ML18113A793

Monthly Operating Rept for Dec 1978

ML18113A793
Person / Time
Site:	Surry
Issue date:	01/04/1979
From:	Costello O VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18113A791	List: ML18113A790 ML18113A793
References
NUDOCS 7901190055
Download: ML18113A793 (42)

Text

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{

VIRGINIA ELECTRIC AND POWER COJVIANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO;*

78-12 DECEMBER, 1978 APPROVED:

L:) 32, til'J~AGER 7901190055

i--

CONTENTS Section Operating Data Report -

Unit #1 Operating Data Reprot -

Unit #2 Unit Shutdo~1s and Power Reductions -

Unit #1 Unit Shutdm~1s and Power Reductions Unit 112 Load Reductions Due to Environmental Restrictions Unit Ill Load Jleductions Due to Environmental Restrictions Unit 112 Average Daily Unit Power Level - Unit Ill Average. Daily Unit Power Level -

Unit 1!2 Summary of Operating Experience ArJendments to Facility License or Technical Specifications Facility Changes Requiring NRG Approval.

Facility Changes That Did Not Require NRG Approval Tests and Experiments Requiring NRG 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 1'n1ich Were Not Completed Within 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 #1 -

Mechanical Maintenance Maintenance of Safety Related Systems During Cu.tage or Reduced Power Periods -

Unit #2 -

Mechanical Maintenance 1:

2 3

5 6

7 8

9

• 11 12 12 14 14 15 16 17 18 21 22 23 24 25 28

. I_

Section Haintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Relkted Systems During Outag~ or Reduced Pc:wer Period:.; -

unit {.!2 - Electrical 1-hintenance Haintenarice qf Safety Related Systems During Outc;geor_ Reduced Power. P~riods - Unit {fl -

Instrument N,,_intenance Haintenance of Safety Related Systems During Outage or Reduced Power *Periods....: Unit 112 - Instrument Haintenance Health Physics Summary Procedure Deviations reviewed by Station Nuclear Safety and Operating CoIDiilittee after Time Limits.Specified in T.S.

i30 32 34 36 *.

38 39 OPSRA.T!,~/G &_1r.1.A R-DQRT Ii.~..

DOCKET NO. 50-280 D.4TE 04 JAN 7~

COMPLETED BY O.J. COSTELLO TELE?HONE

~04-357-3184 OPERATING STATUS

~~------- ------

1. UNIT NAME SURRY UNIT 1

2. REPORTING PERIOD

3. LICSNSED THERMAL POWER <UWT)

-4. NrAHEPLATE _RATING \\GROSS MWE)

5. DESIGN ELECTRICAL RATING (NET MWE)

E. MAXIMUM D5PENDABLE CAPACITY (GROSS MWE)

7. MAXI~U0 DEPENDABLE CAPACITY lNET ~WE)

8. IF CHARGES OCCUR IN CAPACITY RATINGS (ITE,~iS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS 0001 12-1.-7-8 TO 2400- 12-31-78 i441

,-------------~----------,

~47.5 !NOTES I

~22 I

I 911 I

I 775 l _____________ :.__'_ ________ I NIA 9~ POWER LEVEL TO WHICH RESTRICTED. IF ANY NIA

\\NET M'ilE)

10. REASONS FOR RESTRICTIONS~ IF ANY

11. HOURS IN REPORTING PERIOD

12. iVUNBER OF HOURS REACTOR i./AS CH.ITICAL

13. REACTOR RESERVE SHUTDOW~ HOURS

14. HOURS GENERATOR ON-LINE

15. UNIT RESERVE S!iUTDOtiN FIOURS

16. GROSS THERMAL ENERGY GEOERATED (MWH)

17. GROSS ELECTRICAL ENERGY GENERATED (MWH)

19. VET ELECTRICAL ENERGY GENERATED (MWH) 1~. UNIT SE0VICE FACTOR

20. UNIT AVAILABILITY FACTOR

21. UNIT CAPACITY ?ACTOR (USING MDC ~ET)

22. UNIT CAPACITY FACTOR (USING DER NET)

23. UNIT FORCED OUTAGE RATK

24. SHUTDOWNS SCHEDULED QT/ER NEXT 6 MONTHS (TYPE.DATe.AND DURATION OF EACH)

25. IF SHUT DOWN AT END OF REPORT PERIOD *.

• ESTIMATE DATE OF STARTUP

26. UNITS IN TEST STATUS.

. (PRIOR TO COMMERCIAL OPERATION)

INI'1.'IAL CRIT_ICA1.. ITY IRITIAL ELECTRICITY.

COM!1ERCI AL OPEH.ATION NIA THIS MONTH XR-TO-DATE CUMULATIVE 744.0 259.9

0. 0 250.8

0. 0.

583881.:)

187570.0 178035.0 33.7 ojo 33.7 olo 30.9 olo 29.1 o/o f) 5. 6 o/o NONE 1-2 79 9760.0 6393.0

). 0 6293.7

0. 0 15214957.0

!~94771.J.0.0 4704155.0

71. 8 o I?..

71. B ojo E9.3 o/o 65.3 o/o

7. 2 o/o 52824.0 3 5-6 g ':' * ?

o. *o 34858.9 0.0 80355953.0 26307583.G 24971719.0 6E.O olo c6.0 o/o' 61.0 olo

.; 5 7. 5 o/ o 16.3 o/o FORECAST ACHIEVED

OPE RATING STATUS

~-------- ------

1. UNIT NAL'1E

2.

R~PORTING PERIOD REPORT DOCK.ET NO.

D.4l'E COMPL~T°E,'D BY TELEPHONE

• 3. LICENSED THERMAL PO~E? (MWT)

4.

NA~EPLATE RAT:NG :GROSS MWE)

5. DESIGN SLECTRICAL RATING (NET MW~)

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE)

7. MAXIMUM DEP8NDABtE CAPACITY (NET MWE)

9. IF CHAYGZS_OCCUR IN CAPACITY RATINGS (ITEMS~ THROUGH 7) SINCE LAST REPORt. GIVE REASONS S0-2S1 e 04 J.4ll 79 O.J. COSTELI.iO 004-357-31~4 SlJRRY UtlIT 2 0001 12017? TO 2~00 123178 2441

,~------~----------------,

947.5 822 811 775 N/A I :VOTES I.

