ML18141A052

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Monthly Operating Repts for June 1983
ML18141A052
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/07/1983
From: Jones V
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18141A051 List:
References
NUDOCS 8307200197
Download: ML18141A052 (43)
v • d • e


Text

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e VIRGINIA ELECTRIC Af..'1) POWER COMPANY SUP.RY POWER STATION MONTHLY OPERATING REPORT REPORT NO.

83-06

i Sec:ion Operating Data Report - Unit #1 Operating Data Report - Unit #2 Unit Shutdowns and Power Reductions - Unit #1 Unit Shutdowns and Power Reductions - Unit #2 Load Reductions Due to Environmental Restrictions Load Reductions Due to Environmental Restrictions Average Daily Unit Power Level - Unit #1 Average Daily Unit Power Level - Unit #2 Summary of Operating Experience

- Unit /j 1

- Unit #2 Amendments to Facility License or Technical Specifications Facility Changes Requiring NRC Approval Facility Changes That Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments 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 Within the Time Limits Specified in Technical Specifications Reportable Occurences Pertaining to Any Outage or Power Reductions 2

3 4

5 6

7 8

9 12 13 14 16 16 17 18 19 20 22 23 24

e ii Section Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance Health Physics Summary Procedure De,*iations reviewed by Station Nuclear Safety Operating Committee after Time Limits Specified in T.S

  • Page 25 29 31 33 35 37 39 and 40

OPER~NG DATA REPORT e

OPERATING STATUS

1. UNIT NAME
2. REPORTING PERIOD DOCKET NO. 50-280 DATE 01 JUL 83 COHPLETED BY VIVIAN H. JONES TELEPHONE 804-357-3184 UNIT 1 TO 63083
3. LICENSED THERMAL POWER (MWT)

SURRY 60183 2441 847.5 788 811 775 NIA 1------------------------1

4. NAMEPLATE RATING (GROSS MWE)
5. DESIGN ELECTRICAL RATING. ( NET MWE)
6. MAXIMUM DEPENDABLE CAPACITY ( GROSS MWE)
7. l.fAXD1UM DEPENDABLE CAPACITY ( NET Mw'E)
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS I NOTES I
9. POWER LEVEL TO WHICH RESTRICTED. IF ANY NIA lNET MWE)
10. REASONS FOR RESTRICTIONS. IF ANY NIA
11. HOURS IN REPORTING PERIOD
12. NUMBER OP HOURS REACTOR WAS CRITICAL
13. REACTOR RESERVE SHUTDOWN HOURS
14. HOURS GENERATOR ON-LINE
15. UNIT RESERVE SHUTDOWN HOURS
16. GROSS THERNAL ENERGY GENERATED (MWH)
17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
18. NET ELECTRICAL ENERGY GENERATED (MWH)
19. UNIT SERVICE FACTOR
20. UNIT AVAILABILITY FACTOR
21. UNIT CAPACITY FACTOR (USING MDC NET)
22. UNIT CAPACITY FACTOR (USING DER NET)
23. UNIT FORCED OUTAGE RATE
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE.DATE.AND DURATION OP EACH)
25. IF SHUT DOWN AT END OF REPORT PERIOD.

ESTIMATE DATE OF STARTUP

26. UNITS IN TEST STATUS (PRIOR TO COJ.!HERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COJ.1/o!E RCI AL OPERATION THIS MONTH YR-TO-DATE CUMULATIVE 720.0 4343.0 301.7 1255.6 o.o o.o 227.3 1137.1 o.o o.o 398652.0 2506823.0 118720~0 792935.0 109929.0 748709.0 31.6 olo 26.2-olo 31.6 olo 26.2 olo 1 9

-22. 3 0 /

0 1 9

  • 4 0 /

0

21. 9 0 /

0 4.5 o/o 0.9 o/o 92231.0 55167.3 3765.2 53991.8 3736.2 125187422.9 40398978.0 38309172.0 58.5 0 I 0

62. 6 0 /o *
53. 6. 0 /

0

52. 7 0 / 0 22.6 o/o FALL MAINTENANCE -

10 DAYS 11-11-83 08-26-83 * -

5 days - Snubber Inspection FORECAST ACHIEVED

OPER-NG DATA REPORT DOCKET J.10.

