ML18139A238

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Monthly Operating Repts for Apr 1980
ML18139A238
Person / Time
Site: Surry  
Issue date: 05/07/1980
From: Costello O
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18139A237 List:
References
NUDOCS 8005190327
Download: ML18139A238 (46)
v • d • e


Text

. "

ti VIRGINIA ELECTRIC AND POWER COMPAl\\TY SURRY POWER STATION MONTHLY OPEP~~TING REPORT.

REPORT NO.

80-04

APRIL, 1980 APPROVED:

-i-cm:TENTS Section Operating Data Report - Unit ill Operating Data Report - Unit l!2 Unit Shutdowns and Power Reductions - Unit /fl Unit ShutdO'wns and Power Reductions - Unit f.!2 Load Reductions Due to Environmental Restrictions Unit tfl Load Reductions Due to Environmental Restrictions Unit /12 Avera~e Daily Unit Power Level - Unit #1 Average Daily Unit Power Level Unit 112 Sur:imary of Operating Experience Araendments to Facility License or Technical Specifications Facility ChanBeS Requiring NRC Approval Facility Changes That Did Not Require NRC Approval

)

Tests and Experiments Requiring HRC Approval Tests and ExperimentE: That Did Not Require NRC Approval Other Changes, Tests and Experiments Chemistry Report Description of All Instances Where Thermal Discharge _Limits Were Exceeded Fuel Handling Procedure Revisions That Changed the Operating Mode Described In *

  • The FSAR Description of Periodic Tests Which Were Not Completed "h'ithin The Time Limits Specified In Technical Specifications Inservice Inspection Reportable Occurrences Pertaining to Any Outage or Power Reductions*

Maintenance of Safety Related Systems During Outage or Reduced Power*

Periods - Unit 01 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Redticed Power Periods - Unit 1!2 - Hechanical Maintenance Page 1

2 3

4 5

.6 7

8 9

11 12 12 13 13 14 15 16 17 20 21 22 24 25 31

  • I

-ii-

  • Section H2intenance of Safety Related Systems Durin6 Outage or Reduced Power Periods -

~nit fl -

Electrical Maintenance Haintenance of Safety Related Systems During Outage or Reduced Pm,*er Periods -

Unit 112 - Electrical Maintenance Uaintenance of Safety Related Systems During Outage or Reduced Power Periods -

Unit l.'l -

Instrument Maintenance

!1aintenance of Safety Related Systems During Outage or Reduced Po...,.er Periods -

Unit /,!2 -

Instrument Maintenance.

Health Physics Summary Procedure Deviations reviewed by Station Nuclear Safet:y and Operating Committee after Time Limits Specified in T.S.

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Date 80-6 4-1-80 F: Forced S: Sd1ed11led

{'l/77)

UNIT SllUTIJOWNS AND POWER REDUCTIONS REPORT MONTI! APrrIL 1980 F

719 D

1 Reason:

A-Equipmeiit Failure {Expl:1in)

H-Maintcnancc or Test C-Rcfueling D-Rcgulal ory Rest rictlon Licensee Even!

Report tt 80-018 E-Opcrntor Training & License Ext1.mi11:1llon f' *Admlnisl rat ivc G-Opcrational Error (Expl;1in)

II-Other (l~'qi!uin) 3 Method:

I *Manual 2-M:mual Scram.

  • 3-Aul umal ic Scrn m.

4*01her (Explain)

DOCKET NO.

50-280 UNIT NAME DATE COMPLETED BY TELEPllONE Surry Unit 1

~

J, 1980 O. J. Costello (80L1) ]57-3184 Cause & Con eel ivc Action lo Prcvcnl Rcc11nc11c:e Continuation of shutdown for pjping restraint modification nncl turbine rotor inspection which began 2-19-80.

4 Exhibit G

  • Instruct ions for Preparation of Data Ei1try Sheets for Lh:enscc
  • Event Rcpmt (LEIO File (NllRECi*

0161) f-xhibit I* S:.1111c Suurc:c

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Date 80-1~

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UNIT SlllJll>OWNS AND POWER REDUCTIONS REPORT MONTll APRT.L 1980 s

719 f) 1 Reason:

A*Et1uipmenl Pallurc (Explain) 11-Maintcnancc of Test

('*Refueling

  • D-Rcg11l11lory Res111ctiun Licensee Even I Report 1t E*Opcrator Trnini11g & License Exa111i11alion F *Ar.lministrn I ivc G-Operntional Error (E.wlaln)

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DOCKET NO.