I I

I I

l

'-----------~------------'

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY N/A UlET MYE)

10. REASONS FOR RESTRICTIONS. IF ANY N/A 11.. 80URS IN REPORTING PERIOD

12. NUMBER OF HOURS REACTOR WAS CRITICAL

13. REACTOR RESERVE SHUTDOWN HOURS

14. HOURS GENERATOR ON-LINE

15. UNIT RESERVE SHUTDm!N HOURS

16. GROSS THERMAL ENERGY GENERATED (MWH) 17: GROSS ELECTRICAL ENERGY GENERATED- (MWH) 1e. NET ELECTRICAL EJERGY GENERATED (MWa)

.* Q

..I. -

• 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 OF EACH)

25. IF SHUT DOwN AT SND OF REPORT PERIOD.

ESTIMATE DATE OF STARTUP

26. UNITS IO TEST STATUS lPRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY T:iIT I AL E LEC*TRIC.IT Y COMMERCIAt OPERATION THIS MONTH YR-TO-DATE CUMULATIVE 744.0 724.2 0.0 722.1

0. 0 1747175.0 567125.0 539749.0 97.1 o/o 97.1 o / o 93.4 o/o 39.1 o/o 2. 9 o / o 9760.0 7267.7

0. ;')

• 72413.L~

0. 0 17525943.0 5657145.0 5371967.0

'!. 2. 7 o/o e 2. 7 o/o 79.1 o/o 74.6 o Io I

2. 2 o/o 49704.0 336130.5 0.0 3 31 77. 3.

0.0 77236177.0 2 s 2 2. 4 5 3 9

• 0 23925084.0 6 6. 7 ojo 6 6. 7 o / o 62.1 o / o 5 '!

• E o/o

.2.1. 4 0

., 0

/.

STE At'>'f GENERATOR REP LAC ENE NT 6 NONTHS 1-25-79 FORECAST ACEilEVED

Nu.

Dale 78-7 12-8-78 78-8 12-12-78 1

F: forced

- S: Scheduled UNiT smsnJOWNS AND rm*vJER rrnpUC."TIONS REPORT MONTii DECEMBER 1978 I

,.,.LI

'.)

i

-E 11 rl

> eo... I licensee i::

c:: 'J I

U Methot!:

I ~Manual 2-Munu:il Scram.

J-Aulomallc Scram.

4-0lhcr (Explain)

. 50-280 Surry 1 f)OCKETNO.

uNITNAME

• - DATE Jan.-4, 1979 S. Steve1.1.s COl\\iPLETE!J,BY iELE! i!ONE (804) 357-3104 CmlSI: & Coriedivc Acllon lo Prevc111 Recurrence Rampdown to repack "B" and "C" Hain l

Feed Regulating valves.

Repacked valve::;,

While return;Lng to 100% power, reactor t-ripped by_ turbine trip on Hi-Hi level in "C" steam generator caused by mal-function of "C" Hain Feed Regulating valveo Adjust~d stroke of valves.

Primary t:o Secondary leakage on "C" steam.generator exceeded 0.3 gpm limitation.

Shut Clown at end of reporting period.

Inspected steam generators and plugged :;.eaking tubes.

5 Exhibit G-Hnslrni:tlons for Prcpic:aliun of Data Entry Sheets for Uc.:cnsee J~venl Hcpo11 (LEIU Fik (NUltEG*

0161.)

ExhibiU

• Saml! S11111..:1!

I w I

!'J,'.

78-8 I

Date 12-2-78 F

21.9 A

UN ff SHUtDOWNS AND POWER RlEPUCTIONS l

iuwoar MONTH DECEHBER 1978 licensee Evcnl Rcpotl #

DOCKET NO~....,5_0_-*_2_81_,,....., __ _

• UNIT NAME Surry 2.

S).' *... *nr.

.* ~

tO~WLET!~l*;:.i;Y s:-st'e'vcms~-~~

lELEi l!ONE (804) 357-3184 Cause & Corr eel Ive

At:t!o11.au:

Prcvc111 Hc~1a1cni:e 8 GPH Primary leakage via 2-CH-314 valve packins. Repacked valve.

F: forced S: S.ch<!dulct!

('J/77}

Heaso11:

{\\*Eq!iirim;ent Failure (Exp!aln}

IJ-Mafo!Ciiam:e i>i Tes!

C-Rcfoclhlg..

. D*Hcglllalory Hcs1rli:1!011 E*Opi!rato1 Tiai11i11g & License Examlna!lon F -Ad 111i llisr r al i*1c.:

c;.Opcr;1till11al b1111 (Explain}

11 Olhcr ( bplaio) 3 Method:

I *Manual 2-?lifanu:ii Scrnm.

3-Autonli.ll!c Scram.

4-0lhcr (Explain) 4 5

Exhibit G - !11slmctlo11s for Prepa!a!lmi of Dara Entry ~heels for Lh:ensee

,Evcul ltq1urt (LEIO Fik (NUIU.:G-

• 0161) bhil>i1 I-Same S11u1..:I!

I

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• I-f, l,,

(J I

LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: DECmIBER, 197~

f-i l

I DATE TIME HOURS LOAD, HH.

REDUCTIONSl NI HWH REASON None duri h.g this reporti ng eriod.

. I I

I HOt{THLY TOTAL I

[*

e e

LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT N0.2 MONTH:

DECEMBER. 1978

-r--

DATE TIME HOURS LOAD, HW REDUCTIONS 2 HH HWH REASON None duri1g this reporting-eriad.

MONTHLY TOTAL 0

lj_Qfl.'l.Jl. :

DECE,:JBER 197?

AVERAGE DAILY PO'/IER LEVEL DA:Y

\\!-f'tl E NET) 1 736.9 2

747.7 3

737.8 4

746.5 t>

749.2 6

748.6 7

750.4

• 13 664.6 9

I 76.9 10 710.0 11 731.3 12 18.3 13 0 * :J 14 0.0 15 0.0 16 0.0 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS DOJi.Ji.ET NO UNIT DATE COMPLETSD BY AVERA.GE DAY 17 19 19 20 21 22 23 24 25 26 27 28 29 30 31 50-2~0 SURRY 1 1-1-79 0 J COSTELLO DAILY ?0',!ER (N'i/E-NET)

IJ

• 0 0.0 0.0 o.o 0.0

u. 0 0.0 0.0 0.0 0.0 lJ

• 0 0.0 0.0

0. 0

0. 0 LEVEL ON THIS.FORM. LIST THE AVERAGE DAILY UNIT POJER ~EVEL IN MWE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR jHE NtT ELECTRICAL Rr1TI}IG OF THE UNIT. THERE MAY BE OCCASI.'JNS 'tlHEN THE DAILY AVERAGE.POWER EXCEEDS THE 100 ~/ 0

~INE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVSRAGE DAILY UNIT POWER OUTPUT SHEET.SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

}10.'l'J:.fi.:

DEC ~:~*!BE l?.

