Text

Monthly Operating Repts for Jul 1983
	ML20024F069
Person / Time
Site:	Surry
Issue date:	08/03/1983
From:	Jones V, Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	470, NUDOCS 8309080179
	Download: ML20024F069 (42)
	v • d • e

{{#Wiki_filter:o e e VImOINIA ELECTHIC AND POWER COMPANY HacnwoNo,VINDIMIA 20261 W.L. STEWART we).."..'S".7,S.. August 15,1983 Mr. N. M. Haller, Director Serial No. 470 Office of Management and Program Analysis N0/WDC:acm U. S. Nuclear Regulatory Cc-mission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 DPR-37 1

Dear Mr. Haller:

Enclosed is the Monthly Operating Report for Surry Power Station Unit Nos. 1 and 2 for the month of July, 1983. J Very truly yours, ] s) . L-s i W. L. tewart i -Enclosure (3 copies) cc: Mr. R. C. DeYoung, Director (12 copies) Office of Inspection and Enforcement i Mr. James P. O'Reilly (1 copy) Regional Administrator Region II Mr. D. J. Burke l NRC Resident Inspector , ~ Surry Power Station 1. l Q l 8309080179 830003 PDR ADOCK 05000280 l R PDR %F os u i

I e s e o a g VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTELY OPERATING REPORT REPORT NO. 83-07 me O ' STATION PE;AGER l l l l I i l I i l l l l \\

1,. i Section . Page Operating Data Report - Unit #1 1 Operating Data Report - Unit #2 2 Unit Shutdowns and Power Reductions - Unit #1 3 Unit Shutdowns and Power Reductions - Unit #2 4 Load Reductions Due to Environmental Restrictions - Unit #1 5 Load Reductions Due to Environmental ' Restrictions - Unit #2 6 ~ Avarage Daily Unit Power Level - Unit #1 7 Average Daily Unit Power Level - Unit #2 8 Sumary of Operating Experience 9-10 Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRC Approval 12 Facility Changes That Did Not Require NRC Apprcval 13-14 Tests and Experiments Requiring NRC Approval 15 I Tests ;and Experiments That Did Not Require NRC Approval 15 Other Changes Tests and Experiments 16 Chemistry Report 17 Description of All Instances Where Thermal Discharge Limits Were Exceeded 18 Fuel Handling 19-20 Procedure Revisions That Changed the Operating Mode Described in the FSAR 21 Description of Periodic Tests Which Were Not Completed 22 Within the Time Limits Specified in Technical Specifications 4 e l

11 ', e Seccion Pare Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 24 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 28 Maintenance of Safety Related. Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 30 Maintenance of Safety Related 5 stems During Outage or 7 Reduced Power Periods - Unit #2e-Electrical Maintenance 32 Maintenance of Safety Related Systems During Outage or 34 Reduced Power Periods - Unit i1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or 36 Reduced Power Periods - Unit #2 - Instrument Maintenance 37 Health Physics Summary Procedure Deviations reviewed by Station Nuclear Safety and 38 Operating Committee after Time Limits Specified in T.S. I l l l l l l l

OPERATING DATA REPORT DOCKET NO. 50-280 DATE O3 AUG 83 COMPLETED BY V1wlan sones TELEPHONE 804-357-3184 OPERATING STARIS

1. UNIT NAME SURRY UNIT 1

2. REPORTING PERIOD 101B3 TO 73183

3. LICENSED THERMAL POVER (MVT) 2441 l ~ ~ ~~ ~ ~ ~ ~ ~ ~ ~ l

4. NAEPLATE RATING (GROSS finT) 847.5 l NOTES l

5. MSIGN ELECTRICAL RATINS (NET WE) 788

6. HAXIMUM DEPENDABLE CAPACITY (GROSS MVE) 811

7. MAXIMUM DEPENDABM CAPACITY (NET MVE) 775

8. IF CHANGES OCCUR IN CAPACITY RATINGS N/A (ITC S 3 THROUGil 7) SINCE LAST PEPORT, GIVE REASONS

9. POVER GVEL TO WHICH RESTRICTED, IF ANY N/A (NET MVE)

10. RE'A30NS FOR RESTRICTIONS, IF ANY N/A THIS HQNTH 1R-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 144.0 5087.0 92975.0