DATE COMPLETED BY TELEPHONE OPERATING STATUS

1. UNIT NAME
2. REPORTING PERIOD
3. LICENSED THERMAL POWER (.~WT)
4. NAMEPLATE RATING (GROSS MWE)
5. DESIGN ELECTRICAL RATING (NET MWE)
6. MAXI"1UM DEPENDABLE CAPACITY ( GROSS !!WE)
7. l,iAXIMU/.1 DEPENDABLE CAPACITY ( NET AJf!E)
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS e

5 0 -2 81 07 JUL 83 VIVIAN H. JONES 804-357-3184 SURRY 60183 2441 847.5 788 811 775 NIA UNIT 2 63083 INOTES I

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY NIA (NET MWE)
10. REASONS FOR RESTRICTIONS. IF ANY NIA
11. HOURS IN REPORTING PERIOD
12. NUMBER OF HOURS REACTOR WAS CRITICAL
13. REACTOR RESERVE SHUTDOWN HOURS
14. HOURS GENERATOR ON-LINE
15. UNIT RESERVE SHUTDOWN HOURS
16. GROSS THERMAL ENERGY GENERATED (MWH)
17. GROSS ELECTRICAL ENERGY GENERATED (MWH)
18. NET ELECTRICAL ENERGY GENERATED (MWH)
19. UNIT SERVICE FACTOR
20. UNIT AVAILABILITY FACTOR
21. UNIT CAPACITY FACTOR (USING MDC NET)
22. UNIT CAPACITY FACTOR (USING DER NET)
23. UNIT FORCED OUTAGE RATE
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE.DATE.AND DURATION OP EACH)

None

25. IF SHUT DOWN AT END OF REPORT PERIOD.

l!:STIMATE DATE OP STARTUP

26. UNITS IN TEST STATUS (PRIOR TO COMNERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMNERCIAL OPERATION 2

THIS MONTH YR-TO-DATE CUMULATIVE 720.0 4343.0 89111.0 691.4 4100.2 56774.7 o.o o.o o.o 687.9 4061.6 55905.7 o.o o.o o.o 1548456.7 9666490.1 130907836.2 467020.0 3 087 7 9 5. 0, 42570514.0 440119.0 29l7496.0 4 0 3 48 417. Q 95._6 olo 93~5 olo 62.7 0 I 0 95.6 olo

93. 5 o lo 62.7 olo 78.9 o lo 87.0 o lo 58.4 olo 77.6 olo 85.*6 o lo 57.5 olo 4.5 olo 1.4 olo 14.~ olo FORECAST ACHIEVED

Nu.

Dale 83-04 6-1-83 83-05 6-18-83 w

83-06 6-20-83 83-07 6-25-83 F: Forced S: Scheduled

('1/77)

UNIT SHUTDOWNS AND POWER REDUCTIONS REl'ORT MONTII __

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1 Reason:

A-Equipment Failure (Explain)

B-M1intemmce oi Test f-Rducling 0-Regulalury Resuictlon Licensee Evenl Rcpurt #

I 1:-0pcralnr Training&. License Examlnallun F-Adminis1r:a1lve G-Opcrallunal Error ( Explain) 11-0lher (Explain)

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J-Autumatlc Scram.

_ 4-0lher (Explain)

DOCKETNO.

UNIT NAME

  • DATE COMPLETED B\\'

TELEPHONE 50-280 Surry I

.J!!!LZ, 1983 "'

...lLiJLian B.,Tao es Ext. 477 Cause & Currecllve Action lu Preveul Recurrence Continuation of refueling outage Turbine was shutdown to oalance turbine and to. do overspeed test Rx trip/turbine trip due-to loss of 114 bus and both auto. transformers in the switchyard caused by lightning Turbine shutdown to balance turbine, unit was delayed in startup to repack MOV-1587 4

s E xhlbll G

  • Instruct lcHl s for Pr,p:u:ulun ur Da1:1 Entry Sheels for Uccnscr Evcnl Reporl (LER) File (NUREG-0160 E~hlbll I* S3mc Su1m:e e

e

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. 6-20-83 83-1~

6-23-83 I

I 83-12 6-30-83

.?

  • F: Forced S: Schtdulcd C'l/77)

UNIT SHUTDOW.NS AND PO\\VER REDUCTIONS REPORT MONTII __

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A-Equipmen, Fallure (Explaln) 0-Mainlenance oi Tesl r-Rdudlng 0-Rcgulalury Res11lc1lun licensee Evenl Reporl #

E-Opera1ur Tralnin1 & Ucensc Examln11lun F-Admi11ls11:11lve G-Ope1:11lum1l l:rrur (Expl1ln) 11-0lher (Explain)

J c

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J-Aulomallc Scram.

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Rx IJ4 in Rx j

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DOCKET NO.