197g AVERAGE DAILY PO~lEF( LEVEL DAY

'u"J;.; E-NET) 1 752.9 2

647.5 3

25.4 4

E82.0 5

755.2 6

755.6 7

757.3 8

756.3 9

753.8 10 755.4 11 756.9 12 747.8 13 755.2 14 751.7 15 749.5 16 749.8 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS DOCK2.'T NO UNIT DATE COMPLETl?D BY AVERAGE UAY 17 18 1°9 20 21 22 23 24 25 26 27 28 29 30 31 so-2°1 SUH.RY II 1-1-79 D J COSTELLO DAILY Po;.; ER U1YE-NET) 749.0 747. 3 7 53. 1 758.4 758 0 757.5 756.3 750.2 750.4 752.8 756.2 7 51. 5

.750.1 7 51. 6 75*3. 4 LEV~:,

ON THIS FORM. LIST THE AVERAGk DAILY UNIT POWER LEVEL 1N MWE-NET FOR EACH DAY IN THE.REPORTING MONTH. THESt FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT. THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POYER EXCEEDS TEE 100 °/ 0 LIUE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGg DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPAREN~ ANOMALY:

1 *---* -*

. I ~ill-frt~RY OF OPERATING EXPERIENCE~

DECEHJ3ER, 1978 Listed below in chronological sequence by unit is a sununary of operating experiences for this month which.required load reductions or resulted in signi!-

ficant non-load related incidents.

UNIT 1 December 1 December 8 December 9 This report period begins with the unit at 100/; p9wer.

At 0735 power was reduced to 97/~ to *facilitate removing "A" High Pressure Drain Pump for repacking~ At 0810 power was returned to 100%.

Operation with the "A" High Pressure Drain Pump out for repacking and the "B" High Pressure Drain Pump inoperable with a motor prob-lem caused an approximate 40 HWe reduction in unit output.

At 1550 11A 11 High Pressure Drain Pump was returned to service.

At 1855, commenced unit rampdown to approximately repacking "B" and "C" Main Fe~d Regulating Valves.

rampdown at 100 MWe, 17% reactor power.

100 MWe to allow At 2220, stopped At 0416, the *reactor tripped on turbine trip caused by Hi-Hi Level in "c

11 Steam Generator.

Hi-Hi Level was the result of a malfunction df 11c 11 Main Feed Regulating Va.lve.

At 0550 reactor was critical.

At 0735 reactor tripped by turbine trip on Hi-Hi Level in "C" Stearn Generator *.

Hi-Hi Level was the result of malfunction of 11 C11 Main Feed Regulating Valve.

At 08L' reactor was critical.

At 1025, with unit critical and turbine latched but not on.the line, received rod urgent failure alarm.

At 1144 while instrument technicians were attempting.to resolve the problem with the rod control system, rods F-:10.and x,.:.,10 droppedo. The

')'."eactor and turbine were manually tripped. Instrument Technicians resolved the problem with the rod control system, and at 1715 the reactor was critical.

At 1940 the turbine generator was on the line and power increase COillillenced.

At 2252, secured ramp at 600 :t-me due to secondary chemistry transient caused by condenser inleakage.

At 2345, commenced slow ramp to 675 MWe.

At 0650 unit at 670 MWe.

December 10 -

At 0700 commenced ramp to 100% power.

At 0921 reactor power was at 100% *.

• December 11 -

At 2140 commenced unit shutdovm due to.

11 C 11 Steam Generator primary to secondary leakage in excess-of allowable limit.

December 12 -

At 0214 the generator was off the line.

At 0243 the reactor was shutdown and at 0825 the unit was at less than 350°F.

December 31 -

This reporting period ends with the unit still.shutdown for.steam generator tube inspeittion and.repair.

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

At 1625, commenced unit shutdown due to excessive primary leakage on 2-CH-314 (Letdown Line Hanual Isolation Valve) packing.

At 2325 the generator was taken off the line.

At 2335 the reactor was shutdown.

UNIT 2 December 3 December 4 December 31

-.;...Lu-;;----

-MMARt OF OPERATING* EXPERIENCE *

(CONTINUED)

At 1925 after repairs to 2-CH-314 were completed, the reactor was taken critical. At _2119 the generator was placed on the line.

At 0200 the power increase was stopped at* 71% power on request of the system operator.

At 0500 commenced raising power.* At 0730 the unit was at 100% power.

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

AMEHDHENTS T~ACILITY LICENSE OR TECHNICAL SICIFICATIOUS DECEMBER, 1978 None during this reporting period.

Design Change FACILITY CHANGES REQUIRrnG NRC APPROVAL DECEMBER, 1978 None during this reporting period.

FACILITY CHAHGES THAT DID. NOT REQUIRE NRC APPROVAL DECEMBER, 1978 DC-76 Steam Generator Blowdown Description - This modification reduced the blowdown water to a sufficiently low temperature and pressure to enable processing the water by a demineralizer system.

Summary of Safety Evaluation This design change meets or exceeds t~~ safety specifications of the previous system.

Conclusion This modification neither constitutes an unreviewed safety question nor alters the basis for any Technical Specification.

Unit 1,2

2.

DC-77-RCS Overpressure Hitigat_ing System

1.

Description -

The containment instrument air system header to the power operated relief valves (PORV), was modified with the addition of a solenoid valve and a backup high pressure air supply in the line to each relief valve.

Two existing RCS transmitters have been used to provide high pressure alarms and to control the PORV's.

Two keylock switches were installed in the main control board ver.tical section to permit administrative control of the system at the appropriate point during cooldown or heatup.

Summa~i of Safety Evaluation No margin of safety defined in.. the basis for any Technical Speci-fication has been reduced, no potential accident or malfunction dif-ferent fron those previously evaluated have been created, and no consequences of accidents previously postulated have been increased in magnitude.

Conclusion This design change neither constitutes an unreviewed safety question nor alters the basis of. any existing Technical Specifications.

-13_

FACILITY CHANGES THAT A

.ID NOT H.EQUIRE NH.C APPROVAL W (CONTINUED) udit

3.