12. NUMBER OF HCURS REACTOR VAS CRITICAL 739.8 1995.4 55907.1

13. REACTOR RESERVE SHUTDOVN HOURS 0.0 0.0 3765.2

14. HOURS GENERATOR ON-LINE 734.0 1871.1 54725.8

15. UNIT RESERVE SHUTDOVN HOURS 0.0 0.0 3736.2

16. GROSS THERM 4L ENERGY GENERATED (#VH) 1763203.7 4270026.7 126950626.6

17. GROSS ELECTRICAL ENERGY GENERATED (MVH) 558260.0 1351195.0 40957238.0

18. NET ELECTRICAL ENERGY GENERATED (MVH) 529108.0 1277817.0 38838280.0

19. UNIT SERVICE FACTOR 9817%

. ~3 6.8% 58.9 e/o

20. UN77 AVAILABILITY FACTOR 98.7%

^56.8%~ 62.9 e/o

21. UNIT CAPACITI FACTOR (USING MDC NET) 91.8 e/o 32.4 e/o 53.9 e/o

22. UNIT CAPACITY FACTOR (USING DER NET) 90.2 e/*

31.9 e/o 53.0 e/o

23. UNIT FORCED OUTAGE RATE 1.3 ele 1.1 ele 22.3 */o

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS FALL MAINTENANCE-10 DAYS-11-11-83 (TYPE,DATE,AND DURATION OF EACH)

SNUBBER INSPECTION-5 DAYS-8-26-83

25. IF SHUT DOVN AT END OF REPORT PERIOD, ESTIMATE DATE OF STARTUP

26. UNITS IN TEST STATUS FORECAST ACHIEVED tPRIOR TO COWTRCIAL OPERATION)

INITIAL CRITICALITY INITIAL ELECTRICITY COMERCIAL OPERATION t

l, UPERATING DATA MPORT DOCKET NO. 50-281 DATE 03 AUG 83 1 COMPLETED BY V1slan 3ones TELEPHONE 804-357-3184 QPE_RA"'ING STATUS r

1. UNIT NAME SURRY UNIT 2

2. MPORTING PERIOD 70183 TO 73183

3. LICENSED THERMAL POWER (MWT) 2441 l ~ ~~~ ~~ ~ ~ ~ l

4. NAMEPLATE RATING (GROSS MVE) 847.S l NOTES l

S. MSIGN ELECTRICAL RATING (NET MWE) 788

6. MAXIMUN DEPENDABLE CAPACITY (GROSS MWE) 811

7. NAXIMUM DEPENDABLE CAPACITY (NET MWE) 775

8. IF CHANGES OCCUR IN CAPACITY RATINGS N/A (ITEIG 3 THROUGit 7) SINCE LAST MPORT, GIVE REASONS

9. POWER LEVEL TO VEICH R5TRIC"IED. IF ANY N/A (NET WE)

10. REASONS FOR RESTRICTIONS, IF ANY N/A THIS MONTH IReTO-DATE CUMULATIVE

11. HCURS IN REPORTING. PERIOD 144.0 5087.0 89855.0

-12. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 4100.2 56774.7

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LINE 0.0 4061.6 5S905.7

15. UNIT RUERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. ' GROSS 2EERNAL ENERGY GENERATED (MWH) 0.0 9666490.1 130907836.2

17. GROSS ELECTRICAL ENERGY GENERATED (WH) 0.0 3087795.0 42570514.0

18. NET EECTRICAL ENERGY GENERATED (MWH) 0.0

-2927496.0'40348417 0

19. UNIT SERVICE FACTOR 0.0 79.8 e/o 62.2 */*

20. liNIT AVAILABILITE FACTOR 0.0 19.8 e/=

62.2 */e

21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 14 ~'3%

37.9%

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 73.0%

57.0% ~

23. UNIT FORCED OUTAGE RATE 0.0 1.4 */*

14.5 e/o

24. SHUTDOVNS SCHEDULED OVER NEXT 6 MONTHS FALL MAINTENANCE - 10 DAYS (T!PE.DATE,AND DURATION OF EACH) 09-23-83 l

25. IF SHUT DOWN AT END OF REPORT PERIOD, i

ESTIMATE DATE OF STARTUP l

26. UNITS IN TEST STATUS FORECAST ACHIEVED l

(PRIOR TO CO.WERCIAL OPERATION) INITIAL CRITICALITY INITIAL ELECTRICITY LCMtERCIAL OPERATION t 1 l.

~ DOCKET NO. 50-280 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Surry I

DATE Anannt 4-14A1 COMFt.ETED BY vivtan inn..