UNIT NAME

  • DATE COMrLETED DY TELEPHONE

_s_o-28_p __. __ _

Surry II

-1!!!:Y. ]

  • 1983 ~

Viyian H,,Ion.es Ext 477 Cause & Currecllve Acllun 11, Prevenl Recurrence trip/turbine trip due to loss of bus and both auto. transformers the switchyard-ca.used by lightning trip/ turbine trip due to "A" main feed regulating valve failing closed caused by inst. techs ;ln racks using a grounded m~ter I

Rx trip/turbibe trip due to "B" main I

feed regulating valve having excessive.

leakage giving a "B" S/G high level trip.

Feed valve will be worked durin1 outage.

kiown for Trip occurred while ramping scheduled refueling outage, 4

Exhibit G

  • lns1ruc1lons for Prepar:iliun uf O:ar:a Enrry Shecls for Licensee Evcn1 Rerurl (LER) File (NUREG*

0161) 5 I 1 Eidllbil I* S:nne Sou,~it I...

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LOAD R...'C'I)UCTIONS DUE TO E:NVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH:

June, 1983 DATE TII!E:

HOURS LOAD 2 MW REDUCTIONS 2 MW MWH REASON NONE

>URING TH tS REPORTING PERIOD.

I MONTHLY TOTAL 5 ***-**

e e

LOAD REDUCTIOl~S DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MOl,TH:

June, 1983

~ nm: I HOURS LOAD, ?-rw REDUCT10RS 1 MW MWH I REASON I

NONE ~URING TH S REPORTING PERIOD

  • I

~

I I

MONTHLY TOTAL

. I 6

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. J

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I'!...Y 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15

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.4~TSi.~AC.7:: f-,1ILY ?O.,TEP

(.'}il"!:, - tl 2T) o.o o.o o.o o.o o.o o.o 0.0 o.o o.o o.o o.o 0.0 o.o o.o 0.0 f,,4.ILY U.'iI':' FQ;-lER LEVEL FOR.':- I!!8T3.UCTI0.1ls L!:.'T/EL r,..., T',.,

_::**.i. -

S[T]7:::!Y I L'A'!'Y 7-1-83 co.";;L'f:'!'T:.T: ~":':Y Vivian H. Jones T). 'r' L r.t.

16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 T ';""'TT!"'T LJ' I ;_.,.J A :r.2"~-::,1(.'E' !'AIT,Y P'?r~.1:.:=.r: 'l.7lEL

( :' -;.,r:-.'.7!.!')

o.o 116.0 123.8 478. 9 458.8 194.3 252.3 547.0 720. 9 33.2 o.o o.o 213.6 708.8 732.7 O,'l THIS Y'OPJ*, LIST ':"HE.4VT:R4G!:,' D.4.ILY UllIT PO!/ER. LEVEL Il.'.~-'ilE-17ET F'OR F.ACi! Dl:.Y IH J'!!E FT?:J '?:'IliC *.m'TH. T!II'SE FIGURT::S T,'ILL BE U8'EV TO PLOT A GRAPF FriR rncrr F:F'POR'J'-

IJl(J !'.C!.'T'H. !:OTE THAT ?Y [J.(";I.G,';/i.X.I'f[F' !JEP,r:rm,~ELE C.4P.4.CI7'Y ro~-: THE !lE'J' ELECTRICAL P.4Til:'G C? ~'?E !!i:T!'. 'J'Tr~RE /.:r.. Y BE OCCASIC~:."J Yr!!Eri '!'i!F' DAILY A E'RAt;'!." -::,or.'f.R r:;7cr:ED8 T=f.r:; 100 °/o LITE (OR TUE RESTRICTED P()TlEFi ['!:;'EL LT.!~). r:.C:UCH CASD.C: 1 ':'.~? !:l'5F..4:JE DAiiJ' i]']I:""" p*c*:.r.-:R OUTP!J'J' /:J!!EET S[-j()!ll,D pr; FOGT?JOTF;r 'I'O Ei:PL1~I?.1 T.T-!P.-1PPLl.T?:=:n'!' A ?.'o~ ~;1r,.1~.