DC-77 Domestic Water Backflow Prevention 1,2 Description -

In order to comply with State (Virginia) water works regulations air gap, vacuum breaker, and reduced pressure backflow preventers were installed in'the domestic water system at appropriate postions.

Summary of Safety Analysis The installation of this design ch~nge has no refl~ction oti the Safety Analysis Report or the Technical Specification.

Conclusion This design change does not. constitute or create an unreviewed safety question.

4.

_p_c-7 8_

• Waste Oil Storage Fae il ity 1, 2 Description -

This design change provides for a sump, a sump pump with accompanying equipment to collect and transfer waste oil to a storage tank ~ Provisions have been included to reduce the probability of oil spillage which would ultimately seep into the river with the instaliation of a dike surrounding the tank.

Summary of Safety Evaluation No modification to or category 1 systems have been incorporated into this design change and safety aspects have been addressed with respect to fire and oil spill measures.

Conclusion This design. change does not constitute an un'reviewed safety question antl the subject is not addressed in Technical Specification.

ST-31 ST-35 TESTS AND EXPERTNENTS REQUIRING NRC APPROVAL DECEMBER, 19 78 There were none during this reporting period.

TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL DECEMBER, 1978 Service Water Subsystems Data Acquisition TP.st

. Unit The results of this test are still being analyzed at this time,*

1,2 however, indications are that it was completea successfully and any results to the contrary will be reported l!n the.next monthly report.

Test was conducted December 28, 1978.

Inside Recirculation Spray Pump Test was conducted on December 30, 1978.

This test to check*

the amperage bn the recirculation spray pump motors after pump maintenance proved satisfar;:tory.

1

OTHER Cl:ll1.NGES, TESTS fu'JD EXPERIMENTS DECEHBER, 1978 There were none during this reporting period.

• ~*v*-*:}.t ~.. *

• r*

1-SURRY POWER STATTON CHL1JSTRY REPORT DECEHE ER, 19 _2~

T.S.6.6.A.11 PRIHARY COOLAl.'-ff UNIT NO. 1 Ai"JALYSIS MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml S. 77E-l 9.07E-3

1. S3K-l Suspended Solids, ppm

o. 3.

0.2 0.2 Gross Tritium, µCi/ml

1. 61E-l 8.SOE-2

1. 23E-l

• Iodine-131, µCi/ml 6.38E-l 7.09E-3 7.19E-2 I-13.l/I-133 0.6822 _ __I 0. 4 796 O.S904 I

t~7 L.=-ydrogen, cc/kg

. 4.8 27.1 I

l J_,ithium,

• p!Jm 2.lS 0.13 1.08 r

I P.oron-10, ppm +

333.8 99.2 2 ;39. s I

f O:cyg~n-16, ppm

• 4.7

.000 1.14 I

i Chloride, ppm

.OS

.OS

.OS l

G' l\\ pH*@ /.5 °C 7.02 S.39 6.22

+ Borori-10 Total Boron x 0.196 Phosphate Sulfate SO% NaOH NON-RADIOACTIVE_CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 0.0 Boron 1112 Chromate 1400 Chlorine

.e l

UNIT NO.

2 l

MAXIMUM MJ;NINUM AVERAGE

' I 2.07E-l 9.04E-3 8.3SE-2 i I

-i I 0.2 0.1 0.1

' I l.04E-l 4.0SE-2 7.90E-2 I l I

6. 79E-4 l.32E-4

3. 69E--4 f

I 0.1436 O.OSS6 t 0.0884 I

14 7.1 i

21.1

30. 3 l

I o. 38 0.2-1 0.30 I

~--.*-:

I l 116.. 8

21. 6

.000

.000

.000

.OS

.OS

. o.s 7.38 6.. S6 7.14 656

.06 0.0 Remarks:~__:U~n~i~t:_:::l~s~h~u~t=do~.w~m::........:f~~o~r:..__::m=a=i~n=t~e1~1a=1=1c=e.:.....::l=2--~1~2--~7-8_*_to_l_2_-_3~1--_7_8 __ ~~-------~-~~

• ----------------------~-------***

. DESCRTPTION OF ALL INSTAHCES WHERF.

Tif-AL--IllSCHARGE LitIITS WE~

DECEMBER, 1978 Due to impairment of the criculating water system on the following days the thermal discharge limits were exceeded as noted.

December 1, 1978 Exceeded 17.5°F 6T across station December 2, 1978 Exceeded 15°F 6T across station December 4, 1978 Exceeded 15°F t.T across station December 5, 1978 Exceeded 15°F 6T across station December 6, 1978 Exceeded 15°F 6T across station Decer.1ber 7, 1978 Exceeded 17.5°F 6T across station De.cember 8, 1978 Exceeded 17.5°F !:.T across s*tation December 9, 1978 1':

Exceeded 15°F 6T across station December 10,.1978 Exceeded 17.5°F 6T across station December 11, 1978 Exceeded 15°F 6T across station

• Indicates dates when station 6T was < l.5°F across the station for some-time during the day.

These 6T excursions were allowable under Technical Specifications 4.14.B.2.

There were no reported instances of significant adverse environmental impact.

On December 27, 1978, the temperature change at the station diE?charge exceeded 3°F per. hour while per:f:orming, Special Test ST-31.

On December 31, 1978, the temperature chan:ge at the station discharge again exceeded 3°F per hour. These changes occurred* while increasing flow through Unit No~ *1 curidenser i:..r,aterboxes and were reported as required by Tech. Spec. 4.14.B.1.

FUEL HA!WLIUG DECEMBER, 1978 One shipment of new fuel for the upcoming refueling on Unit 2 was received December 21, 1978.

~W"':'.

I

\\ '

e UNIT NO. 1 e

FUEL HANDLING DECEMBER, 1978 I

DATE NO OF ANSI NO.

NEW OR SPENT FUEL SHIPPED/RECEIVED ASSEMBLIES PER SHIPMENT

.INITIAL ENRICIDIBNT SHIPPING CASK ACTIVITY LEVI.

None during this reporting period.

L I

I I

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--~-*

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. ~...,_,_,..;, __ :, __ :'** -***-**-:.,_ -*Q*--*-**..,...,....

....*.... '. -.. ---* *y

'**'" r-H'**....... -* **.... :.,... ~-...----*---* -.

I e

e UNIT NO. 2 FUEL HAHDI,ING DECmIBER, 1978 DATE NO OF ANSI NO.

