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Monthly Operating Repts for Nov 1979
	ML18136A285
Person / Time
Site:	Surry
Issue date:	12/04/1979
From:	Costello O; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18136A284	List: ML18136A283; ML18136A285;
References
	NUDOCS 7912140338
	Download: ML18136A285 (43)
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VIRGINIA ELECTRIC Ai.'ID POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 79-11 NOVEMBER, 19 79 APPROVED:

MANAGER

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Section

Operating Data Report - Unit /11 CONTENTS Page 1-Operating Data Report - Unit #1 - Corrected Copy Month of October 1a Operating Data Report - Unit /F2 2 Unit Shutdowns and Power Reductions - Unit #1 3 Unit Shutdowns and Power Reductions - Unit #!-Corrected Copy Month of October 3a Unit Shutdowns and Power Reductions - Unit /12 4 Load Reductions Due to Environmental Restrictions ~ Unit 11.1 5 Load Reductions Due to Environmental Restrictions Unic /J.2 6 Average Daily Unit Power Level - Unit #1 7 Average Daily Unit Power Level - Unit /12 8 Summary of Opera.ting Experience 9 Amendments to Facility Lic*ense or Technical Specifications 10 Facility Changes Requiring NRC Approval 11 Facility Changes That Did Not Require NRC Approval 11 Tests and Experiments Requiring NRC Approval 12 Tests and Experiments That Did Not Require NRC Approval 12 Other Changes~ Tests and Experiments 13 Chemistry Report 14 Description of All Instances Where Thermal Discharge Limits 15 Were Exceeded Fuel Handling 16 Procedure Revisions That Changed the Operating Mode Described In 19 The FSAR Description of Periodic Tests Which Were Not Completed Within The Time 20 Limits Specified In Technical Specifications Inservice Inspection 21 Reportable Occurrences Pertaining to Any Outage or Power Reductions 23 Maintenance of Safety Related Systems During Outage or Reduced Power 24 Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 26 Periods - Unit #2 - Mechanical Maintenance

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Section Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance J

}>age 29 Maintenance ~f Safety Related Systems During Outage or Reduced 31 Power Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced 33 Power Periods - Unit #1 - Instrument Maintenance Uaintenance of Safety Related Syst2m.S During Outage or Reduced 35 Power Periods - Unit #2 - Instrument Maintenance Health Physics Summary 37 Procedure Deviations reviewed by Station Nuclear Safety and 38 Operating CoII!Illittee after Time Limits Specified in T.S.

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OPERATING DATA REPORT DOCKET NO. sc~2ao DATE 04 D~C 79 COMPLZTiD BY O.J. COSTELLO TELEPHONE 80~~357~3184 OPERATING STATUS

1. UNIT NAUE SURRY UNIT 1 .

2o REPORTING PERIOD 791101 TO 791130 3o LICENSED THERMAL POWER (MWT) 2441 1------------------------,

4. NAMEPLATE RATING (GROSS MWE) 847.S !NOTES I

5. DESIGN ELECTRICAL RATING (!iET MWE) e22 I I 60 MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) e11 I I

7. MAXIMUM DEPENDABiJE c APACITY (NET MrvE) 775 1--~--~~---~----~--1 80 IF CHANGES OCCUR IN CAPACITY RATINGS NIA (ITEMS 3 THROUGH 7) SINCE LAST -**.

REPORT; GIVE REASONS 9o POWER LEVEL TO WHICH RESTRICTED IF ANY NJA 9

(NET MWE) 100 REASONS FOR RESTRICTIONS 9 IF ANY NJ.A THIS MONTH YR~Ta~DATE CUMULATIVE 11e HOURS IN REPORTING PERIOD 120.0 eo1e.o soe4o.o

12. NUMBER OF HOURS REACTOR WAS CRITICA~ 120.0 2605.7 38305.e 13;~REACTOR RESERVE SHUTDOWN HOURS o.o 3500.9 3500.9 14., HOURS GENERATOR ON.,LINE 720.0 2600.1 37459.0

15. UNIT RESERVE SHUTDOWN HOURS o.o 3504.6 3504.e 16~ GROSS THERMAL ENERGY GENERATED (MWE) 1748073.0 6270436.0 86626389.0 17 GROSS 'ELECTRIC AL tNERGY GENERATED (MWB)

& 567000.0 2020220.0 28327803.0 180 NET E£ECTRICA~ ZN'E:RGI GENERATED (MWH) 539327.0 1919679.0 26891398.0 190 UNIT SERVICE FACTOR 100.0 o/o 32.~ oJo 61.6 o/o

20. UNIT AVAILABILITY FACTOR 100.0 ojo 76.2 o/o 67.3 o/o 210 UNIT CAPACITY FACTOR (USING MDC NET) 96.7 oJo 30.9 o/o 57.Q o/o

22. UNIT CAPACITY FACTOR (USING DER NET) 91.1 o}o 29 1 o/o 0 53.8 o/o

23. UNIT FORCED OUTAGE RATE 0.0 E7.5 o/o 24.E ojo 24a SHUTDOWNS SCHEDU~ED OVER NEXT 6 MONTHS REFUELING JUNE 1~ 1980, e WEEKS (TYPE,DATE~AND DURATION OF EACH)

25. IF SHUT DOWN AT END OF REPORT PERIOD~ N}A ESTIMATE DATE OF STARTUP 2E. UNITS IN. TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION)

INI~IAL CRITICALITY INITIAL ELECTRICITY COMMERCIA~ OPERATION

-la~

.OR!tCTBJ mPY FOR fDNTH OF OCT ...