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T!!, V

( '-tT/'F.-NP~)

1 735.7 16 716.4 2

730.2 17 703.5 3

73S.5 18 71:l.2 4

738.9 19 717.7 5

732.3 20 492.5 6

736.6 21 249.9 7

732.0 22 435.3 8

734.4 23 322.9 9

736.6 24 257.0 10 738.4 25 468.9 11 738.4 26 559.1 12 736.5 27 5S5.S 13 733.1 28 567.3 14 731.3 29 543.9 15 731.3 30 6.0

!J_4ILY u*:.r':' EDv/EF LEVEL FOR' 1 Ti8TRUCTI07JS Q?? "'!.'ID _-::icJI::':. LIST 'I'l:.T:.4FZ7F4GE DAILY UJ'IT PO:lEF: LEVEL D 1 'iFE-'t'f:-:' 'PO? EACH f!AY I

TT? I'LP:)_7.:77.-.-; ;:nr.'TTJ. THESE FIGiF?ES flILL '[;F; ~757_:"[l TO PLO'!' A GRA.P.r.r F02 '[:,iCH PI'POF:.'!'-

I!-.1,7 J.'CJ.!'.7. ::t)':'F: 'J'llAT PY 7!SING i!/1YI:',"!J'.' D.t:P'F:?:DABLE CAJ?ll.CI'!'Y _r;i11r;_ 'J"i.11J ;r::T F.:T.ECT.9.Jr.,1r, F..4 ".'I! 'C IJ5' ':'Jc!: ih:TI', - '.:'r!'F.RT: /.:'Jl.Y n,r.; r>r"Cke:Im:!J f.P.E~-' '!'RE Dt.I!J' /1 VET:'A(l.":: POTrz.::R E.YCl"EV8

'I'!':: 100 °/o DI.'TF (()R ':'!-![ F?'F:S'!'PIC'J.':.:.:!J P()T.';:3 LT;!_r:;L LI:':f). r;., :per: C.'12!:S, T,'If.E ATli';."'AGE

[.4IL1!' lf.'-/I:"' F-'t:::..:.7.~F, Ol!TP,'l'I' sr.1:.:"E:'!',.~l:?Jt'l[.D RT FOIJT:;*orF:D TO r:::(PT:.4I:"'! T.T!!: !1.=?A.:~E?~T l7lQ*::'.4LY.

8

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~

SUMMARY

OF OPERATING EXPERIENCE June, 1983 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE June 1 June 2 June 12 June 14 June 15 June 16 June 17 June 18 June 19 0000 This reporting period begins with the reactor critical at 3% power, preparing to roll turbine.

0216 Tripped turbine, #5 bearing is wiped 0742 Shtudown reactor, commenced plant cooldown 1247 RCS< *350°F, 450 psig 1426 RCS< 200°F 0740 2317 1051 0339 RCS drained to mid-nozzle to repair l-Si-82 bonnet leak RCS solid, venting head Bubble in pressurizer RCS > 200°F 1630 RCS> 350°F, 450 psig 1254 Rx critical 1046

?.a.in generator on the line 1435 Holding at 35% power do to chemistry 1735 Commenced ramp to 50% at 3%/hr.

2200 Rx at 50% power, holding for flux map.

0100 Commenced plant shutdown, for overspeed test.

0247 Main generator off the line 1300 Main generator on the line, ramping at 3%/hr.

1200 Stopped ramp at 74% power for flux map.

1500 Ramping at 3%/hr.

2000 Stopped ramp at 84% power for flux map.

2130 Rampin& at 3%/hr.

2335 Stopped 'ramp at 90% po~er for incore/excore calibration 9

l

June 20 June 21 June 22 June 23 June 24 June 25 June 26 June 28 June 29 0741 1300 1607 0031 Ramping at 3%/hr.

Unit at 100% power.

Reactor trip, lost bus #4 and Ill auto. transformer Reactor is critical.

0255 Main generator on the line, commenced power increase at 3%/hr.

0835 Holding power at 42%, working "C" RCP flange leak.

1748 1835 Commenced power increase at 3%/hr.

Holding power at 96% power, investigating main generator amps. difference between phases.

2234 Commenced power increase at 3%/hr.

0120 Rx at 100% power.

2210 Commenced plant ~hutdown, ramping at 150 mw/hr, to balance turbine 0411 0535 0216 Main generator off the line Rx shutdown to repack MOV-1587 Rx critical 0907 Main generator on the line, increasing power at 150 mw/hr.

1002 Holding power due to condenser vacuum problems.

1445 Commenced power increase at 150mw/hr to 70% power.

1645 Stopped ramp at 70% power for calorimetric 1950 Commenced ramp at 3%/hr.

0545 Unit at 100% power.

10

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e

SUMMARY

OF OPERATING EXPERIENCE June, 1983 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT TWO June 1 June 20 June 21 June 22 June 23 June 24 June 25 June 29 June 30 0000 1608 This reporting period begins with the unit at 100% power.

Rx trip due to loosing bus 4 and auto-tie transformers 2003 Reactor critical 2136 Main generator on the line 2220 Rx at 30% power, holding for chemistry 0205 Commenced power increase at 150 mw/hr 0256 Rx at 50% power, holding for delta flux 0615 Commenced power increase at 150 mw/hr 0815 Rx at 75% power, holding for HP drain pump.