UNIT NAME DATE COMPLETED 11'1 TELEPllONE

'.i0<~8J Surry Unit 2

_l11.Y.._l_._l.2l2Q_

O. J. Cos teJ.J.o (80L1) 35 7-3J.8L1 Cause & Corrective Acti1111 to Prevent Rrcurrenrc Continuation of shutdown for refuel-ing & stenm generator replacement, which begnn on 2-L~-79.

\\Vork still underway on piping restraint modifi-cations required prior to unit recovery.

4 Exhibit G

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Exhibit I *Sarne Sour~e

s LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIOl-!S UNIT NO.

l HONTH:

APRIL, 1980 I

I I

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LOAD REDUCTIONS DU~ TO EtNIR0~01ENTAL RESTRICTIO!~S UNIT NO. 2 HO!ffH : APRIL, 19 80 HOURS LOAD, HW REDUCTIONS.

~*fw HWH REASON None duri*g this reporting period.

MONTHLY TOTAL

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9 -

Sill'~fARY OF OPERATING EXPERIENCE APRIL, 1980 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 piping restraint modifications a~d turbine rotor inspection.

April 26 -

A dilution from 3217 PPM boron to 3066 boron occurred without containment integrity when gravity flow occurred from the refueling*

water storage tank (RWST) to the primary system (RCS) during the performance of a periodic test (PT-18.10).

The RCS boron concentta-tio.n at all times was >2000 PPM boric, the minimum allowed for injection during all analysed accidents.

April 30 -

A spurious train A safety injection (SI) occurred at 0218.

The SI w-as caused by electricians working in the relay racks.

The SI would not reset due to a fault in the circuitry. At 0511 it was discovered that the RWST was gravity draining to the RCS via the boron injection tank (BIT).

The motor operated valves (MOV) isolating the RWST from the RCS via the BIT were open due to the locked in SI signal.

The MOV's were shut and de-energized to prevent their reopening and the RCS was sampled for boron concentration (CB).*.

Tne RCS had been diluted from 3090 PPM to 2926 PPM without contain-ment integrity.

At 0920 while attempting to verify tb.e position of SI accumulator discharge MOV's 1865 A & B the control room operator had power briefly restored to the valves.

During the

  • brief time power was restored to these valves, the Train "A" SI signal which had not been reset caused the valves to start opening.:

The amount the valves opened was limited due to the short time power was available to the motors.

With the RCS at atmospheric pressure and the 11A" & "B" SI accumulator pressurized with nitrogen, there was a rapid influx of borated water from the SI accilmulators into the RCS.

Due to the fact the RCS was partially drained for maintenance and an air volume was present in the system no over pressure condition existed in the RCS.

The over pressure mitigation system was fully operational and no actuation of this system occurred.

At 1007 while attempting to close the "A" SI accumulator MOV,. *an Electrician under authority of the Shift Supervisor installed a jumper in the MOV power supply breaker and eneq;ized the breaker.

The SI signal again caused the valve to open causing another partial discharge into the RCS.

Again, the vented condition resulted in no over pressure condition and the valve was immediately closed elec-trically, the breaker de-energized and jumper removed.

At 1320 the problem with the SI circuitry was identified as a faulty relay and repaired.

The SI signal was reset.

The RCS boron concentration injected was at all times >2000 PPM, the minimum allowed for inject-ion during all analysed accidents. This reporting period ends with

t

e.

SUMMARY

OF OPERA.TING EXPERIEKCE APRIL, 1980 UNIT 1 (continued)

April 30 -

the unit at cold shutdown with piping restraint modifications and turbine repairs in progress.

UNIT 2.

April 1 This reporting period begins with the unit.at cold shutdown, all fuel removed from the reactor and piping restraints modification in progress.

April 15 -

At 1840 the containment spray (C.S.) drawdown test of the refueling water sto.rage tank (R.W.S.T.} and the chemical addition tank (C.A.T.) began.

The test was concluded at 2046.

April 19 -

At 1041 the fuel reload connnenced.

April 23 -

At 0457 the Unit core fuel reload was cow.?leted.

April 25 -

Reactor upper internals were reinstallea at 0912. Full length control rod latching was completed at 2033.

April 30 -

This reporting period ends with the Unit at cold shutdown.

  • A N1Ei./DHEH.i:

TO FACILITY LICENSE OR TECHNICW SPECIFICATIO.HS APRIL, 1980 The Nuclear Regulatory Cornm.ission issued, on Narch 21, 1980, Amendment Nos.

58 and 57 to the Operating License for the Surry Power Station Unit Nos. 1 and 2, respectively.

The amendment results from the NRC Staff's review of our request to revise the provisions of the Steam Generator Repair Program.