1 1

'" OPERAT.G DATA REPORT DOCKET NO. 50~2ao DATE 27 NOV 19 COMPLETED BY O.J. COSTELLO TELEPHONE 804~357~3184 OPERATING ETATUS

~---- -~---~

1. UNIT NAME SURRY UNIT 1

2. REPORTING PERIOD 791001 TO 791031

3. LICENSED THERMAL POWER (MWT) 2441 1------------------------1 4~ NAMEPLATE RATING (GROSE MWE) 847.5 INOTES I

5. DESIGN ELECTRICAL RATING (NET MWE) 822 I I 6~ MAXIMUM DEPENDABLE CAPACITY (GROSS MWE)* 811- I f*

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 775 '--~---~-~~~-=-=-------!

a. IF CHANGES OCCUR IN CAPACITY RATINGP NIA (ITEMS 3 THROUGH 7) SINCE LAST REPORT~ GIVE REASONS

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY N)A (NET MWE) 100 REASONS FOR RESTRICTIONS, IF ANY NJA THIS MONTH YR~TO~DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 745.0 7296.0 60120.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 172.i 1885.7 37585.6

, 13. REACTOR RESERVE SHUTDOWN HOURS 572.9 3500.9 3500.9

~14. HqURS GENERATOR ON~LINE 168.4 1880.1 "36739.0

15. UNIT RESERVE SHUTDOWN HOURS 576.6 3504.6 3504.6

16. GROSS THERMAL ENERGY GENERATED (MWH) 362746.0 4522363.0 848783~6.0

17. GROSS.ELECTRIC.AL ENERGY GENERATED (MWH) . 118 06 5. 0 1453220.0 27760803.0 18 ~ NET ELECTRIC AL ENERGY GENERATED (MWH). 112088.0 1380352.0 26352071.0

19. UNIT SERVICE /ACTOR 22e6 oj@ 25.8 o/o 61.1 o)o

20. UNIT AVAILABILITY FACTOR 100.0 ojo 73.8 o/o ee.9 ofo

21. UNIT CAPACITY FACTOR (USING MDC NET) -19.4 o).o 24.4 ojo. 56.6 ~1°

22. UNIT CAPACITY FACTOR (USING DER NET) 18.3 o)o 23.0 o/o 53 3 ojo 0

23. UNIT FORCED OUTAGE RATE 77.3 o/o 74.2 oJo 25.0 ojo

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS REFUELING, FEB. 6 WEEKS~ SNUBBER (TYPE,DATE,AND DURATION OF EACH) NOV. 20s 1 WEEK 2 5. IF SHUT DOWN AT -END OF REPORT PERIOD, NIA

. ESTIMATE DATE OF STARTUP

!26. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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OPERATING z9A REPORT DOCKET NO. so~281 DATE 04 DEC 79 COMPLETED BY O.J. COSTELLO TELEPHONE 804':.'357!73184 OPERATING STATUS L UNIT NAME SURRY UNIT 2

2. REPORTING PERIOD 791101 TO 791130

3. LICENSED THERMAL POWER (MWT) 2441 ,-------------~----------!

4. NAMEPLATE RATING (GROSS MWE) 847.5 !NOTES I

5. DESIGN ELECTRICAL RATING (NET MWZ) -......

s:l"" l* I

e. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) 811 I I

.1 *. MAXIMUM DEPENDA:BLE CAPACITY (NET MWE) 7 75 '---- __.:______ 1

8. IF CHANGES OCCUR IN CAPACITY RATINGS N) A (ITEMS 3 THROUGH 1) SINCE LAST REPORT 'P. GIVE REASONS

9. POWER LEVEL TO WHICH RESTRICTEDs IF ANY N)A (NZT MWE)

10. REASONS FOR RESTRICTIONS~ IF AN! N)A THIS MONTH YR~TO!SDATZ CUMULATIVE

11. "HOURS IN REPORTING PERIOD 720 .. 0 eo1e.o 57720.0 12 .. NUMBER-OF HOURS RZACTOR WAS CRITICAL o.o 81904 34499.9

.13. REACTOR RES~RVE SHUTDOWN HOURS o.o o.o o.o

,, . 14. HOURS GENERATOR- ON<: tLINE

0 .. 0 818.9 33996.2

~

15. UNIT RESERVE SHUTDOWN HOURS OeO o.o o.o 166 GROSS.THERMAL ENERGY GENERATED (MWH) Q" 0 1957906.0 79194083.0 17 .. GROSS ELECTRICAL ENERGY GENERATED (MWH) o.o 644305.0 2see8e44.0 18 .. NZT ELECTRICAL ENERGY GENERATED (MWH) o.o 611521.0 . 2 4 s. 3 .6 6 o. s

a

19. UNIT SZRVICE FACTOR o. 0 10.2 ojo 58.9 o/ q

20. UNIT AVAILABILITY.FACTOR a.a 10.2 0 /. 0 . 58. 9 o)o

21. UNIT CAPACITY FACTOR (USING MDC. NET) a.a 9.e o)o 54.9 0 I. 0

22. UNIT CAPACITY FACTOR (USING DER NET) a.a 9.3 of o 51.7 o)o

23. UNIT FORCED OUTAGE RATE o.o o.o 21.0 o/o 24 .. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,DATE,AND DURATION OF EACH)