1815 "A" HP drain pump was started and tripped on overcurrent.

2116 Commenced power increase with three condensate pumps running.

2344 Rx at 83% power, holding due to feed pump suction pressure.

1152 Rx tripped due to "A" feed regulating valve failing closed.

1330 Rx critical 1535 Main generator on the !ine, slowly increasing power as delta flux drops 2120 Rx at 40% power, holding to reduce delta flux 0510 Commenced power increase to.49% power.

0620 Rx at 49% power, holding for delta flux 0405 Commenced power increase at 150 mw/hr.

1030 Rx at 90% power, holding due to feed pump suction pressure 2120 0059 Commenced plant shutdown for refueling Rx trip due to "B" S/G high level at 24% power 2400 This reporting period ends with RCS at 500°F, setting main steam safeties 11

e e

AMENDMENTS TO FACILITY LICEUSE OR TECHKICAL SPECIFICATIO!~S June, 1983 The Nuclear Regulatory Commission issued, on April 27, 1983, Amendment Nos. 88 and 88 to the Operating License for Surry Power Stations, Units 1 and 2 respectively.

The change has been designated as Technical Specification Change No. 100.

The change revises the schedule requirements for functional testing of the 50 kips and above category snubbers.

The functional testing is rescheduled when an engineering evaluation determines the failure mode to be non~generic.

The Nuclear Regulatory Commission issued, on April 26, 1983, Amendment No. 87 to the operating license for Surry Power Station Unit 1.

The change has been designated as Technical Specification Change No. 99.

The change raises the control rod bank insertion limits for Unit 1 to meet the current radical power peaking factor design limits to Cycle 7 operation.

In addition, this change removes the List of Effective Pages from the Technical Specifications.

12 l

FACILITY CHANGES REQUIRING NRC APPROVAL June, 1983 e

None during this reporting period.

13

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FACILITY CHANGES THAT.

DID NOT REQUIRE NRC APPROVAL June, 1983 DC 81-104 Class lE Transmitter. Replacement Unit 1 This design change replaced certain transmitter:with equivalent transmitters which have adequately demonstrated environmental qualification per the guidelines set forth by IEEE Std 323-1974.

Summary of Safety Analysis The modification will provide additional assurance that the transmitters will perform their intended safety function during and following a postulated LOCA or HELB accident.

DC 81-116 Main Steam Piping Monoball Support Modification Unit 1 This design change added support steel to stiffen the existing monoball supports for the main steam piping.

Summary of the Safety Analysis The modification of the Main Steam Piping Monoball supports will serve to enhance the capability of the supports to function as designed.

This modification will not adversely affect any safety-related system or component.

DC 82-05 Diesel Generator Exhaust Modification Units 1 & 2 This design change cut and removed the exhaust piping exposed to a potential tornado generated missile on the three emergency diesel generators.

This will ensure that the exhaust piping is located within the existing reinforced concrete structure. Deflector plates were installed to direct the exhaust gases out of the structure.

Summary of Safety Analysis The modification does not requ,ire a change to the Technical Specifications, the Final Safety Analysis Report and it does not create an unreviewed safety question as defined in 10CFRS0.59.

DC 82-10 Class lE Terminal Block Replacement Unit 1 This design change replaced certain terminal blocks with equivalent terminal blocks which have adequately demonstrated environmental qualification per the guidelines set forth by IEEE Std. 323-1974, IEEE* Std. 344-1975 and NUREG-0588.

Summary of Safety Analysis The modification will provide additional assurance that the terminal blo.cks will perform their intended safety function during and following any postulated LOCA or HELB accident.

14

DC 82-16A Replacement SKV Electrical Penetrations Unit 1 This design change replaced 9 existing penetrations with new Conax penetrations.

The design of these replacement penetrations utilizes ceramic bushings at the pressure boundary and requires no compound.

The lack of maintainability of the old connectors and the difficulty in procurement of replacement components resulted in the decision to replace the penetrations with those of a proven and qualified design.

Summary of Safety Analysis This modification does not affect station operations or the operation of safety-related equipment.

The replacement of the penetrations enhances the containment pressure boundary, as well as the operation of the Reactor Coolant Pumps and Residual Heat Removal Pumps.

15

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TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL June, 1983 None during this reporting period.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL June, 1983 None during this reporting period.

1-6

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OTHER CHANGES, TESTS AND EXPERIMENTS June, 1983 None during this reporting period.

17

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION

.CHEMISTRY REPORT JUNE 19 83 ---

T.s. 6.6.3.d PRIMARY COOLANT UNIT NO. 1 UNIT NO.

ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM 6.17E-l 8.. 57E-2*

-1 Gross Radioact., uCi/ml 8.99E -

4. 25E Suspened Solids, ppm 0.5 0.5 0.. 5 0.5 Gross Tritium, &J.Ci/ml l.96E-2 l.56E-2 1.76E -2

-1

2. 02E Iodine131,

3.24E-3

_r:; 1. 55E-3 4~37E-l

&i.Ci/ml

6. 08E..

l!l31/Il33 (A)

(A)

(A) 1.39 (B)

Hvdrogen, cc/kq 23.1

1. 9 13.4 42.1 Lithium, ppm 2.10 1.00 1.59 1.00 Boron-10, ppm*

368 130 231 209 v.Ay...,en, (D. o.),oom 0.800 0.005 0.005 0~005 Chloride, ppm 0.05 0.02 0.02 0.05 DB @ 25°C 6.67 5.70 6.20 8.47

  • itaoron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS (D)

T.S. 4.13.A.6 Phosphate ____ ~

Boron, 1582 Sulfate Chromate o.o 50% NaOH ----

Chlorine 0.0 MINIMUM l.34E-l

. 0. 5

. -2 l.62E

1. 49E-3

.37

,cJ 15.4

.33 1

0.005

. 0. 02 6.72 2

AVERAGE 2.87E-l 0.5 1.56E-l 7.16E-2

.66 30.9

.78 21

  • 0.005 0.02 7.57 REMARKS:

(A) *. Unit not at stable i;:x::,wer for the 48 oours required for this test.

(B}.

ICM average reflects Unit's caning up £ran scheduled shut-down.

(C) * *tJnit at O i;:x::,wer cx:mnencing to de-gas.

(D).

~

levels of these chanicals should produce-no adverse enviromental inpact.

'!he follCMi.ng Lithian additions were made: Unit 1.

1600gms on 6/15; 486gms on 6/17; 810gms on 6/19; 810gms on 6/21; 245gms on 6/24; 490gms on 6/26; 972gms on6/27; 89lgms on 6/28; arxi 650gms on 6/28. Unit 2.

340gms on 6/3; 370gms on 6/7; 340gms on 6/10; 162gms on 6/18; 420gms on 6/19; 440gms on 6/21; 630gms on 6/23; 845gms on 6/24; 227gms on 6/26; and 324gms on 6/27.

18

e DESCRIPTION OF ALL INSTANCES WHI THERMAL DISCHARGE LilfITS WERE EXCEEDED JUNE, 1983 NONE DURING THIS REPORTING PERIOD.

19

DATE SHIPPED/RECEIVED NO. OF ASSEMBLIES PER SHIPMENT FUEL HANDLING UNIT #1 June, 1983 ANSI NO.

INITIAL ENRICHMENT NONE DURING THIS REPOE ['ING PERIOD.

20 NEW OR SPEh"T FUEL SHIPPING CASK ACTIVITY LEVEL

DATE S~IPPE.D/RECE!VED e

NO. OF ASSEMBLIES PER SHIPMENT FUEL HJJ-IDLING UNIT #2 June, 1983 ANSI NO.

INITIAL ENRICHME11' NONE DURING THIS REPOR [ING PERIOD.

21 l

I NE\\.: OR SPE1"T FPEl SHIPPING CASK ACTIVITY LEVEL

~ROCEDURE REVISIONS THAT CHANGED~E OPERATING MODE DESCRIBED IN THE FSAR JUNE, 1983 NONE DURING THIS REPORTING PERIOD.

22

e e

DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LLt.fITS SPECIFIED IN TECHNICAL SPECIFICATIONS June, 1983 None during this reporting period.

23

e e

REPORTABLE OCCURRENCES PERTAINING TO ANY OUTAGE OR PO'v."ER REDUCTIONS JUNE, 1983 NONE DURING THIS REPORTING PERIOD.

24 -*.. *-.....

MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 1 MECHANICAL MAINTENANCE June, 1983 25

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  • _OG/!)6[83.. HS_.VA£VC.*. _SOV-~1S-:102JL___SEX-L1Mir....slUXCllltS BH9HBN-/,&W-R/H1HRB8 30~tU3o--.--.. -------. -*

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  • COHPR DOES NOT UNLOAD,

._ '. HO'l'rJR AND CON7'1V£S 30602ilf17 1: (' 06/08/83 n,1 COVTIIOT,£ £C/llA 102 FIX OR REPLACP. L~E£ CONTROLLER DRIED our TF:ST SAT 3032311f30 _Of./09/83.m, __ /IOTOR *--..1~R/l-:P-1A ----ADD.. OII.-~l'.P8R-PO!f-ARIJBIHJif,-ffJ-iJPPBR--f'Or 3086'Jt0211--------- * -

  • '*I OG/09/83 ""

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i 06/l?./113.. I/I V/tf.!'P.