Of significance, License Cond.i tion 3.G. (2) (b) has been changed to read as follows:

(b)

Temporary containment and ventilation systems shall be installed and operated for all cutting and grinding operations involving components with removable radioactive contamination greater than 2200 DPM per 100 cm2 except when the Health Physics Coordinator for the Steam Generator Repair Program determines, based on an evaluation involving ALAR..~

considerations, that their use will increase overall occupational radiation exposure to workers involved in the repair activities.

The Nuclear Regulatory Commission issued, on March 26, 1980, an Order for Surry Power Station Unit No. 2.

The Order is issued to lift the suspension of facility operation required by the Order to Show Cause dated Harch 26, 1980.

Of significance the Order requires the following:

1.

Effective this date the suspension of facility operation required by the Order to Show Cause of March 13, 1979 is lifted.

2.

All modifications to correct piping system overstress shall be completed prior to startup.

  • FACILITY Clv\\J.~GES REQUIRn,9 NRC APPROVAL APRIL, 1980 None during this reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL The following facility changes were implemented during the month of April:

Design Change Unit 1,2

1. DC-79-S55 Auxiliary Feedwater System Flow Indication Modification This change upgraded the auxiliary feedwater flow indication loop power supply from semi-vital to emergency buses to satisfy existing requirements.

This was done by replacing the present 3*1oop power supply to the instrumentation with 3 separate power supplies powered from the emergency. buses.

Summary of Safety Evaluation The auxiliary feedwater flow indication modification does not effect station operation nor does it alter the operation of safety related equipment.

2. DC-80-S35.

Diverse Isolation Signals to Containment Trip Valves As indicated in 1TUREG-0578, diverse isolation signals were stJp!)lied to non-essential containment trip valves by modifying the existing *control cables.

Summary of Safety Evaluation 1

The modification supplying diverse isolation signals to containment trip valves involves. the deletion of outputs from the CLS system and replacing them with Safety Injection Signal outputs.

This is the only change in the operation of the Engineered Safeguards System.

Station Operating and Testing Procedures should be updated to reflect this change.

This design change improves the containment isolation system and has no effect on the operation of other safety systems or safety related equipment.

TESTS AND EXP.t:RH1ENTS NRC APPROVAL APRIL, 1980 None during this reporting period.

TEST.Alm EXPERIMENTS THAT.

DID NOT REQUIRE NRG APPROVAL APRIL, 1980 ST-82 UNIT NO.

1 The Overtravel Test on Westinghouse BFD Relays was.conducted and reviewed on*

April 2, 1980.

This test, in response to IE Bulletin 79-25, was to determine the proper operability of the relays in order to assure the safe and efficient operation of the plant.

Upon completion of the testing, those relays found to be out of specification were removed from storage and marked so that they will not be used.

OTHER CHANGES, TESTS AND EXP ER

  • i{'fS APRIL, 1980 None during this reporting period.

SURRY POWER STATION CHL~ISTRY REPORT APRIL

, 19~

T

  • S
  • 6
  • 6
  • 3.* d

'I PRIHARY COOLANT UNIT NO. 1 UNIT NO.

ANALYSIS MAXIMUM MINIMUM AVERAGE YiAXIMUM MINIMUM Gross Radioact., µCi/ml 3.83 E-1 1.20 E-2 2.70 E-1 5.25 E-3 1.19 E-3 Suspended Solids, ppm 9.4 **

0.0 0.6 1.0 0.0 Gross Tritium, µCi/ml Iodine-131, µCi/ml

  • ):

1-131/I-133 i:

Hydrogen, cc/kg Lithium, ppm Boron-10, ppm +

630.53 400.82 503.21 430.42 402.19 Oxygen-16, ppm 2.2;**

0.4 1.4 SAT +

SAT+

Chloride, ppm 0.05 0.05 0.05 0.05 0.05 pH @ 25°C 5.52

4. 77 5.19 5.45 4.74

+ Boron-10 = Total Boron x 0.196 Phosphate Sulfate 50% NaOH 190 0

NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T. S

AVEE c\\

2.07 *-*-

0.2

......-.~

416. :.?~

SAT

--:-r-0.-*.y

' - - ~~

4.'-'S:

Remarks:

  • i' Local DIP sample
    • '< 0 7 Saturated on local DIP samples 4-(3, 4, 5)-80

~------""-------------------------~~

+ Oxygen considered to be saturated - local DIP sample of cavity

>'< Unit at cold shutdown (1)

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

  • DESCRIPTION OF ALL INSTANCES -RE THEPJ1AL DISCll<\\RGE LH!ITS W.t:RE EXC.t.EDED APRIL. 1980 None during this reporting period.

FUEL H...;.HDLIHG APRIL. 1980 One hundred c:.nd fifty-seven full assemblies (full core load) were moved from the spent fuel storc:.ge facility to Unit 2 reactor as per reloading procedure.