25. IF SHUT DOWN AT ZND OF REPORT PERIOD, 5/5/80 ESTIMATE DATE OF STARTUP

2e. UNITS IN TEST STATUS FORECAST ACHIEVED (PRIOR TO COMMERCIAL OPERATION)

INITIA~ CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

DOCKET NO. so- 280 UNIT NAMI! SURRY UNIT i UATE DEC. 1, 1979 COMPLETED llV O.J. COSTELLO ilEPOllJ MOtflll . NOVEMBER, 1979 Tl!lJ~l llONI~ (804) 357-3184 I.

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DOCK El" NO.

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SURRY 1 .,_.

l>ATE NOV. 2 1,979 COMl'l.ETEll llV 0. J. COSTEL flEPOllT MOl'flll OCT. 1979 TEI.El JIONI! (804) 357-3184

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79-8 10-01-79 F 574e6 D 1 Con.tiriuation of shutdown due to Sho**

Cause Order issued by the NRC cancer ng 79-9 10-24-79 F 2* 11* 3 possible error in piping stress analysis performed by Stone & Webster.

The Show Cause Order was *modified Aug. I 22nd to allow interim operation when Ill I

required modifications are completed.

Shutdo,~n began on 3/19/79.

~"Reactor tripped on feed flow/steam flow

~ismatch coincident with lo steam genera-tor level signal while feeding steam generqtors in manual during power increas following startup.

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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.l MONTH: NOVEMBER, 19 79

.1I DATE Til1E HOURS LOAD 2 MW REDUCTIONS 2 MW MWH REASON

--*-* -- I I

I None during this reporting per od.

MONTHLY TOTAL 0

LOAD REDUC~IONS DUE TO ENVIRONMENTAL RESTRICTIONS

. UNIT NO. 2 MONTH: NOVEMBER, 1979 DATE TIME HOURS LOAD 2 MW. REDUCTJ;ONS 2 MW MWH REASON None du :ring this reportini period

MONTHLY TOTAL 0

~*-- -- - --=-

, .. ' .. DOCKET NO .280 UNIT SURRY I DATE 12':'1'lf79 COMPLETED BY 0 J COSTELLO AVERAQE DAILY UNIT POWER LEVEL MONTH: NOVEMBER 79 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWEwNET) DAY (MWE"NET) 1 751.8 16 753.e 2 750.a 17 750.5 3 755.0 18 752.3 4 757.5 19 753.5 5 757 .. 7 . 20 752.7 e 753.,8 21 751.1 7 753.5 22 751.9 a 753 .. 9 23 751.3 9 756.5 24 753.0 10 682.,5 25 752.0 11 699 .. 5 26 751.8 12 75204 27 751 .. 1 13 755.a 28 750.11 14 758.2 29 749.8 15 755 .. 6 30 752.5 DAILY UNIT 'POWER LEVEL FORM INSTRUCTIONS ON THIS FORM, LIST THE AVERAGE DAILY UNIT 'POWER LEVEL IN MWE!iNET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH P.EPORTTr 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 oj.o LINE (OR THE RESTRICTED POWER LEVEL LINE) .. IN SUCH CASES~ THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT AllOf.fALY.

DOCKE1& 50,,201 UNIT SURRY II DATE 12.1~79 COMPLETED BY 0 J COSTELLO AV?RAGE_ DAILX, VJll.X. POWER LEVEL, MONTH: NOVE!t!BER 79 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LF:VEL DAY CMWEt1NET) DAY (MWE;rNET) 1 o.. o 1e . o.o 2 o.o 17 o.,o 3 a.a 18 0.;0 4 o. (} 19 o. o 5 o.o 20 o. o 6 OoO 21 o. o 7 o.o 22. o.,o e OoO 23 OeO 9 o.a 24 o.,o 10 o.o 25 o.. o -*

11 o.o 2e o.o 12 o.,o 27 o.. o 13 o.o 28 o.o 14 o. o 29 o.o 15 o.,o 30 o. o

.DAILY UNIT POWER EEVEL FORJ-t INSTRUCTIONS ON THIS FORM, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE"INET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT...

ING MONTH. NOTE THAX BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT 9 THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100. 0 / 0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMA.LY ..

SUMMARY

OF OPERATING EXPERIENCE NOVEMBER, 1979 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sign-ficant non-load related incidents.

UNIT 1 November 1 This reporting period begins with the tmit at 100% power.

November 2 Reduced reactor power to 99% while investigating validity of secondary calorimetric data.

November 3 Evaluation of calorimetric datacompleted satisfactorily.

Reactor power raised to 100%.

November 10 At 1158 indications of gross condenser tube leakage were received in the control room (i.e., the condensate sodium recorder "pegged" upscale). Immediately, preparations were made to remove the leaking condenser waterbox from service and the steam generator (S/G) blowdown was increased to 65 gpm on all S/G's. Shortly after the waterb:ox with the highest leakage (as indicated by installed conquctivity cells) was removed, it became apparent that condenser tube leakage was not the source of sodium in the main condensate system.