REPORT MONTir Julv TELErfl0NE (804) 357-3184 ___p a .3 ,$E 3 }Yj (.lcensee [g t Cause & Corrective No. Date k gI ,yac Event p ,3 Action to g F E j 65 Repoel #

) O 6*

Prevent Reeverence o ~ l 83-08 7-7-83 S 0.0 H. 1 Reduced power to load follow 'on orders i! of system operator i 83-09 7-8-83 S 0.0 H I Reduced power to load. follow on orders I 3 of system operator I i 83-10 7-9-83 S 0.0 if 1 Reduced power to load follow on orders g of system operator 83-11 7-15-83 F 5.9 A 3 Reactor trip caused by the loss of "B" main feed pump 83-12 7-15-83 F 4.1 A 3 Reactor trip caused by "B" S/G high I high level due to excessive leakage of "B" feed regulating valves 5 i 1 2 3 4 j F: Foeced Reason: Mellaod: Exhibit G. Insttuciluns A Equipment Failure (Emplain) 1-Manual for Pseparation of Data S: Sciwduled i B-Maintenance of Test 2 Manual Scism. Entry Sheets for Ucensee i C. Refueling 3 Autumitic Scram. Event Report (l.ER) File (NUREG. D Regulatony Restoiction 4 Other (Emplain) 0161) E-Operator Temining & Ucense Enaminathm F Administentive 5 Exhibit I. Sanw Source 4 i G-Operational Error (Emplain) l 19/77) II Other (Esplain) q I

i l n UNIT SifUTDOWNS AND l'0WER REDUCTIONS DOCKET NO. 50-281 o s UNIT NAME Surry II .DATE August 4, 1983 I COMPLETED BY vivian Jonta_- ~ REPORT MONTil Ju !.y TELEPflONE (804) 357-31s(_ l l' F l '5. 5 3 e e, -k g I.icensee Cause & Corrective 7,.g

soc Event uT i

Action to .E'E E

i No.

Daic M" f, dk vie j175g Repora # oyG u p,,,,,,g,y,,,,,,, F 8 'i 83-12 06-30-83 S 744.0 C 3 Continuation of shutdown for refueling { 'I which conenenced 06-30-03. e + a ( t i I 2 3 4 l F: Forced Reason: Meil ext: Exhibit G. Instructions A Equipment Failure (Explain) 3 -Manual foe Peepaemelon of Data S: Scheduled 8-Maintenance of Test

2. Manual Sceam.

Entry Sheets for Licensee C.Hefueling 3 Automatic Sceam. Event Report (LER) File (NUREG-D Regulatoey Restsiction 4-Othee (Earlain) 0161) j E-Operator Tsaining & Ucense Examinathm 5 F. Administrative Exhibit 1 - Same Source G Operational Eeene (Emplain) j l'7/7 F) Il-Other (Emplain) i

LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.1 MONTH: July, 1983 DATE TILE HOURS LOAD. MW REDUCTIONS MW MWH REASON NONE DU1 LING THIS REPOEING PERIOD. I l I e. _ _ _ _. +,m, 4.e4., e m em e. er i 6 e., ap O" f f ,m- ,.._a I e MONTHLY TOTAL . _ _.. l

LbADREDUCTIONSDUETOENVIRONMENTALRESTRICTIONS UNIT NO. 2 MONTH: Julv, 198'3 DATE TILE HOURS LOAD, MW REDUCTIONS, MW MVH REASON NOEll DURING TKIS REPORTIN'I PERIOD.

t.

e 9 9 4 2 9 e e l l i l e m o MONTHLY TOTAL

DOCKET NO 50-280 UNIT SURRY I DATE 8-1-83 COMPLETED B1 Vivino E. Jones AVERAGE DAILY UNIT POWER LEVEL MONTH: JULX 83 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWE-NET)

