOMAL 2 0050513%3 111%

NOTOR ONRATIONS N0hMAL 2 0050513%% 11 A 6 '

06/23/00 RS TNr NTR 2eKS.P.18 DISCOMklCT EDR NECHANICS OG123?a0 RS INSTR LS.RS.200C CALIBRATE AND w 0r CHECE ANUSTED LLYEL SVITCH 2 005151205 80 ANUSTED LIMITS 2 006202100 69 06/23/00 RS N0Y NoveRS.2568 CHECK LIMITS 53

  • 0 06/23180 CH NOV NOVe22898 NOTOR CONTINOUSLT RUNNING CWrLETED AS NR EMreCeNOVe18 2 006210000 OGl23/80 CH NOV NOV CH.228IA NOV TNS CWrthTED AS NR F.NrereNOVe%5 2 901251%%9 56 06/23180 CH NOV NOVeCH.2281C Nov FNS CmrLETED AS PER threreNOVe%5 2 901251%51 %2 N. OG/2%)80 St VALVE NOVe286IB VALVE WILI NOT WL12 CLOSE CWrM1ED AS NR LNreceNOVe63 2 006221505 29 '

OG/2%)a0 RS NOV NOV.RSe2569 IErf0m LMrer.NOVe%5 DLVIATION CWPLATE 10 11 11 2 020159600 0 1 05/25180 RS 1NSTR LS.RS.201A CMAN ANU CAL LEVEL Swi1CH ChlChED 2 005151132 125 y'

$ LEVEL SWITCH CHECKED 2 005151202 125 v 06/25180 RS INSTR LS.RS 2018 CMAN AND CAllBRATE 2 006230225 6 06/25180 CH 1KSTR D UNI'lN S19reSThkT SVITCil TES1ED SAT g WILL NOT CTC M CWrLLTED AS PLR ENreCeNNe63 2 006231300 28 0G125180 SV NOV NOV Swe20$D *

[ i 0G/25100 SV NOV NoveSVe205C WILL NOT CICM C W FLETED AS PER LMreCeNOVe63 2 006231301 28 558'e n Peri NTAL ,

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

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No maintenance was performed on safety related systens during outages or reduced power periods.

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  • 10:59 AM VMk 5

, . m UNIT 2= Ilot}80 (MAINTENANCE OF SAFhTT hfLATED STSTLMS Lt/N!% CUTME OK Sllt/Civ IWER EERIOPS)

. s ALTSEhVVT STS COM? NARANO SUMMAkT VKlERF U NR NTIVNTN 06fto2100 kN NONINR RiehMS=2G2 10N CHAN0lk Fall w LRCtEDED TbES3]ht LIMITS 2 0052G2113 146 GG101/80 N1 SOUNCL N.31 AErLKE SOUhf1C AANCE PETLCTOR hlrLACt;D PithCTOh 2 005201101 103 0G/04/80 llc VALVL LT 2.%9% REPLACED LP CRAIN VALVE CMAhw VAIME ANU PRl:SSIRE CNLCK 2 003300815 G

  • 06/0%I80 BC OTitER TE-2453 hTV Tt; ?%53 1S BRCAEK REPLACw hirrM ANU ATO 2 005161500 359  %

06/0%l80 CC 1NSTR IT.CCoadlB FASTEN TRANSNET1tR 19 ENSTRUNF;NT RhC FAURICATEU DRACKET 2 005311050 5 OGl0%f80 K VALVE XV*2%55A KESTKOKE VALVE VAINE CHFCkED OUT SAT 2 006021%32 23

  • OG/0%f90 RC VALVE ECV-2%558 hESTh0kE VALVE VALE CHECALP CUT SAT 2 006021433 23  %

06/0%l80 FC VALVE KVe2%56 L1FTS hhllEF VALVE RESLT OUTIVT OF RIGH PRLSSIRE: HEC. 2 00G021%35 25 06/0%I40 1A INSTR IWM IN PLASTIC AIR LINE REPLACE 0 AIR LINE 2 00G0%00$$  %