Each assembly contained its appropriate insert.

The part length control rods were not reinstalled in Unit 2 in accordance with D/C-S78-25.

FEEL HANDLING UNIT NO 1 18 --

APRIL, 1980 DATE NO. OF ANSI HO.

NEW OR SPE1~T FUEL

O::I?PED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVE I

I I

I I I I

None di ring this reporting peri< d.

I I

t I

I I

I I

~

I I

I I

I I

IBHT NO. 2 19

  • FUt.C HAl~DLING APRIL, 1980 DATE NO. OF ANSI NO.

- :t.SW OR SPENT FUEL

'-=:'.IPPE:D/1-~CEIVED ASSEMBLIES PER SHIPHENT INITIAL ENRICill1H-iT SHIPPING CASK ACTIVITY LEVE I

I I

I I

I None d llring this reportino-Perild.

I I

. ~~

\\

I I

I

.,~~

I f

t I

I I

. -- ----- _I_ __ -

PROCEDURE REVISIONS THAT C1D\\NG~THE OPERATING HODE DESCRIBED IN THE FSAR APRIL. 1980 None during this reporting period.

21 -

tl:scRIPTION OF PERIODIC TESTS i..1L~H WERE NOT CO~*!PLETED WITHIN THE TIHE LIHITS SPt.CIFIED Il~ TECHNICAL SPt:CIFICATIO:!-iS APRIL, 1980 PT-17.3 Containment Outside Recirculation Spray Pumps *-:as not completed on Urrit: No. l when scheduled (04-09-80).

The test requires a flow test of the pumps and valves to verify that they will respond properly.

The test was conducted satisfactorily on 04-19-80, three days beyond the 25% grace period allowed by Technical Specification 4.0.

22 -

rnsERVICE rnsPECTIOU APRIL. 1980 liNIT NO. 1 Liquid Penetrant Inspection was completed on all pressurizer Safe End Welds per Westinghouse recommendations.

No reportable indications were noted.

Magnetic Particle Inspection of the Low Pressure Turbine is completed.

All indications noted have been cleared.

The two Low Pressure Rotors are acceptable.

Visual inspection of the hanger modifications is in progress.

UNIT NO. 2 Eddy current inspection of the main condenser tubing is co~plete. The results of the partial inspection were satisfactory.

The Westinghouse portion of the Inservice Inspection Program per Technical Specifications ~s complete.

No reportable indications were noted.

I')

VF,f'l'=NVT 1 NAY 80

  • 1:*11 I'M l'Ar;g 8 UN1T1* fiiOilllO (MAlNTENANC/<,' OF SAfF,TY RET.ATIW SYS'J'F,MS D//RlNG OIJTAr.F. OR Rf<.'VIJCF.TJ POWER rE17JOTJS)

'l m:T sr.: RV /Jf SYS COMI' M/11?T!.NO

SUMMARY

lrl<f'E'RP

/}

Mil

'f0'1'/JJ.!N1'N 011/liil)Ali ilC SG f.,ifc,.g.. 1A T'!?Rf'O!IM EDDY Cl/Rllfi'NT F:DVY Clh?t?!'NT*SAT )lr;L RT£rAii?ESvSAT i

()()1;.!110115 12ll

    • 1 011IOR)OO Rr:

SG 1*ii'C.. E-.1C I'Ei/FOi!M EVVY Clfi/RBN'f E/JVY CURRENT"SAT ALL REl'/IIi1S~SA'f 1

0021110'16 1155 0*1/00100 17C SG 1"RC-f:-.1B Pf:1?f'01?N EDDY CllRRENJ'

/WVY CIJRi"IENT*S/17' ALL REI'AlRS"S/IT 1

U022110'1Y 1155 m:n rmw,

130

  • ")

9*1 f'

)

)

r...:i

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w

)

')

0)

-')

)

()

)

  • )

0

  • Q

.o

24 -

a.

"'4ifEPORTABLE OCCURREHCES PERTAINill'TO P.2IT OUTAGE OR POWER REDUCTIONS APRIL. 1980 None during this reporting period.