An investigation of possible sources commenced and at 1350 reactor power was reduced to 90% in an attempt to reduce sodium carryover in the ,*;ain steam exiting. the S/G' s. The unit reached 90% power at 1445. At 1520 a further reduction to 75% power was .commenced. At 1610 the sodium contamination source was eliminated. The source was traced to the auxiliary steam drains and an improperly installed jumper hose. The unit reached 75% reactor power at 1700.

November ll At 0423 secondary chemistry had shown significant improvement and the decision was made to begin a power increase to 90%

reactor power. The tmit reached 90% reactor power at 0535.

Secondary chemistry continued to improve and at 0730 a reactor power increase to 100% began. At 0845 the unit reached 100%

reactor power.

November 30

Th.is reporting period ends with the unit at 100% reactor power.

UNIT 2 November 1 This reporting period begins with the unit at cold shutdown~

all fuel removed from the reactor and steam generator replace-ment in progress.

November 30 This reporting period ends with the unit at cold shutdown.

.AMEIIDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIOUS 11

NOVEMBER, 1979 e None during this reporting period.

FACILITY CHANGES REQUIRil~G

..., .. NRC APPROVAL NOVEMBER, 1979 There were none during this reporting perio.d.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL NOVEMBER , 19 79 There were none during this reporting period.

t*

e TESTS AND EXPERilfENTS REQUIRING NRC APPROVAL e NOVEMBER, 19 79 There were none during this reporting period *

. TES.TS . .AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL NOVE..~ER, 1979 There were none during i:lhis reporting period.

t ** ... :

OTHER CHANGES, TESTS AND EXPERIMENTS e NOVEMBER, 19 79 e There were none during this reporting period.

- ..Le+-

e -

-- SURRY POWER STATION CHEMI.5-TRY REPORT e .

NOVEMBER 19 79 T.. S. 6. 6 .A.11 .

PRIMARY CO~'"! UNIT NO. 1 UNIT NO. 2 ANALYSIS MAXIMDM MINIMDM. AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml 5.26E-1 3.26E-1 4. 19E-1 2. 08E-2 l .49E~4 8.72E-3 Suspended Solids, ppm 0. 1 0.0 0. 1 0. l o. l 0. l Gross Tritium, µCi/ml 1 .36E-l 7 .33E-2 4.33E-2 * *

Iodine-131, µCi/ml 2.59E-2 3. 43E-3 8.79E~3 * *

I-131/I-133 0.8301 0.2066 o.4190 * *

Hydrogen, cc/kg 40.2 - 25.7 3 0.2 * **

Lithium, ppm 1 .03 0.60 0.83 * *

Boron-10, ppm + 78.8 6 2. 7 71.5 367.5 216 244 I

.. .. .. . .. .. .. -I I

oxyg*en-16, ppm. 0.000 o.ooo 0 .000 4.0 LS 2.4 Chloride,* ppm 0.05 0.05 o.os 0.08 0.05 0.05 pH @ 25°C 6.99 6 .88 5.23 4.89 5" 10

+ Boron-10 = Total Boron x Ool96 NON-RADIOACTIVE CHEMICAL RELEASES 2 POUNDS T.S. 4.13.A *.8 Phosphate 0.0 Boron 268 Sulfaee 834 Chromate .24 50% NaOH 1.050 Chlorine 0.0 Remarks: -

Unit #2 is in cold shutdown condition RHR System refi 1led 11-21-79.

.RIPTION OF ALL INSTANCES WHER.

L D!SCllAR:GE t:t:m.Ts WERE EXCEE NOVEMBER., 19 79 Due to impairment of the circtilating water system on the following days the thermal discharge limits were exceeded as noted.

November 1, 1979 *Exceeded 17.5° b.T across station November 2, 1979 . *Exceeded l7o5° b.T across station

NoveIIiber. 10, 1979 *Exceeded l5o0° LiT across station November 27, 1979 *Exceeded 15.0° b.T across station November 28, 1979 *Exceeded 15.0° AT across station November 30~ 1979 *Exceeded 15.0° LiT across station

Indicates dates where station AT was <15.0°F across the station for sometime during the day.

The LiT excursions* were allowable _t.mder Techncical Specifications 4.14.B.2. There were no report~d insta.nces of significant a~verse environmental impact.

On November 10, 1979, the 'temperature change at the station discharge

'exceeded 3°F per hour while removing lB condenser waterbox from service

for suspected tube leakage. This event was reported in accordance with Technical Specifications 4ol4.

.i

FUEL HANDLIUG NOVEMBER, 1979 There was no fuel received or shipped during this reporting .

period.

.t'age .LI

~

' . FUEL HANDLING

" , v ...-.:n:;*1, ig7q DAIE NO OF ANSI. NO.

NEtV OR. SPENT FUEL.

tl!IPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITI.AI. ENRICHMENT SHIPPING CASK ACTIVITY LEVE None durin: this reporting period.

I I

I

-----*----* *--*-~- ----*- *~ *-- . .. .. .. ~

Page ].~

. ** E'UEI. ~..NDLING

'NOVEMBER~ 1979 DATE NO OF ANSI NO. NEW OR SPENT FUEL UPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVE I

I II None duringlthis reporting period.