NEW OR SPENT FUEL SHIPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAI, ENRICHrillNT SHIPPING CASK ACTIVITY LEVI:~L 12 21 118.

. ' 12 LM06FT/3.l 2*. 5 mrem/hr.

\\

LM06FS/3.l 2.5 mrem/hr.

LM06FN/3.l 2.5. mrem/hr.

LM06FR/3.1 2.5. mrem/hr.

LM06FG/3.4 2.5 mrem/hr.

LM06F3/3.4 2.5 mrem/.hr.

• LM06FH/3.1 2.5 mrem/hr.*

LM06FL/3.l 2.5 mrem/hr.

LM06FP/3.l 2.5 mrem/hr.

-1 LM06ET/3.l 2.5 mrem/hr.

LM06EW/3. l 2.5 mrem/hr.

LM06FJ/3.l 2.5 mrem/hr.

• • I I

• ~tf.~'

~--CC..:R.:::.EIJ..:...'.ISIONS THAT CHANGED -

HODE DESCRIBED IN THE F-DECEMBER, 1978 There were none during this reporting period.

,. DESCRI92N OF PERIODIC TESTS WHICH WI~Rh COHPLETED WITHIN THE TIME LINITS SPECIFIED IN TECHNICAL SPECIFICATIONS DECEHBER, 1978 There were none.during this reportin,g period.

• ~

~zJ-INSERVICE INSI'ECTIOH DECEMBER, 1978 An Eddy Current, Gaging Inspection was performed in Unit Ill A,B, arid C Steam Generators in accordance with VEPCO NDT Procedure 14.1.

Eddy current inspections were performed at lOOKHZ and 400KHZ using.650,

.610 and.540 probes.

As a result of the eddy current inspection the following number of tubes were plugged:

A Steam Generator B Steam Generator C Steam Genera tor*

75 69 114 Due to leaks, eight (8). previously plugged tube ends were repair welded in 11A 11 Steam Generator in accordance with.approved Westinghouse procedures.

-*:...24-

_!{.J,RTABLE OCCURRENCES PE1Z°IAINING 'f' ANY OUTAGE OR PO\\-lER REDUCTIO, DECEMBER.z 1978 On 12-11-78, a tube leak in Uni-t 1 11 C 11 Steam Generator was determined to be of such intensity that unit shutdown was required.

LER-78-047/0JL-0

• was **submitted covering the details of this event.

/

Uaintenance of Safety llelated~stems During Outage or *Reduced *Pm1er 'Periods*

UNIT ill Mechanical Maintenance

DEl'f=N.'XH 11 JAN 7g *

?. :119 PM Uf;JT1-UtArNTt:NANCE OF SAFSTY RE[,AT8D SYS1't:MS' DURING OUTAGE 'au REDU1.'E'f) !'OWE[( PE:RIOUS) fr'f.'T S& !IV DT SYS COMP MA!iKNO

SUMMARY

WKPSHF u

MR 1'0'I'WNT/.f 1//00/7~

Ff.{

V /l[,V!l n.'v111°P, RE:PACK.

Rf1'PACK8/J VA[,VE.'

1 80A1f;150B 3

1?./Q0/7~

HI VALVS FCV-lliAR REPACK VAf,VE RBPllCH.li'D VADVE:

i qtl ?00q06 3

12/13/7D

• NS VALVB 1 MS-11q RBPACK. VAI.VE RE:PACl(f.D VALVE.'

1 812051/.22 9

12/13/70.

SYl.

V 1iLV&

1-SW-115 RE.'PLACE STEM WITH STAifv'f,fi:SS 1 1/?.

R8PiACil'/J STP:M 1

O.J 20fi11'10 7

12/13/7~

E'..!

VADV&

1-EW*-131 ii'f,'P[,ACE/J sn:M W.T'l'H S1'A.TNLRSS 2 RE Pf.Ace* VALVE S'l'ISM i

~12061230 7

12/13/7° SI~

VllLVE 1'-P.1'*-116 RE:PLACf..STEM fl!TH STAINLESS 2 Rl'.'PlllCf.D STEM 1

81?.0!01?.SS 7

12/13/7q E'rl VAf,Vt:

1.. Elr*-171 R!iPDAC:F. STEM rnrn STAINLESS 2 Re'PLllCr:D S1'b'N 1

8120fi1302 7

12/13/B s:v.

VAlVE 1-BW-1/.1 fi'T::Ff,ACE 81'1!:/.1 l,T.[TIJ S'l'/J.rN[,f:,'SS 1 1/2 REPMCE 81'/i,'M 1

'l120Gl305

.1 12/lli/7° 8\\'

VAlVE 1-sw-1rio RE:CLACE 81'6?1 WI1'11 8Tt1.UIU:SS 1 1/2 R6'Pf,AC6' S1't:N 1

B121J61315 33 12/111/7~

f!,{

V l]T,V E 1-8!?-170 HE'l'f,ACIS,'}'J"f,'N W['!'!/ S'l'AJN/.,/*:ss 1 1/2 IN RF:Pl/IC/i,'/J S'fEM 1

?12131532 2

1?/14/7q Sil VAT,VN 1 *Sf./*17:l lTE.'PLACi!,' 8'/'il'M frl7'1! S1't1INDES8 1 'J./2 IN Rlll'!,AC 11'/J,S'J'BM 1 P.1"131!;33 8

e 12/11.1f7q Sf{

VA/,V8' h%'"1~1J VALVE DlsC MJ88Jf/(]

RBPL.4CE SI'6'N+DISC 1

8121315115

~

12/1F./7~

Cl!.

v A/,liS icv-1111;on..

BODY TO BONN6"f GASl<.6'1' LlW<.

lltPUAC6'D FJONNF:'l' AllD LOltb'R GAGE*GASKb' 1 *eoF.271311 2fl 12/lF!./7~

RC Vt1DVE PCV-1'1SSA JN[;pgr;1* ANIJ R8PAJ R Rl'.'NEWt:D GAGE llrlD LOl-II::R f!I,ArmE GASl(J1'T 1

81? 1/.1101 St:

12/1Fo/7?, *.nr; VAirn 1-l/C-71

.C WUP l1F./,1Et' UNF: ISOLAY'WN R!IPAC/i.F:D VALVE,'

• i 9.12131520 7

12/17/7~

Cll V Al,VE 1-Cl/-Ql!

VADV[;; IJH'FlCU[,'l' TO OE'8h'A7'1','

REPLAcrm BONN6'T 1

0.070115'.23 1

. i2/17/7~

RC VAL.Vb'.