  • OG109180 CS ENSTR Lt.CS*200A hWST DVER FLOV V010 PER EMINLt; RING 2 005211000 0  %

0G/09180 CS INSTR LleCS=2008 hVST CVERFLOV V010 ft;R ENGENLERING 2 005291001 0 OG/09/80 CS INSTR Lt.CS 200C FHST CVERFLOW VOID TER LMINEERING 2 0052I1001 0

  • OGl09/80 CS 1RSTR Lt.CS.2000 kWST OVERFIAW V010 Pt;R i MENEERING 2 00521100% 0  %

0G/09/80 'S inSR IToCS 201A VALVE MISSING INSTALMD C00SE NECA ISOLATION VALVE 2 005291%20 81 06/11/80 C1 INSTR Fl.CCe21GC liEPLACE MISSING CEE ON CC TO ACP DNSTAllLU CALIBRATO CME 2 0060%0900 2%

  • 06/13180 IN NONINR AM 259/2GO w FLOV AND FILTER FAULT STHAIGHTlhw PATER 2 005050801 2210 1 06/16180 CC INSTk INSTALL PhESS CAUGE INSTAlif0 GME AhU VALVE 2 00110101% IS g RLVI;L ENDICATOR CLEAhlD*RlrLACED FLU 10 2 005300I51 53 0G/19180 KK INSTR LleEE.1000

( 06/20180 CC INSTR T1.CCe2%58 T1.CCe2%50 llROKlN RirLACM TLMPERATURE INDICAMR SThokw VALVE CHECK OUT SAT 2 0041608c es 2 0050%2200 12G3 115

$1 0G/2?/60 RH VALVE HCVe21%2 CHECN STROKE OR VALVE I

06/2)}e0 CN VALVE KVe2122 VALVE WILL NGT OEthATE RlrLACEO PLUG OR1FICE ASST 2 00G22l500 18 t 06/23180 RC INSTR LT*2.%GO VENT VAINE DROKEN liEPLAClO VENT VALVE 2 006230900 9 1 06/25/B0 SS VALVE TVeSSe206A. SOV AIR LINES CONNLCTED Ur WRONG WROM SOV INSTALMD 2 0061110%% 30 06/25/80 SS VALVE TveSSe20%A SOV AIR LINES WRONG SOV 1NSTAllED 2 00G1110%$ 30 4 06/25180 SS VALVE TveS$*202A. SOV.SS.202A 1S NOT INSTL BACANARDS VRONG SOV LMSTALLEO 2 00G1110%G 30 g OG/25180 SS VAINE TV SSe201A 2Ve?.*- 3LA 1NSTL SACKWARD WRONO SOV INSTALLE0 2 00G1110%I 30 06/25/80 SS VAINE TV.SS=200A STillNG HOT CONRKTED CORELCTLE 171BlNG C0KhECT WROM S0Y 2 006191200 46 i eeeeee i UEIT NTAL %I10 g- a g 6

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, HEALTH PHYSICS JUNE, 1980

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l 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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PROCEDUPI DEVIATIONS REVIEWED BT STATION NUCLEAR , .

. , , , SAFETY AND OPERATIEG CO CIITTEE AFTER TIME LIMITS SPECIFIED IN TECICIICAL SPECIFICATIONS JUNE, 1980 NUMBER UNIT TITLE DEVIATION OPl.1 2 Unit Startup Operation Step 5.7-HCV 22003 shut.

(Solid Plant Operation) Step 5.11-MOV's not operable.

The above procedure was deviated May 17, 1980 and reviewed by the Station Nuclear Safety and Operating Co:nittee June 11, 1980.

PT 2.13 1 Charging Flow Steps 5.4.1, 5.8.7 thrt.;agh 5.8.6 (F-1-122), and 5.1.1-NA Omit all data perti-nent to anything other than trans-mitter calibration.

The above procedure was deviated June 5,1980 and reviewed by the Station Nuclear Safety and Operating Connittee June 20, 1980.

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