I I '

I I

I

',I

l PROCEDURE REVISIONS THAT CHANGED THE

... .* OPifl:NG MODE DESCRIBED IN THE FSt'I NOVEMBER, 1979 None during this reporting periodo

n~PTION OF PERIODIC TESTS WH WERE NOT COMPLETED WITHIN THE TI.ME ITS SPECIFIED IN TECHNICAL SPECIFICATIONS NOVEMBER, 1979 The following monthly Periodic Tests were not conducted in August.

Subsequently these test have been completed satisfactorily.

NUMBER TITLE DESCRIPTION ET-24.4H Fire Protection Systems QHose Houses) To check equipment and hydrants for operability.

ET-24.8

. . _Fire Protection Systet!lS (Fire Lockers) To assure -loclcers contain:

equipment on inventory and operability of gear.

The following Periodic Tests were not completed within the time limits specified in the Technical Specificatio.ns.

PT-"38.11 Prima:ry Coolant Crud Analysis was* not completed on Unit Ill when scheduled (11-9-79). The test performs a radio chemical

. analysis of the )reactor coolant to evaluate certain corrosion products present. The test was conducted on 11-19~79, _three days beyond the 25% grace period allowed.

PT-38.29 Service Air and Breathing Air Compressor Sampling on Unit Ill was not conducted when scheduled (-5~31-79). The test is to assure the quality of air used in ..self contained breathing apparatus, respirators, hoods, and suits meets required specifications. This sem:i-annual. test was conducted on 10~25-79 three (3) months beyond the 25% grace period. When conducted, the test indicated the air fulfilled specified requirements.

. .. .* . INSERVICE INSPECTION NOVEMBER, 1979 ..

The Unit 112 radiography of the feedwater lines (IE Bulletin 79-13.

Revision 2) was completed. One weld (117) on :rA" Steam Generator feed-line was rejected (small area of reject~ble porosity). This weld was repaired and accepted. All other welds were accepted. Several of the welds on the feedwater lines were replaced as part of the S/G Replacement Project. These welds-were r8plac~d prior to the IE Bulletin 79-13 implementation in Unit #2. ~""DE information on the original w=lds was unobtainable. All new welds were radiographed to the S/G ReFlacement Project construction code in force and not to the requirements of IE Bulletin 79~13.

The monthly visual inspections required by IE Bulletin 79-17 Revision 1 (Pipe cracks in stagnant borated water systems) is in

_progress in both Units .1an,d2 * . No rejectable indications have beep.

reported at this time. The inspection is still in progresso t.*

~

DEPl'=NDT 3 DEC 79 ~ 2116 PM PAGE 5 llNIT2d.2J03)79 (MAINTENANCE OF SAFE2'Y RELATED SYSTEMS DURING OUTAGE OR REDUCED )'OWER PERIODS)

RETSERVDT sxs COMP MARKNO .

SUMMARY

llKPERF lJ MR TOTDWNTM 11)20,479 CH PIPING 3AI! CH11'106d50 BEHOVE ARC STRIKE REMOVED ARC STRIKE PERFORMED EXAM 2 9110921*15 120 U/21}79 FW PIPING 111*h'FPDd09*60 .ND'l' E'EE'DWATE:R PIPING NO REJECTABLE INDICATIONS 2 9072'10030 2856 11)21179 E'll PIPING 1'1,,lt'E'PD-117*60 NDl' E'EE'DWA2'b'R Pll'ING ONE REJECTAbZR WELD*REPAIRED 2 9072*10032 2056 U/2!/79 DEPT TOTAL E'W PIPING 1'l*WFPDd13*60 NDT FEE'WATER PIPING NO REJECTABLE INDICATIONS 2 907270033 2856 8680

"~

I N

N I

REPORTABLE OCCURRENCES PERTAINING TO

.. *. ,~ OUTAGE OR POWER REDUCTIONS NOVEMBER, 1979 There were none during this reporting period.

10*-

Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT /Fl Mechanical Maintenance.

J

. ... UNIT /Fl Mechanical Maintenance None during this reporting period.

-.26.-

0 Maintenance of Safety Related Systems During Outage or Reduced Power.Periods UNIT *tn Mechanical Maintenance

DEP'l'=MECH 3 DEC 79 "' 2116 PM PAGE 1 UNIT2"12/03J79 ,*

(MAINTENANCE OF SAFET't RELATED SYSTE.'MS DURING OIJTAGE OR REDUCED POWER PERIODS)

RE'l'SENVD'l' SIS COMP NARKNO SUMMARlf WKPERF lJ MR T01'WNTM 11/01J79 Ill COMPRESS 2..IA.Cwt OIL LEAK REPAIRED OIL LEAK 2 910221117 206 U/02/79 EE COMPRESS EOG 2 LIFT INNERSTAGE RELIEF VALVE REPLACED INTAKE AND DISCHARGE VALVES 2 905110415 29 11)02)79 PR SNUBBER 2"RCwHSSd37 REBUILD SNUBBER WITH EP MATERIAL REBUILT SNUBBER 2 905161530 11054 11/02J79 PR SNUBBER 2*RC,.HSSd36 REBUILD SNUBBER WUH EP MATERIAL REBUILT SNUBBER 2 905161531 11054 11/.02/79 PR SNUBBER 2t!HC.HSSd35 REBUILD SNUBBER WITH EP MATERIAL REBUILT SNUBBER 2 9051E1532 '1056 11/02J79 PR* SNUBBER 2'1RC*HSS*131J REBUILD SNUBBER WITH EP MATERIAL REBUILT SNUBBER 2 905161533 3213 u.102}79 PR SNUBBER. 2wRC*IISS'I0133 REBUILD SNUBBER 1112'/J EP HA2'ERIAL