PCV.. 11156 V11[,VE DT::AK.S 1'1/RU 13ADDY REPAIRl','U V AlVE IN1'eliNAlS 1

81/.051215 Ell j') /17 /7q HC VAJ,V t PCV-14SSC V ADVE [,l','/l/(S 2'/IRU RE'PDllCW GASKETS LAPP[!,'/J SAT FOR 100 1

~.\\2051215, 611 12/17/7Q, RC EG 1-liC-E-111 Rflf.fOVE~Rl\\lNS'l'A[,f, 6 INCH llANDHOl.,8 Rl>NOV/i'/J AN!J RB.TN:l'J'A[,[,!W 6IN I/AND 110[,

t P1'.i'121125 12 i2/17f7q Cl!

VA/,Vt:

1 CIJ--31'1 REP/;CK VAlVli' RE'MOVED 0[,D PACKING ANU RSPMCb'/J 1

81?131022 p

12/17/'i~

li'C VALVE 1-RC-45 RB,'PACK V/lf,VS Rt.'PACKE/J VAlVE 1

81J1 'J1D:~2

?.°o I

1?/1°/n Cl/'

VADVli' 1-Cll-297

[,EA/(S 'l'/llW REPf,ACl:,'IJ VALVE 1

~or.,noqoo 51

{.,,:)

1'//1°/7~

Cll VAL.VE 1 *Cfl.*300 VALVE [,EAKS THRU REl'lAC t:D V Af,V E 1 RO!;;i1oqo1 5<i

°'

I 12/lq/70.

C/f VA£Vll 1-CIJ--2<Jt1 VALVE UiAl<S TllRU inili'N 8/WT TIGHT RBP[,!1C/','/J V11LV!'.'

1

~or.nd802 51 17./10./7~

Cl!

VA[,V/i,'

1-cu.,3q2 IJACKJNG LEAK lff,PAC.rnD 'V A&V/:,'

1 eoqo32300

• 2 12/l~f7q HI V AWE r:cv.. 111qo h:PACl<.-C!IECK FOR ST/:,'M lo/EAR Rb'f.'[,ACIW S1'l'M AND PACKING RING 1. ~1.1:!51215 151 12 /10./7~

HI VA£Vt::

FCV-1'17'3 Rl\\'PACK-CIJEC/( !:'OR ~;,pg,1i WE:A°R RllPLllCEQ STEN AND PACKING RING 1

q1:t251216 151 12/1q/7a, CH VADVE FCV-112?.

V/llVE STICKING

.Au.rusn;;o l'AGKlflG 1

~120P,OQ25 3

12/1P/7P, Cl!

PIPING FE 1122 W1lKS ON/-; DROP E'V8RY I\\ SECONDS CHARG~: hex G1ISK8T CTIGHTEN'fi,'D) 1 912l11'15'1 3

12/1 ~/7~

HSS SNU/JBER Pb'HF'ORN Pl'. 3?A+Pl'. 3°8 VISUA[, JNSP COf.1PU'1'ED VISUAf, INSN:CUON 1

P.1/'121036 1112 12/1a,17q NS V Af,~E 1*NS*-81 R,l!.'PAC/( VAlVll lil.IMOV/l:/j OLD PACKING REl'LACED WITfl :NE 1

qi21111423 7

12/1°/7q MS VAT,VE 1-NS-75

'Rfll'ACK VADV/i,'

NE11UVW OLD PACKING RF.l'lACffD ~'IT/I NE 1

Pj 2111111/.lj T

. 1'2/1°/7q MS VAlVE PCV-MS-114 i:-'ACK.IF/r; r,r:A/( N04 S'i'OP Bi'PASS HEPACKt:V VAf,VE 1

813 ?1.0733 11 e

1'J/ 1°/7~

RC SG 1-RC-E-18 l/b'MOVE'+R/':.!NS2'ALD fi lNCfl llA:VDflOLF:

liE:ftiOV E:D Ail!J IN.~']' ALM,'U 1/.11/IDllO LE COVER 1

812121126 llA 1?/10/?P.

/IC VADVS PCV.. 11155C SO[,E:NOJU ON l'CV-1'155C BDOf./S AI.'? BY Rff PLACISU VALVE ASSYS 1

A1/.1q0230 13

. 12/1'~/7~

RC VtlDVl.i' PCV-1456 SODF.NOJD ON PCV-1'~56 BWWS AIR BY RF:Pf,ACE/J VALVF,' ASSYS 1

e1nqo231 13 17/20/7q BR PUMP

. 1-lJR-P-O ANNUAD PMS NMP.. P.. G*-012 COMt'U'1'il'U ANNl/Af, PNS 1

811271026 455 12/20/7~

RC SG 1.. l/C*E-1C Ti'f,'MOVl~->f?f,'Pf,ACE SECONDARY M.4/IWAY

//f,'MOVW + REP/,ACBU :11/INWAYS 1

Pi?.121130 101 12/21/7° RC SG 11/C-E-1G Rr,'NOVE /IND Rli'INS'l'ALD 6 INCFI IJAND/JOLE

[(f,'.lfOVC:/J+l//':lNS'I'A[,[,F,'/J f/JlNDl/0[,E COVERS 1

81212091.3 35 12/?.1/7A SI MOV MOV*-1°G**A IJOUY.TO 80.VNJ..:1' LE1IK Rl:.'P[,,jcsu IJONNET GASKE'l' Ai'//) l'ACKIW 1

8121'!1230 72 12/22/7q CH VALVE LCV11l60/3 SO[,ONOID VAf,VE' LEAKS 8/IU[,Y INS1'Af,(,F,'/) m::r BOLONOl D VALVE 1

qor-:2201115 129 12/?.2/7q IA COi'f PRilSS 1-Iil-C-2A CliE'Ch. Of'E:RATION AND REPAIR CHANGIW OUT e'N1'1RE COUP 1

811251210 2111) 12/22/7q IA CONPRP.SS 1-IA-C-213 CHb'CK OP/i'RATION AND REPAIR OV.&,'fUl11U£/W CONl'/le'SSUR 1

~11)51211 10 12/22/78 Frr VAf,VE 1-~JOV-l*Y-151 MOV-t'iV-151C IIAS PACKING u:Ak IN81'/lf,f,f,'V NeN P11CKlNG 1

0 121110713 10 12/22/70.