DA? (MWE-NET) 1 739.2 17 732.5 2 ?- 738.5 18 730.7 3 738.7 19 728.8 4 739.2 20 726.4 5 735.8 '21 722.3 C 740.0 22 724.5

/

676.8 23 728.5 8 S33.7 24 727.3 9 675.2 25 729.0 10 740.3 26 727.8 11 742.1 27 728.4 12 744.0 28 730.4 13 739.8 29 731.6 14 739.3 30 729.9 15 438.5 31 729.4 1G 510.0 DAILI UNIT POWER LEVEL FOMI INSTRUCTIONS ON THIS 70MI, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITI POR THE NET ELECTRICAL RATING OF THE UNIT, THEE MAY BE OCCASIONS WHEN THE DAILI AVERAGE POWER EXCEEDS THE 100 */* LINE (OR THE ESTRICTED POWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY UNIT POVER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY. 7_

o ~ DOCEET NO 50-281 UNIT SURRY II DATE 8-1-83 LGi?LETED BX Vtytan E. Jones AVERAGE DAILY UNIT POWER LEVEL MONTH: JULY 83 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL NY (MWE-NET) DAY (MWE-NET) 1 0.0 17 0.0 2 0.0 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 7 0.0 23 0.0 0 0,0 24 0.0 4 9 0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 ~ 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0 DAILY UNIT POWER LEVEL FOR4 INSTRUCTIONS ON THIS POM!. LIET THE AVERAGE DAILY UNIT POWER LEVEL IN MVE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORTe ING NORTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITI FOR THE NET ELECTRICAL RATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 */* LINE (CR THE RESTRICTED POVER LEVEL LINE). IN SUCH CASES, THE AVERAGE MILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT AN0 HALY.,

i

SUMMARY

OF OPERATING EXPEPIENCE July, 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. INIT ONE July 1 0000 This reporting period begins with the unit at 100% power. July 7 0043 Commenced power decrease, load following 0233 Holding power at 60% Reactor power 0510 Commenced power increase 0800 Unit is at 100% power July 8 0035 Comenced power decrease, load following 0320 Holding power at 60% reactor power 0500 Come.nced power increase 0716 Unit is at 100% power Tuly 9 0125 Commenced power decrease, load following 0320 Holding power at 60% reactor power 0600 Commenced power increase 0845 Unit is at 100% power July 15 1414 Rx trip, caused by loss of "B" sain f eed pump 1619 Rx critical 2008 Generator on the line 2013 Rx trip, caused by "B" S/G hi-hi level 2218 Rx critical July 16 0021 Generator on the line 0145 Holding power at 34% for chemistry 0530 Commenced power increase 1430 Unit is at 100% power July 31 2400 This reporting period ends with the unit at 100% power _9 m ~. -

SUMMARY

OF OPERATING EXPERIENCE Julyr 1983 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sig-nificant non-load related incidents. UNIT 'lWO July 1 0000 This reporting period begins with the unit shutdown for refueling at 500*F while setting safeties 12,00 Rx coolant system < 350*/450 psig on RHR 1605 Ex coolant system <200*F July 13 0405 RCS loops drained July 20 0715 RCS bead lif ted 1933 Control rods unlatched July 21 1942 Commenced fuel off-load July.24 0630 Rear.cor vessel is defueled July 26 1818 Commenced fuel on-load July 31 2400 This reporting period ends with the unit at refueling Shutdown, core on-load is progress. i

AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS None during this reporting period. J +- N = 9 Y e f I i I a -e..

...m_ l FACILITY CHANGES REQUIRING NRC APPROVAL July, 1983 1 None during this reporting period. i { r I I 1 i 4 s J 6 t e d t e .u. - ~ g -mm,-ve - e, e e. ..n.- -.-,,,..n,

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL 2 July. 1983 DC 81-53 Containment Grab Sample Dedicated Penetration Unit 1 & 2 This design change installed the supply and return tubing from the containment to the Containment Atmospheric Sampling Panel (CASP). The CASP shall be installed in accordance with DC 80-31. The separate Con-tainment Atmospheric Sampling System will fulfill the requirements for NUREG-0737, Section II.B.3. Summary of Safety Analysis The modification does not affect normal operation or the operation of any safety related equipment under seismic or accident conditions. DC 82-16B Replacanent SKV Electrical Penetrations Unit 2 This design change replaced the 9th existing penetration with a new Conax penet:Etion. The otber 8 were rr. parted in May,1982. The design of these t replacentnc itsnetrations utilizer cera:.nc oushings at the pressure boundary and requires na corpound. The lack of mair.tainability of the old connectors and the difficulty in Um.rament of replacecc7t components resulted in the decision to replace the penetrations with those of a proven and qualified design. i S'mmary of Safety Analysis This modification does not affect station oparations or the operatio'ns of safety related equipment. The replacement of the penetrations enhances the containment pressure boundary, as well as the operation of the' Reacter Coolant Pumps and Residual Heat Removal Pumps. DC 82-30 Replacement of Station Battery Chargers Unit 1 & 2 This design change installed replacement battery chargers, Documentation is provided to demonstrate that the equipment will function in the environment j (both atmospheric and siesnic) that it operates in and that it can provide l the indicated load. Summary of Safety Analysis The station battery chargers were replaced during a refueling outage to minimize the impset on station operation and safety. The FSAR will be changed to reflect the increased capacity of the new units (300 AMPS versus 200 AMPS). DC 83-11 Replacement Diesel Generators Battery Racks Unit 1 & 2 This design change replaced the emergency diesel generator batteries to ensure proper response. The old batteries had approached their useful life, were at reduced voltage level, and required excessive maintenance. Summary of Safety Analysis I. The modification enhances the operation of the emergency power system by l providing a more reliable battery output to flash the field of the emergency diesel generator responding to an emergency start signal.