25 -

Maintenance of Safety Related Systems During Outage or Reduc'ed Power Periods UNIT f.!l Mechanical Maintenance

('

,... )

{'\\

I'")

m:rJ'~w:cu 1 MAY 00

  • l:"1 l'M J'/t(;f; "2

<1" l!Nl 'fin 5/0l)Oll (MMNTENANCF,' OF SAFl'."'fY 1?];[,A'fEIJ SYSTEMS DlliUNG OllTAGf: OR m:IJ/JCF.D rol-IER I'ERJOUS)

~

i<F.'fSF:fiV /IT SYS COMP NAliKIVO Sl/NMAflY Wkl'f:RF I/

/.Iii

'I'O'fWN'fM 011/10/00 CTI MOV MOV~1209/l RF:rACK RF.T'ACK.TW V Jlf,VE 1

UUIJU11 !i112 211

($>

CJ11/11J/8U C/I V Al.VE n;*v~110G l'ACKlNG U:AK.

t?F.l'ACK.!W VAT,VE 1

00110115%

211 011110100 Fl' Pil'lNG 1-fl'~P*2

/JlF:sr.;r,,101 N'I' u;AKB 178/'AIREV U~AK 1

lJOllOCi2330 10

{)11/10)90 w:

I'IJ,111' 1-liC*1/J Rli'ROTJ'f E I'll L /, f,J NF.

REl10//1'E f,lNf:S AS PF.R 111\\QllEST 1

OtJIHJ'llHi70

'/'I 011/10/90 v**

MOV Mov-vs~10011

!'ACK.ING T,F:AK.

i?!ll'ACY.IW VAl,VF.

1 0011onOHJA 11 IJll.111 /OO SI-I

.l NS'l'R 1-'1~."1-1-101/J 1/NAfJT,F. TO RF.AV PLOW RAT/\\

CU~AN/SlJ Slfil/'f Gf,ASS 1

l)IJll IJ'l 0-11 ').

12 011111100 fl/

OT/IP.fl LlMl'f SWlTl'/I 1'111 P JNS1'Al~r;fi.'{) DRACK.F.T FOR LlNl'f b1'11TC//

1 00110110010 ri 011/12/00 vs v A1.vr; MOV~vs~100A lNSTAT,[, Tr:STlNCI. fl.ANGF, 1NS1'AT;r. ~'fo:S'f f'T.ANGF.

1 oo:i:i11200 F1G

-~

011/12/00 Fl' lNSR FI~FP~100 JNSl'f:CT Oillf'JCF,' *FOR cu:A1?ANCR G/J.'il<f:'J' Sl/JIFACR REl'C.ACF:lJ 1

Oll'11012/.0 51 0 11/13/SU cc NT'LNG G"cc~;1s

/JC 99*S32C INS'l'Af.[, CONSTRAJNT CONl'Uf'1,'IJ 1

Oll211l133.11 10fl!l c

011/13/80 MS V A/,VF.

1nMS"31J1 iWSE/11' + RF.PAC I<

Rf,'Sr,'A1'f:/J AND RF,PAClilW VAC.VE 1

Ull7:r2llGlG 111 0

011}1J/Ht>

NS VAC.VE l~Ms.3113 r.r;s r:: AT

~ Rr:l'ACK flliSf,'A'l'F.lJ AND REl'ACK!W VAT.VE 1

00:.!22lHi20 111 u11/13IOU cc Pl PING 10-cc.9 DC Y9"S3:1A lNS'l'ADC. SllPI'ORT COMf.Lfl:TED 1

003101~111

'1"11 t!)

011 /13) I.Ill cc PlPlNG 6.cc.20 ix: 19,S32C INS'rALT, CONS'.l'RAJN'f CONl'LF.TElJ 1

003:.'013'.11 llfl 5 011l1J/OO f'C I'l Pl NG 1:7.*f'f'*l DC 19-<.'i32C 1NS1'ALL CONSTRAlNT CONl'L8"l'J::lJ 1

003201331 11Rc; 011/13/80

(;//

Pl PING 2.c11~23 TX 19*S32C lNSTAT,C. CONSTRAINT COM!'Lfl:Tli'TJ 1

003251303 216 lllt 011/13/80 CITJ Pl Pl NG 3*1/GCR*2 DC 99"S32C lNSTADL SI'171N(; //ANGER COMPU;n"/J 1

OOlllJ31"1Y 11111

~

011/13)00 BlJ Pl PING 3~WGCB*2 UC '19*S32C lNSTA[,L CONSTRAlN'l' COMPLE'l'ED 1

00110311118 11111 011/13)30 cc l'll'lNG 3.cc-20\\1 C'J/'l' I'Il'F. AT l!ANGER rn:;r.u lJNACCUTllBT.flJ ARl!ll ON l'Il'[I; 1

OOllO'l061!i 1110 011)111/80 VG V AT.V r, rv.vr,.. 109A tJOIJY '.l'O lWNrn'f U;;/1K ON IT 16.11 REN,ACIW BONNE'l' GASTiF.T 1

00110111!i~[j 1Ci3

"~

011/111/90 SI MOV MOV*Sl"1B6'1B

[IONNF:f OF VAT,VE LEAKING RErALRElJ C.!IAI<

1 911'.lo111n (i03 011)111/01)