REBUILT SNUBBER 2 9051615311 3213 11/02179 PR SNUBBER 2wRCttHSSd32 REBUILD SNUBBER WI2'H EP MA2'E.'i1 AL REBUILT SNUBBER 2 905161535 3213 11/02/79 PR SNUBBER 2wRCwHSSd31 REBUILD SNUBBER WITH EPHATERIAL REBUILT SNUBBER 2 905161536 3213 11)02,.179 PR SNUBBER 2*RCwHSSd30 REBUILD SNUBBER WIT/J EP HA2'ERIAL REBUIL'P SNUBBER 2 905161537 3213 11A02/79 PR SNUBBER 2..Rc..11ss..i 29 REBUILD SNUBBER WITH EP MATERIAL REBUILT SNUBBER 2 905161538 3213 11/.02/79 PR SNUBBER 2.. Rc.11ss.12e REBUILD SNUBBER WITH EP MATERIAL REBUILT SNUBBER 2 905161539. 3213 11/02)79 PR SNUBBER 2*RCw/JSSd21 REBUILD. SNUBBER WITH EPMATERIAL REllUILT SNUBBER 2 9051615'10 3213 11/Ci2179 PR SNUBBER 2wRCwHSSd.26 REBUILD SNUBBER WITH EPMATERIAL REBUILT SNUBBER 2 905161541 3216 11/0SJ79 MS VALVE GAGE.' SAFETl VALVES CO/o!PLE2'ED 2 9110111355 2 11/0E/79 FW PMP H2'R 2wE'W.. Pt!3B NO LEAK OFF 2'1/RUST BEARING+PACKING ADJUSTED 2 911042204 211 11107/79 RH VALVE 2*RHn2 DC 79*05 REPLACE STUDS WITH IJ16SS VALVE BONNET WAS NOT REMOVED 2 9102111000 160 11/07179 RH 'IALllE 2wR1/*8 DC 79~05 REPLACE STUDS WITH IJ16SS VALVE BONNET WAS NOT REMOVED 2 9102'11001 160 11/07J79 RH VALVK 2.,R/Jw21J DC 79*05 REPLACE STUDS WITH 416SS VALVE BONNET WAS NOT RE/olOVED 2 910241005 163 11/07)79 RH VALVE MOVwRHw2120JJ DC 79*05 REPLACE STUDS WITH lt16SS VALVE BONNET WAS NOT REMOVED 2 91021J1007 1116 11J.07J79 RH VALVE MOV.R/Jw2120B DC 7!!n05 REPLACE S'1'UDS WITH 1!16SS . VALVE BONNET WAS NOT REMOVED 2 910241008 1116 ......,,

11/07/.79 SI VALVE 2nSI .. 1111 REPLACE STllDS REPLACE STUDS 2 911061503 11 I 11/13/.79 cc PUMP 2.cc.F..ic EXCESSIVE AXIAL MOVEf..IENT RBDUILT l'U/.JP 2 9100023115 792 11/13)79 SI VALVE 2wSid30

REPLACF; S'l'UlJS REMOVED OLD STUIJS+REPLACED UPGRADED 2 911061502 120 11/14179 CH VALVE 2*C/Jrr263 VALVE HANDWHEEL SHEARED AND REMOVED REPLACED VALVE HAND WHEEL 2 908182105 5 11}15.'79 DG VALVE 2*00w10 REPLACE DIAPllRAGM REPAIRED VLV 2 902161003 27117 11)15,179 DG VAL.VE 2.. Da.110 REPLACE DIAPHRAGM R8l'LACED DIAPHRAGM 2 90216100*1 27'17 1111s;19 DG VALVE 2*DG.,!i0 REPLACE DIAPHRAGM REPLACED DIAPHRAGM 2 902161005 27*17 11/15/79 VG VALVE 2*DGn51 REPLACE DIAPHRAGM Rf.'PLACED DJAPllRAGM 2 902161006 27'17

11115/'/9 DG VALVE 2"VG*611 REPLACE DIAl'IJRAGM REPAIRED VLV 2 902161017 27117 11)16179 VG VALVE 211DG .. 59 R~PLACE DIAPl/RAGN REPLACE DJAPH VALVE PHOGRAM 2 902161013 2770 11h6fi7!1 00 VALVE 2"DG,.60 Rf.'PLACS DI APllRAGM REPl.ACE DI/lPllRAGM VALVE PROGRtW 2 9021610111 2770 11}161'19 11/16/7S 11/16)79 DG DG DG V1ILVE VALV8 l'ALVE 2rDG.,.12 2..Da.,1s 2wDG .. 76 RE.'PLACE DI APllRAGM REPLACE DIAPHRAGM REPLACE DI APilR AGM REPLACE DIAPllRAGM VALVE PROGRIJ.I REPLACE DIAPH VALVE PROGRAM REPLACE DIAP/J VALVE PROGRAM 2