.. TV-IA-:100 _______.££0,<;ED.INDIC. CON~-RN-... - --...c....Alllf/S'JWl}-£nll'r8-ARB-* --- 0608U52 * -**-** *

    • Qfj/J 3/83 PP.

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( '.'!'!11"l'!J __ 1,,:... _11*11*,*;__ **-----"-~l3 ________ __clJECLI!D1S Ori BOO alU PIN-CN'ltClf-&4'1' it0691:1620-------- " Ofj/111/83 CII VALVE /10V-£CV-1115C VLV III££ NOT CLOSE C£EARED ffJRQUB SJ/1'ICII 306071651 C.* " OG/15/83 FP nATT CliG RIA CIIECK nAffli:R1 CHAllCER .. CHBCKED CHARGF:R ANC, 3060923111 1 AA/15/83. CL A£Alrfl. B-Cl-lf ... _.....A£ARJ.I IIIL£.. N07'.. UCNT -REl'l,MJt;l).. CARl>--Arl/J--* ~06130729 ---*-------- " ut/15/83 s:: VAT.VF. IICV-SS-1028 NO INIJICATINC £IG11TS INIJICATING £IGilTS CHECK 205201101f C. 11* 06/16/83 PP PA1*r1,'h' l'l'-P-2 LOOSE DATTA'HI CAB RA'PAIR llBPLACED BATTA'Rl 306162020 ,1. OG /16 /8:J __ CII.. l'UI//' .1-CH~ P.-:1A ------.* JJT PIPlNC....JIE8DS-TO../JE. I.A<;<;fiD RSPLACEI> Al.~IBSING.. --- 06 051515* ------- ** "I 06/H,/83 Cl/ l'llnP t-Cll-1'-lfl Pil'IllG NEEDS TO BE LAGGED llEl'LACI!.' ALL HISSING 306051511J , 1., 06/17/83 #:S VALVN TV-l1S-101C VALVE III££ IIOT OPBII VALVt.' CHEC/t.ED SAT. 30616065J '. 06/17/83 RI RECO/Wlt NIA INVALI1J.-A£ARM-- ---*-ALARHS CHBCKBIJ BAT-- ---- --------306131000* -------*--**

06/21/83 rs PU/ll' 1-VS-P-lA Cl/ANGE OUT BBARINGS MOTOR CLBANBD AND 3051111201 i

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,, 06/21/83. El' COIL F:-11

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  1. IOV-RS-155A RESP.T CLOSING STOP LIMIT STOP UNIT R~SBT 303270930 l*.. 06/21/83 RP ROD Pt?Sl P-8 CIIF:CK CONNf,'CTIOII ON 11EAD CLF:ARA'D Pl,/JG COHPLF.'1'8 301191529

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... -*--*--*--*-:,001s2023* .. I 06/?.r;/83 !m V.~T.Vf.' TV-SS-106R RF.S7YJR1~ VLV INDICA CYCLED VA£VF. SAT 30621J0302 ~,. oi;/2'i/113 R!"I AT.Ari'/ R-D-1 ALAR11 f/ILL NOT 1,IGHT RF:PMCF:D CARTJ AND 306130730 Oli/2R/1.13 C/1 _JIT. 1-Cll-l'-lC----1'1/Lf. RACIC-.Jfl!.------------*-RWHOVB-+-lillPLMJR------------* 306271039------------ I, -***.. ~*--**-*---.. *.. . **1 -1:p

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MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 ELECTRICAL MAINTENANCE June, 1983 33

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  • ----------------------------~--...,,..,_....,.-,,,,.,.,..,.._,..,._..,,....,..;,.,..,.,...,..,--,-,----,-,,..,.------------*--.