SI HOV MOV-SI*HG'JA C!ONNF:'f OF VAT,VF. TP.AKfNG Rfi:P/Jl.RED T,EAK 1

911'.l511J7.0 (i03 0

011/15)00 MS

VALVF, 1*MS~to RF.SF.117' i RF.l'ACK m:SEA'i'l!:V ANV RF.I' AC KEV V A/,VE
1 00222lJ!ill3 23

~

011/15/80 MS VAT.VE 1*MS*3*10 iil!:SF.A'l' *I 17/i'I'ACK RF.l'Alilf\\'IJ VALVE 1

002270550

(,:J Ull/15/80 MS VAC.V F.

l"MS*3'l9 f/F;SEAT

~ REPACK REI'AlliED VALVE

i. U02:l20556 (il e

0 11/l!i/JJO NS VAT;VF.

1*MS*B'1 lili'SSAT

~ h'F,'PACK m:m:A'fll'V AND REPACKED VAT,VA' 1

00222or.111 n

~

011/15180 MS

.VllVF.

1-Ns~na Rli'SF.AT i REl'ACJ<.

RF..'Se.A'N;/J AND t?EPACK!W VAT,VE 1

002220G15 30 lJll) 1!i/80 MS VA[,Vr,'

1~MS*290 RF.SP.'A'f i 11F.l'ACJ<.

//!i'Sr:A'O:IJ AND RF;P/ICKE/J VALVE 1

0022/l)fill !i 30

~

011/15/All Cl/

f'Il'lNG 11"cu.11:>.

/JC ~9*S32C.INSTAT,f, S'I'RAP CO:ltf[,E'J'/','/J 1

OO:l:J111106 q

011/15/00 C:IJ P.ll'lNU 3*Cll-"Jll UC 119*S32C lNSTAL[, S'i'iiAP CUMl'iF:'l'F.IJ 1*

00321.1 110'/

9(i

e.

lJll/15/80.

r:11 PJPIN<i 3~Cll*09 1x: *v g.snc IN Sr AC.C. srmrr CCWP/,fo:~W/J 1

UU32111i!i0 gr, 011/15)00

.'ii l'lPfNG 2~s.r. 131

/JC '19*S32C 1NS1'/JC,L S1'RTJ'f CONJ'[,F;TEIJ 1

Oll321l115Y 9fi

~

011/lf,/80

/)[)

PJNNG 3*W<iC8*2

/JC V9-S32C lNS'/'A[,[, CONST!IAIN'f COMI'LF:'l'IW 1

001103111 rn 192

. 0 11/15/00.

/1/)

I'l l'.1 Nfi 3~WGCTJ"2 VC v9rS'J?<J INSTM,f, CON.'i'l'fllllNT COMl'f,/i'Tf:D 1

00110311119 1'12 (fl 011)15.JBO

[l/1 T'J f'lNG 3~1..acv-2

/Jr: '19"S3').C lNS'L'/JT,{, CON.'iTR/llN'f

  • COMl'f,P:'/'f<,'V 1

00110:111110 19?

IJll}lr./00 IJ!)

l'.l!'lNG 3-Wr.r;B-'J

/X:

J~f>32C 1N5T/Jl,l. CONS'./'RAlNT CUNl'/,E-0:/J 1

00110:11 11'.ll 1'1'.l Oil /1!i/OO TJ/)

T'l NNG

'J*Wr.C/J,'J IX]

119*.'132C INSTAC.L SWAY srR/11' r,*om*r,~:n*u 1

0011on11n 192 1)11/l!i/llll RS MOV f*tOV"RS~+!iSA u:AKF.IJ rw:,:11:;1 Vf.'f, y ON !~' 1c~;*

lNSIWC'l'IW VAJ;VF..'

1 00'111)J 105 gr;

~

tlll/15/80 HI v11r,vg

  • 1*flf"09 lNSN.'1.I' VAf.,Vf'.'

Rf:f'Al'/!liV VAl,v~;

1 0011102000 Y'l 011/t!l)!lO

[11' VAI,VE 1*DJ"27'1 IJWCll (J//l*:Cli VM,V/\\ <:wm;v lNiJ'J'Af,fW IJWl'H.

1 001111t2111 oi

(}.

011/l!i/OU Cl/

VAT,V1':

l*l,'/!*1110

{'[,//G-1 f.:T,801~ vorms;ri1~:AM OF v l.V

~rJUll'ff.,'N@ Tll17EADS 1

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?