Fl./

VALVE f.JOV-FW-151E PACKING LF.AJ;.<;

lNSTAU):D NF.Ir PACKING 1

81?1'11007 1?

1?./22/70.

F'..!

VA[,V/i' NOV-E:Y-151F PACK.ING U:11KS lNSTllUE.D Nb'fol PllCKJNG 1

A121'1100P.

15 1'//2?/70, SI Pl !'ING SI 0,3 -152 DISC FiANGE U:AKS ON B [,/JS 1 PUNP

. R6'PLAC6'/J /!'LEX GASKS1' 1

?1/.:tll:l?.32 26

\\..,

UEFT=i*ff,'C//

RbTSE:lil'DT Si'S CO/.IP 12/22/7~

Cf{

12h3/7q Cf/

12/7.3/7° C!i 12/77 /7.q Rf/

1//27/70.

SI D/2°/78 NS 1?/2~/7° NS 12/2°/7q

/.IS 12/?P./7° MS 12/7. 0 /'iq NS 17./?~/7g NS 17./2°/70.

MS 1?/2°/7q

/IS 17./2q/78 SI 17/? 0 /70.

fl./

17.f?a/n MS 12/2?/7°.

MS 12/2q/7q NS 17./2°/70.

i!BS 12/n/?R R!-1 17./2°/?g RC 12/'J'>./70.

RC 12/30/7~

RS 12/31/70.

RC 17./31/70.

RC 12/28/78 cc VAI,VE V!:J,VE VAJ,VE MO\\'

V AI,V e V AJ,V E VA[,Vf.

VA!,Vll VAI,VE VM,VE VALVE:

V llI,V E:

VAL,Vt';

V /1[,Vt:

PIPING VALVE Pll'lNG PIPING Sll/J/3MRS NOllI'l'OR VALVE VAJ,VE PUNP SG SG PUMP DEPT. TOTAL UNITl-NAWTENANCE OT! SAFF:TY R/SiATIW SYS1'EMS WRING OUTAGE OR' Ht:DUC/S'I POWER PERIODS)

N/IR!(NO MOV-13)D l/CV-131011 1-C// 1.tO NOV-R//-1700 1*-SI- 0 5 1-NS-379 1-11S-:tt1C>

1 NS-209 1-MS-:tSR 1-MS-PO 1.. MS.. 266 1-.'!8*711 1-Ms-1113 1-Sl-79 1-Sl-l*E' *1A 1-118-145 RN-GW-101 1-ilCV--14SSA 1-HCV-145SC 1-RS-P**lB 1-fiC-E 1B 1-RC-E-1C l-CC-P-2B SUM11AfiY PACKING LP.AK SOLENOID wnr, NOT OPERATE STb'M S/~l'A!r'ATSD PRON DJllPllR1W INSPECT A/ID Ri<,'PACK BODY TO BOi>Nlff STU/JS DE'l'ERIOATEIJ Rt;P11CK l' A!,V/S PAC!WiG [,EAK RL'FACK VA£VE llfl'11CK VA[,VE m:PACK. VALVE R8P11C K I SO[, FON DRAIN Rl'.'PACK VALVE RP.PACK VALV/\\

BODI'

~l'O BONNE1' S1'/JDS DETE'RIOATED.

Sh' LISAl<S INTO CC !IF.AD 7'K.

BODY TO BONNET ANIJ PAC/WIG Ll'JAK E'M!IGE: f,f;/if(

INS1'1ll,L MS L.TNE BWCKS FOR HYDRO COf/DUC'P SNU/3BER VISUA[, INSPECTION LOW T![,Of-1 Cl/AllGE SOI,ENOID CIIANGE SOL,t.'NOID OPI'ICAT,[,Y Al.lGN PUMP

£1/i.'/10V8/INSTALI, PRIM NA1Vf.IAYS R8MOVE,'/INS1'AL[, PRIM MAfMAYS EXCESS SEAL LEA!v\\GE f./KPt:RT!

REPlACED PACKING JNSTADT,W NEW SOLE'NOI:J 118l'LAC6'/J Sl't:M+DI APJ/ARGM Rf.'PAC/(JW Hll'PLACt:D STUD AND GASl<E1' li'EPACKIW VADVE' Rb'PACl<F-:D V Al VE REl'AC KF.D 11 A!,VB:

HEl"AC/iSIJ VAWE REP1ICl<ED VADVE REl'tiCKr.'IJ VAI,VE REPACKIW VA£VE Rb'PACKE.D I/ A!,V8 Cl/ANGf,'D GASKF.T llE'l'Ail!ED LEAK REPACKW !IND REPAIRfW BONNET U:AK TIGHTENED nANGb' INS1'AJ,[,ED llND RF:MOVEIJ CONPU'7'EIJ VISUA!, INSP@CTION REPl/JCE:D PUMP f./IT/l SER 775 REPlACEW SOU'NOJD REPDACED S0[£NOJD OPI' IC AL[,Y ALIGNb'D PUMP.

COMPD6'1'ED INSTA!,LED NANl~AYS REPLACED MECH SEAL u

MU

'J'OTDJ-INT.'*f 1

111221on10 1

0.12161?.52 1.Pj,217?.000 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 Rl:t?.51?20 R121 'll ?.27 R112P.l055

?11?.S1057 91J.7.P1155

. P.11?R:,159 R112P.1205

~1.12~~/.:1.0 gll/81305 q11(.814:?0 P.12).'11126

?122111345 0 11/qlQSF; 0.11?.Rl1115 Rl/1310?0 812171111.5

~1/.1P.0!'00

~17.?.~:tt100 B12?.81 1i02

~0'!07 l!iOS 1

P.121.112115 1

P.1"111320 1

81225.1300 7

25P, 27 171 107 3'1 311 2'1 311 33 311 4

3ll 1?.~

47 Q

t1 3R5 2B 2

23 23

'137 1120 3g7 26 I

N I

--..... /

" ~

f:-

( Maintenance of Safety Related Systems Durino Outage or Reduc~d Powet Periods UNil' f,12

• Mechanical Maintenance

UEl'I'=Hf\\1,1/

UN.P/'2'"

I

\\MMN'l'ENANl'P, Of SAFE.'TY Rl'.'f;,1'/'f<:f) 81'81'81'.f.'.I /JUU!N(J OUTAGF.' 01\\ RISVUCi;'IJ POfJt*:J? /Wlt'lODS)

RE;TSflRVV1' SYS COMP MllRKNO 8Ul*111ARY liKPERF l2/'J3/7° Cli VALVE

• 2-C/J-3111 PACK.rNG LE11K TIEPACK8D VIII.VI!:

DE,Pr TOTM, 11,l/iN 7"

• 2:59 FN PliU/1 1 u

MR 1'<J1'/Jl.'N:l'/.I 103 103 I

N l.D I

Maintenance of Safety Related Systems During_

Outage or.Reduced Power Periods UNIT tf l Electrical Maintenance

/

UE!'7'=E:LEC RETSEHVIJT SYS CO/IP

.12/0u/70 Ff.I CON1' 17./1~/70.