2 2

902161020 902161022 902161023 2770 2770 2770 e

11/16/79 DG VALVE 2rDGri71 RE.'PLACE.' DI APHRADM REPLACE DIAPll VALVE PROGRAM 2 9021610211 2770 11/16179 DG VALVE 2"va.. eo RE.'PLACE DI.4PHHllGM Rf.PLACE DIAPHllAGM VALVE PROGRAM 2 902161025 2770 11/tt:/.79 DG VALVE 2.. 00.eG REPLAC"8 DIAPHRAGM 'REPLACE DIAPHRAGM VALVE PROGRAM 2 902161029 2770 11/16)79 RI/ VALVE 2wRf;.,23 INSn:cr VAiVE INSPECTED VALVE 2 90et71615 *10 11/.1'JJ79 DG VAL.VE 2~vG .. s*1 REPLAi~E III APHRAGM REPLACED DIAPllRAGM 2 90216101!1 27 117 11/20/79 Cl/ VALVE 2.. c11 .. :io9 *LE:AK.S THHU ON PT16. I! REPAIRED VALVE 2 907101130 2'1 11120/79 Cll VALVE HCV112310A REPAIR POSITION INDICATOR ADJUSTED :l 911160805 5 11/20179 C/J VALVE FCV112160 H~:FAIH POS2'10N INlllCA2'0R Rfi:PAIRED 2 911160806 5 11/20/79 CIJ VALVE llCV;i2"11 RE:blIH POSI2'IO.V ON 11/DICATOR *1 ADJUSTED 2 911160808 5 11}21/79 :JI VAT.VE 2.s.r .. 109 REPLACE S2'UDS REPLACED S-l'UO:J 2 911061501 1108 11l21J79 cc l1'iSJ'R FI 111:c.. 21aB 1Nt1'ALL fl,01/ INDICATOR REPAIRE.'D 2 9112001!21! 1 11/22/79 cc VA/,VE 2.. cc.. 9ss llALl'E l:J MISS.ING IJANDYIJEEL REPLA~ED VALVE HANIMl/EEL 2 911200821 37

\

.{

DEPl'=MECH 3 DEC 79 ~ 2116 PM PAGE 2 f/NI'r2d2/03/79 (MAINTENANCE OF SAFETY RELATED SXSTEMS DURING OUTAGE OR REDUCED POYER PERIODS)

RETSERVl11 sxs COMP MARKNO SUMMAR! WKPERF lJ HR 7'0TDWNTM 11.J2EJ.7!ll SI VALVE 2nSI .. e5 RE'PLACE S'l'UDS REPLACED S'l'UDS 2 911131015 169 11J2eJ79 Sl VALVE 2.sr.. 211a R/i.'l'LACE ~--i*1ms REPLACED STUDS 2 911131016 tee 11/26J79 SI VALVE 211Siw2'10 REPLACE S'J.'UIJS REPLACED STUDS 2 911131010 161!

11/26179 SI VALVE 2.s.r.2ii2 REPLACE S'.l'UDS REPLACED WITH UPGRADED STUDS *2 911131020 111ii un6n9 SI VALV8 2*Siw9'1 REPLACE S'l'UDS REPLACED ST/JDS 2 911131025 160 HJ26/79 SI VALVE 2*8111230 REl1LACE S'l'IJDS REPLACED WI2'H UPGRADED BOLTS+NUTS 2 911131026 1'1'1 UJ27179 11J21ns 11)27179 11)28,179 RC RC CH SI

'llALVE VALVE l'UMP VALVE 2wRC1111fll.

2.. RCd58 2wCHwPw2C 211Siw02 REPLACE STUDS REPLACE S'.l'UDS REPAIR OIL LEAK ON SIGHT GLASS REPLACE STUDS REPLACED SWDS REPLACED STUDS REPLACED OIL FEEDER REPLACED DEGRADED S'rUDS+NUTS 2

2 2

2 911051620 911051622 9112'10535 911131019 501 507 192 5 e 11J21!,l79 SI VALVE 2wSI.08 REPLACE S'rUDS REPLACED DEGRADED STUDS+NUTS 2 911131023 192 11}29J79 SI VAL'IB 2JJSiw91 REPLACE S'J.'UDS REPLACED STUDS 2 911131021 31 11}29}79 SI VALVE 2wSiw239 REPLN:E STUDS RE.'PLACB °s'IUDS 2 911131022 3'l 11/29)79 BR VALVE MOVwBRdOtB REPACK REPACKED VALVE 2 91127111113 25 12J01J79 DEPT TOTAL BR PUMP BR11PdA INLET+ DISCHARGE FLANGES.LEAK. REPAIRED 2 91127111115 26 I I N

00

,)

- I

Maintenance of Safety Related Systems During Outage or.Reduced Power* Periods .-1 UNIT !Fl Electrical Maintenance 0

3 DEC 79 ~ 2:14 PM PAGE 1 UNI'l'1w12/03J79 (MAINTENANCE OF SAFETK RELATED SYS'l'll'MS DURING OUTAGE OR REDUCED POWER PERIOIJS)

RETSENVTYf S'JS COMP MARKNO SUMMARJ! llKPERF MR 1'01'DWN1'M U/19J79 CH INS'IR DEf'ECTIVE RELAX REPLACE COIL i 9111411lli6 120 ll!ttl*'I~