011/15/AO

!JR

/'I/Ml' 1"/JR*P-W

/1.f,Jl;N AN/J l'UNN/o,Y,'T CO/lP/,lN C011l'U.'D l'llMT' 'l'O M01'011 1. 90!lll'll 3U2 5'1f>li 011/ln/BO S.I MOV MIJV*l8G'IC llOllY TO TIONNF.'l' /,F.AK REPAiiim Lll'AK 1

0031 ?.t5:10 no 0

011/16/60

,'Jl MOV MOV"l66'ID lJOIJY TO TJONNF.f U:AK.

ii'P:f'Alt7f:/J C.li'AK 1

00312:l5:ll no

~

. 011116160 M8 VA{.VF,.

l"HS.. 'I fiO{)Y TO llONNh'I' LF.t!K 1wr1i1 R l\\'IJ c.1;;r,x 1

0031 $0YJ9 ll 011}1f,/OO CV V..U,Vl\\

1-cv-2

!.T~A/l.S Tlli1U ON rr 1!i,11 LAl'l'F:D G1t/'f<.'

1 0011o:i1*1Ju 216 (J

oq!lf,/HO vr, vt.r.vr.:

1rVG.. r.

Rli:['[.A1;*w TllA!'/11IAN Rf.'F'l,ACIW V /Jl,Vg 1

0011u111sn 216 0

  • . ¢'.

I("'\\

.q.'

vn'T~m:r.11 1 MAY 80

~

1I111 /'M

/'AGE 3 UNIT1~ !i)Oi!BO

.iJ)

<MAINTENANCE (IF SAFl\\1'Y RF:r.ATEIJ SYSTl-:MS DURING O/JTAGF: 017 1Tfo.'IJ/ICI\\/} rornm PE1WJ/JS) c;.

Rl\\J'!JF.RV /J'f SYS CON!'

N/li1'KNO

SUMMARY

1/Kf'r-:iiF I/

Mil

'/'O'f'IJIJ N'IW

~

011)tr.J110

.'JI/

v,;r,v ft; 1-:~1"2i2 11 M,i\\' [,'J' F.'M Rr.:r1.ticti1 11 Ar.v t i

lJl)llll'llJ(jJ'I 211 t\\1ll C)11/161Bll RS VAT.VE MVV~17Sn1!i61l cif:AN v Ar;vri:

C/ffi:CKEJJ V/,V lNT/i'i"!NAiS 1

001110ono 11111 0

011,IH/00 NS PJ.f'lNG f'DANGF..' LEAK tlfi:PAlii'l*:/J LP.AK 1

00:11soJ3G 29 0 11)H)OO ii!'

VAC,VF.

hV1'"12 Lk A k.s 2' lliW 0 N F'l' 1 ti.

CLEANF.U V[,V INTERNA[,S 1

0011031'13!i V'J el) 011)1Y/8ll SI{

r/JMI' 1-sr{~r-1on F.XCliSSJVF. f,F.AKAGT!.'

REI'LACF./J PACKING 1

IHJl1090520

~:)

e 011/.HIOO VS fl [,Tll17 1~vs~FL"3B FILTER GA//Gf: IS Pr.:GGED l/IGll Rf.'ff.ACED VIii'l'Y PREF.l LTERS 1

IJUll1J01130 211

()11)1 '1180 51{

VALV~'

1"STr*1UG S'fEM DRVKF,N m:r r.r RTW v AL Vii 1

OtJll1~020U 33

~

u11/1VIOO f'W

VALVF, 1-fWtt2~

lf/Sf'ECT JN2'ERNALS ANIJ REl'AJR Rl\\'I'Ali?f:D VAC.VE 1

0011 lr>ll916 1/.

-9 011)HIBO vs flC.TER 1"VS"FL"3A Fl L'l'f.'R GAUGE lS PEGGF.'IJ lllGll RE.'f'[,AC~:D Vlil7'I I'RF.FJC,TERS 1

0011tliU8llO 211 011;t6/IJO MS VAL.VI.I 1-MS"3'J"l i!P.SF:AT

~ RF.I'AC}(

REI'LilCF:D VAliV E AS f'F:R REQIJEST 1

Otl21.2U!i1111 133 0

011116/ijO t7S l'llMP Rf.'ClRC S1'1i'AY SUMP Pl/MPS RP.I'/1li!F:JJ 1'1/Ml'S 1

Oll21'l1L1.B it 011,llBIBO f'(,'