RS com*

1?/1~/70.

/i,C:

COflT 12/22/70.

Cl/

. COllT

.12//.2/7P

/IC p/.fl' M1'11 12/2?./7~

RC PNP M'TR

• 12/22/7P RC

.fOTOR 12/2F./7~

BS VA[,VE TJi:.'PT TO.TM, UN.IT1-

• .NAJNTF.'NA!ICEOC' SAFETY llF.[,AT/i:D SYS1'W*.1S DUUING OUTAGE 011 RF.DUct:v POIVl-:R T'S/1.WDS) f*IARKNO SUNN ARY 1./KPEHI!'

FCV-111Qq CHECK.C:Ol.ENO.WS nsn:D sAT

[,S~RS-100C UP ALARM S!v LEllKING AHOUND TREADS S'../ITCll OPERM'TONAL LS-RS-100D LO [,P,'V sr~ /JOE:SN'1' OP LOCAL IND L.ZGHT llE/"1!1/'D MICHO SW.l1'Cll 11AKF:llP MODE CON!/0[,LE;R OFF PIX Sll'f 1-RC-P-18*

BRIDGE l'I CUli'VE OTL Slli\\!P£E PI llND OJ[, IS SAJ'ISFAC'l'OTIY 1-TIC-P lA IJEiIDGE PI CUHVE GIL S1li.f/'Lli,'

PI AND OJL SllTISFACTORY 1-RC-P-lC BRIDGE r.r CUHVE OIL St:."4PLE PI Nm OIL SAT.lSFACTORY TV-SS-10F.A WHL N01' SHUT FRON COiJTROL ROON AD,JUS1'E/J LIMITS lf Jiili 79 "

2:'1'1 P,'J u

MR 1

R:l20~1332 1

012150720 1

R:t/1S0721 1

?.070"0500 1

8.11131507 1

0.1113150g 1

Rl.1131510 1

817.1C!0013 7'0'/'IMN1'.'f

~

?O.

20 38'1 11 200 200 200 157 46L19 I w f-'

I

(..

-(:-

~--

c Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT {f2

. Electrical Maintenance

\\,, __.* Electrical Ma~ntenance UNIT 2 There was none during this reporting period.

.~

.... J.**

(

( Maintenance of Safety Related Systems During Outa 0 e or Reduced Power Periods

~~-~'--~~~~~-

UNIT f,!l Instrument Haintenance

. /Jf,Pf=If/S]'

i RSTSERVUT Sl'8 CO/.JP I.

12/0q/7".

Cl/

.rrit.r 12/00/7"..

HI CON1' 12/0a/7° fit' CVliT i2/1?./7q Rii IllST 12/15/7~

RC.

VALVE 17/1°/70.

RC INST D/20/70.

Hi.

CON1' 12/20/79.

C:r' CONT 12/7.7 /7~

CF/

INST 12/27 /B CF/

INST D!-Pl' TOTtl[,

I IJ JllN 79

• 2:110 PN llNl1'l~

• UIAlN1't::fiAllCl!J (jf;' SM'E}'f'/ m~£An'l) llYB2'/1f.!S VUU!f{G OUTAGE' Oft /UtfJUCl!:D l'IJl-lmi PE'lllf)f)S)

MARkNO FCV-it?.2 FCV-11JCJ?.

FCV-:1.118~

't'R-1-6611 PCV*11\\55A LI-1-461 HGV -Fff-15 SB PCV-14<:iR PI1153 Pl-1152 SUMNARY CONTRO[,Lf:R is iIUNTING REPAIR CONT/f.0[,S AFTt:I? i1F:C/I REPACK Rf,'P/ilR CON1'ROLS tlF'I'ER Nl','C/I REPACK.

m:EUS C11l..I/Jflli1'JON OR R&PAIR EXC8SIV f,' nor*

PZR a;;ver, TRtlN[O,'.JJ1'TER FITTINGS [,EAKING tlT.lSO[, VALt'E+RF:G AIR [,5111<.. A7' Fn'T!NG 1'0 R/','GULATOEI DISC PiiHSSIJR/',' GJlllGE Ftl!Lr:D ON C PUMP Rb'P[,ACE GAGE lvKPb'RP u

UR. T01'lWt/T,"1 VALVE IS S1'ICKING 1

~113.011115 CHECK/I'/) T/JE CONTRVLLE!i FON OPENA1'ION 1

812081330 CHc'CKlm THE CONT!Wf,[,ER FOH OPf.RA'I'lON 1

Pt20R1331 INSf/il,T,EU NflW /(I'D EJ,El1fl'N7' 1. 81005163'1 VADVE OV8R/IAULF.D AUD S'J'ROKE ATUUS1'P,/) 1 P.07.l023'!2 RtlN 2. 3 SA1' 1

Q17.POIJ.35 TIGlf'l'llN&D F17'1'TNGS 1

~12B0°1S TIGHnNED FITTING 1

R1./1S0917 CAf,IBHA'J'l!:U G1li!GE 1

?,12130730 CALiiJ/IATE,'U GAi/GP:

1

~17.7.10 17 1£q

.7 7

1320 3774

. 17 22

.22 11'!

11~

I w Vl

. I

). Maintenance of Safety Relate<;l. Systems During_

• Outage or.Reduced Power Periods UNIT 112 Instrw:;:ient Maintenance Instrument Maintenance UNIT 2 There was none during this reporting period.

.. HEALTH PHYSICS DECEMBER, 1978 There was no single release of radioactivity specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20.

There were 5 individuals who received single radiation exposure spec:..fically associated Fith Unit f.11 Outage, which accounted for more than 10% of the allowable annual values in 10CFR20.101..

PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR SAFETY AND O?ERATING COHt1ITTEE AFTER TIHE LIHITS SPECIFIED IN TECHNICAL SPECIFICATIONS

• DECEMBER, 1978 There were none during this repor'::ing peridd.

\\.