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,g "06/10/83 RC INSTR Y1-VU:,-101A ALAR/.IING FOR NO REASON RESET WSS OF SIGNAL 305291317 f~ ~ 06/10/BJ RC E'WR CA/J II/A URGENT FAILURE ALARH REPLACED MXR1. REf,AY 306010900 ~ ~ 0&/10/BJ JIP INSTR ffl6 INDICAXING HOO B8TTGHTEN£W SC4C8 ID 'J06010818 ~ . oslio7aa-iil-iNSTll-*--RI-LW-108 rAIL/RESE'l' LIGIIT fl!LL NOT)ioRJ{j;.-:'.');;i,;R~PLACEp.;TRANS1STOR /;.;/(:/;'/' - 3i>20lt195lt E ('., ~ 06/llt/83 RC CONl'A. IIAT E'C-lf;J. 5 ALRM COMES IN ABV S87'f!<)INT):"i..i i((,t;/ ALARM *ctEARED Bf RESCAlf ~iO;,'., *,!l;{;,ir 305071238 ~ 11 06/15/BJ ____ cx: ___ GAl/GE... __ PI-CC-139tL___QIJLIBRAXJL!iAJJGK__.* .*;*: *. _;. *..::*.>,;:

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~06/15/83.RC INDIC PI-1-lf68 INDICATED FAILED LOW REPAIRED LOOSE CONNECTION 306152000 f

  • 06/16/83 DC TRANS,'!

LT-DG-101 CALIBRATE TRANSMITTER CALIBRATED TRANSNITTBR 306101615 '06/16/A3_RC MODULF. __ (,fct~IJ661/ _ _f:IJEJ..'K.J'RIP PQTNTS BEAOWSTF:D COMP4H47'0R lOGJ.4.l.a.G1... 5=----------*--*-*--. -- *-- *-*--.. OG/17/83 Rft NOl!I'F(}JI RN-R,'/S-12111.. FAIL1JH"t: LAHP ON

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06/21/83 CH JNSTli FCV-U:n CONTROU, NOT CONTROLLING 1,0WERF.D SETPOINT l'OT 306202115 ~ "OG/23/83 FP. Cr>>fl'R 1-F.8-F:G-1 (.'(JffPRP.SSOR WONT START IN AUTO REPAIRBD + CAHRRATED 306190357 "!ll;/2=!/.1!3_l!/ __ r;~_.T]JP..(lr __ fl.[:.11_1,_ ______ JlL!JL.llEAllIJKLJliuU ____...,_.-,--,,...--RESCALED....lUJIJER--RAN'li.C~li'-------,-lwOl>t-n-1J~--------....... _ 06/23/83 RC LlllfICR Yl-Vr!.<;"-101A. INV8STIGA'J'E.. PROBLEM

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MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT NO. 2 INSTRUMENT MAINTENANCE June, 1983 37

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SUMMARY

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f.\\ ' 06/23/83 MS NODULE F/.f-2-1ns RESCALE MODULE 'REi;c,fr.eD MODULE 3060617117 06/23/83 ~s !fOD(lf.f; m-2-11 BS RESCAl,E* MODUT,,:-- ---* -*----* -* *----mrsCAt~*jtoDULE_____ - --:30608171J6 ""- -*--*-....... 06/23/83 JfS lf0D(l[,F, FU-2-1195 RBSCALE f.lODULE RESCALED IIODULE 3060817115 (. " 06/23/83 SI INSTR LI-2-922 CHANNr:L DEVIATBS BLEW WATER OUT OF 3061722111 11 -06/2'1/83--RP**--INPIC- -*K-2-*----*-*--ERRATie ~WUSTKrrrNDICATOlr-AN . _.-:-*3052216111**--*--* " 06/29/83 RC INSTR Ti-1150 RF.PLACt AMP

  • . *. REPLACED AND CALIBRATED 306250930

" 06/29/93 F:F: Sf'TTCII NIA COMPRE WILL NOT STOP .,;, CLEANED AND AWUSTED 305220633 "-oi;/~0/Fl3 *f:H... IN!/1'ff*... U-CH-200...:.....:.--*-r.RRll.rrc-1Nb1CA1'ION

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C if) .. 1. HEALTH PHYSICS June, 1983 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. l

r* PROCEDURE NO. PT 2.lOA (F-1-496) PT 32.3 MMP-C-HSS-019 MMP-C-HSS-019 L PROCEDL""RE :::lEVV.TIONS !',EVIE'i*:'ED BY STATIO:-: m.iCLEAR S *.\\FETY AND OPERATING CO:-Il.fITTEE *.\\FTE:: TI!!E LIHITS SPEC!FIED IN TECE.KICAL SPECIFICATIOXS June, 1983 DATE .!!!!I TITLE DEVIATED 1 F-1-496 Feedwater Flow 5-19-83 1,2 Compressed Air Piping Capacitance 4-29-83 Test for Auxiliary Ventilation 2 Removal/Rebuilding/Reinstallation of 4-22-83 12" B-P Suppressors 1 Removal/Rebuilding/Reinstallation of 4-28-83 12" B-P Suppressors 40 DATE SNSOC REVIEWED 6-3-83 6-3-83 6-15-83 6-15-83}}

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