l'l f'l NG 16*Ff'" 11.l DC 99.. s:nA 1NS2'ALL CONS'l't?AlNT COMl'LETW 1

003:1013{0

!iUll 011/Hl/OO cc l'lf'JNG 3,.CC*20'1

/JC Y9~832A lNSTAC.J; CONSTRAINT COMf'LF.TlW 1

0032512:.>1 5011 e

011,1101an CV VAf,VE rv.cv.1soA

/,f;AKS EXCT-:SSJ.VE ON ET 16.11 m:rAIRll'D J;EA}(

1 00110100110 1103 f) 011/10)80 Cl/

Pll'JNG 3.c11.v1

/!C V9*S32C REMUVll' ROD l/llNGER CVMl'UiTIW 1

110110111532 n

011110100

[)A VAt;VE TV*DA-100A LEAKS r.xr;T-,'SSLVF. ON IT 11;.11 Cl,P./INIW VALVE If/Tfi.'Rf/AT.S 1

001105tv O!i 1

tl>

011118}1!0 DA VALVE 2'V*DA* 1008

),EAKS F;xcr:ss1v1~ ON IT 15.11 c,'Lr:11NEU VAT,V g INTERN ADS 1

001105ivtHi 1

~

l)ll/10)80 Sf./

INS'fR F'l-b1r'.. 100A F'WAT JN /Jl'{,' AT017 IS 8RCJKF:N INS'l'llLLIW NP.Y lNIJICATOR 1

00110<0r;115 63 011/18180

~1{

lNS'rR.

fl~.'M*101A SCAL8 TO MF;ASURE f'LrJr{ MlBSING CT.EANIW + R1"<;1'11JRED SCALE 1

001109 06'1G 63 0

011110100 cu f'lf'.lN(;

3*Cllr.'19 VC \\f9qS32C lNSTA[,L CONS'l'RAINT CONl'J,F:'f/<:D 1

OOllOA111l.

V1

1) 011/18/80 cs V A[,VE 1~cs"211 NEF:VS TO lJE m:rAcl<F.:D FOR 1'T 1G.lj RE.'l'ACKEU VADVE 1

0011111111 11111 N

011Jt8J8D RS VAT,VF.'

1*R8* l'I Nf.'ll'/JB TO m: t?P.PACJ<EV FOR f'l.' 16.11 RE PAC /(f.'IJ V A/,V F.

1 0011111112 11111

())

e 01111 0/80 JA VAz;vg Alt? UN f.; TO 8 Al'CllM/I C.ATVR RF.PLAr;mJ VAMAGf.' r.INE AS REIJ/IESTED 1

00111111'1:1~

G3 011/18)80 2-Cll*Pn1A Nf:W VF.NT RlG ON PMP 1NS1'A&WD VllN'f RJG Cl/

l'/IMI' 1

OOllH1010 9

tJll/18)00 NS VAC.Vf 1*M8~2'13 VAt;Vf. :.tfRJl'T'F:IJ lNii'fM,LEIJ HANWIJEF.li 1

  • tllJl11Y20l'i 9

~

011)19/BU RC P/JMP 1*RC"P"1ll UNCOllPL}!: FO/'/ F.LEC7'17ICl'ANS RF.CO//PI,F; MOTOR '.l'O ruMP 1

Oll:JtJB1USr.

101)0

'II) 011119/80 CV VALVF:

7*v-cv.1!ioB DOJi.'S NO'f PASS FUW RF.l'llLRT\\D v 1ir.vF:~c11ANGEV GASKETS 1

tJIJ11112D10 21 011/10100 Cl/

f'lf'lf/G 3~1:11-t VC v*9*S3'lC J.VSTAMi CONSTl7AtNT CtiMl'f,i;."1'F,D 1

OOJ70tll'l8 r,r,,1 (ti 011 )7tJ/RIJ fl{

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HL<\\LTH PHY-~S APRIL, 1980 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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I 1-.'UHBER PT-16.3 43 -

?ROCEDURE I.1EVIATIO~rs REVIE'i-rt:D BY STATION NCCLEAR 5,.\\ :;"£TY *.\\lill OPERATING CWMITTEE AFTER TI~i.c. LL.HITS SP:SCEIED TN TI:.CHl'iLC.:U... SP:t.CI.t I CATIONS UNIT 2

APRIL, 1980 TITLE Containment Leakage Rate Test - Type "A" at 45 psig DEVIATION Step 5.2A - Add a second Operator or Engineer The above procedure was deviated on Harch 8, 1980 and reviewed by the Station Nuclear Safety and Operating Committee April 9, 1980.

PT-16.4 2

Containment Isolation Valve Leakage Steps 4.63.10, 4.63.5 and -

4.63.6 -

Change 40 psig to 45 psig The above procedure was deviated Harch 24, 1980 and reviewed by the Station Nuclear Safety and Operating Committee April 9, 1980.

PT-16.4 2

Containment Isolation Valve Leakage Steps 4.33.3.5, and 4.33.3.6 and 4.33.4 Change 40 psig to 45 psig The above procedure was deviated on Harch 24, 1980 and reviewed by the Station Nuclear Safety and Operating CoIDI!1ittee April 9, 1980.

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