DEPT TOTAL 120 I

w 0

n

0 Maintenance of Safety Related Systems During Ou~ge or Reduced Power Periods UNIT IFZ Electrical Maintenance 0

DEP.r=ELEC 3 DEC 79

2116 H/ PAGE 3 IJNIT2d2J03/79 *

(MAINTENANCE OF SAl'E1'Y RELATED SXSTEMS DURING OUTAGE OR REDUCED POWER PERIODS)

RETSENVIY.A' sxs COMP MARKNO SU/.JMAR'i WKPERF u Mil TOTWNTM 11/02/79 EPDC CHARGER 2A2 CllA'CK f'Oli INSULll7'ION DliEAK!J<MN cm:CJCED WIRING TESTED SllT 2 9052311130 llO U/03/7!!1 EPDC CHARGE 28111 INSTALL NE:W CAl'ACITORS !Nb'TALLED NEW CAPACITORS LOAD TESTED 2 910290725 100 U./05/79 ~l/ MDV HOVwSJlw2061i #IOV l'MS COMPLETED AS PER EMP1tPnMov .. q5 2 901251535 6600 U/05/79 SW MDV MOVnSW*206B MOV l'HS COMPLETED AS PER KMP.. l'*MOV"q5 2 901251536 1600 11}05)79 CH PUMP 2wCllwPd8 AUX OIL 7'11EliMALS OUT LOAD CHECKED SAT 2 909290210 792 U/06J79 FW MOV MOVwE'Jln251D MOV PHS COMPLETED AS PER EMP*l'n/.lOVwqS 2 9012511109 6504 11/111/79 CH HT PNLU..6 UN ALARM ALARM HAD CLEARED 2 911111010 26 11/14/79 CH HT PNL8w6 LOW ALARM ALANM HAD CLEARE.'D 2 911111811 26 11/19/79 Cll MOV MOV*Cllw2310 DISCONNECT FOR MECHANIC COMPLETED AS PR EMPwCnMOVn11 2 903002151 51100 HJ19J79 EPDC BA7'1' PERFORM P'l'. 23, IJAI COMPLETED E/.IP*P*EPDC1t'lll PT 23. S 2 911091*100 33 11/21179 CH MOY MOV*2310 HOV PMS COMPLETED AS PER EAfp,.p.,./.fOVwll5 2 9012511t56 6725 11/26J79 CH MOV DISCONNECT FOR MECH MOVe2286B VIXONNECTEDtHECONNECTED 2'ESTEO SAT 2 900190951t 173 11nen9 RC VALVE HCVwRCw2556C CONNECT SOV TESTED VALVE VALVE TESTED OK 2 911201331 10*1 11J2BJ79 DEPI 'J'OTAL RC VALVE HCVnRCw2551C CONNECT SOV TES'l'ED VALVE JI LV TES'J' OK 2 911201331t 1811 I

w

!'.)

I

_;I 1'" -

-- - -JJ-

9

_r1 v

Maintenance of Safety *Related Systems During Outage or Reduced Power Pe~iods UNIT Ill Instrument Maintenance 0

- , fill UNIT /Fl Instrument Maintenance e

None during this reporting period.

-~--

'. '~*

1*

d\

'd Maintenance of Safety Related* Systems During Outage or Reduced Power Periods UNIT ff2 Instrument 1-f...a.intenance

DEFJ'=INST 3 DEC 79

2116 PM PAGE IJ IJNI'12d2}03/79 (MAINTENANCE OF SAFE'11 RELA'IED SXSTEHS DURING OUTAGE OR REDlJCED POWER PERIODS)

RETSERVO'f SJ!S COMP MARKNO Sl/NMARX llKPERF lJ /.IR TOTWN7W U/07}79 RC INSR CALIBRATE PRESS '1RANSNI2"J'ER CALIBRATED TRANSMITTERS UJ21A79 Gii INS'l'R 2 911060000 30 H2"Gll*203 COMPLETE CALIDRKI'ION CAL+OP CHECK 2 9111111051 11111 11/29/79 RH INSTR FCVlllRH-2605 REPAIR VALVE REPLACED RELAX ADJl/S'.rMENT E/P 2 9112'11200 911 DEPJ' TOTAL ~***.,

2E9 I

w C\

~

- - - ___ - -HEA11'H- -PHYSICS -- --- --

4 ~..,.r .

'""!'<<,\...

fl. ~*

NOVEMBER, 1979 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.

-3~-

lJRE DEVIATIONS REVIEWED BY ST "ION NUCLEAR !~* :: .* 1--

~1 * ~ ... . AND OP.ERATING COMMITTEE AFT U!E LIMITS SPECIFIED IN TECHNiCAL SPECIFICATIONS ". l .. *""* *----*-- .

NOVfilIBER, 19 79 NUMBER UNIT TITLE DEVIATION OP-7.1 1 Safety Injection System l-SI-21 Left Closed Valve Check.off Sheet This procedure was deviated October 17, 1979 and reViewed by the Station Nuclear Safety and Operating Committee November 7, 1979.

OP-32A 1 Steam Generator Blowdown l-BD-37 Left Closed *.

Valve Checkoff System I

I. Sheet This procedure was deviated October 15, 1979, and reviewed by the Station Nuclear Safety and Operating Committee November 7, 1979.

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