7 Unit D/C 82-44 Incore Thermocouple (T/C) 1 Replacement During reinstallation of the reactor vessel head, one of the thermocouple columns was damaged and subsequently removed. A ?-- bottom mounted integrated flux thimble thermocouple was added to restore lost temperature detection. Sumeen'_of Safety Analysis The modification does noe aff ect normal statien operation nor the operation of any saf ety related equ ipment. i I e - l

=. i e e TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL None during this reporting period. TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL None,d'2 ring this reporting period. e ] I i t )

r

( . -. = . = -.

r. OTHER CHAMGES, TESTS AND EXPERIMDITS e None during this reporting period. 0 6 9 4

~ ) VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION CHEMISTRY REPORT July 19 83 - T.S. 6.6.3.d

(A)

UNIT NO. I UNIT NO. 2 ANALYSIS MAXIMUM: MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross __Radioact., uCi/tol 6.78E-1 9.64E-2 4.45E-1 2.65E-1 2.24E-3 3.65E-2 j Sunpened_Sglids, pp*n 0.0 0.0 0.0 0.5

0. 5_

0.5 Gross Tritium, itCi/ml l 1.88E-1 7.15E-2 1.22E-1 i l31 Iodine cym1_ 3.13E-2 1.41E-3 3.90E-3

9. 7t.E-2 1.395-5

$.7tE-3 131 133 7 77 g 0.35 0.08 0.13 47.1 N)h3.0 31.6 25.0 3.9 11.2 Hydrogen, ce/kg 1.90 1.31 1.55 1.91 0.96 1.44 Lithium, ppit, Boron-10, ppm *

169 129 151 445 203 373 0.005 0.005

, 0.005 3.80 0.005 2.10

Dxygen, (D.O.), ppm 0$02 0.02 0.02 0.02 0.02 0.02 Chloride, ppm 6.92 6.54 6.67 6.32 4.73 5.18 pH 9 25'C

Boron-10 m Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (C)

RELEASES, POUNDS T.S. 4.13.A.6 Phosphate Boron. 831 ~ Chromate 8.0 Sulfate Chlorine 0.0 50% NaOH ~

'.1;* (A) Unit 2 shut-down for refueling outage.

REMARKS: (B) Operations notified; recommended increase in VCT pressure. (C) The levels.of these chemicals should produce no adverse environmental impact. D e following Lithium additions were made to Unit 1: 340 gas. on 7/8; 275 gas. on 7/12 325 gas on 7/13; 600 gas. on 7/16. S e Primary Cation Bed was placed in service for Lithium removal from Unit 1 on the following dates: 7/1, 7/3, 7/5, 7/18, 7/19, 7/25, 7/28, 7/31. -. -L --:--- 2:::~ r : r -

L

.~ JL,. - - : ~., _.. = -. -, -

DESCRIPTION OF ALL INSTANCES WERE THER!iAL DISCliARGE LI!!ITS WERE EXCEEDED a None during this reporting period. s... 4 6 ( eg -g ee 9 = g e 6 & aq g e i e. I l G l em 4 W O @6 .e' re* -@*D , i t

l FUEL HANDL*ING UNIT I July. 1983 4 DATE NO. OF ANSI NO. NEW Oil SPEh7 TUIL SHIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMEh7 SHIPPING CASK ACTIVITY LEVI i NONE DUEING THIS REPORTING. PERIOD. A i. F 4 A'tIWh Ww g g g. e 9 l l l SD.

r s FUEL HANDLING l

e UNIT II l

July, 1983 DATE NO. OF ANSI NO. NEW OR SPEh7 FUEL SHIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVEL, NONE DULING THIS REPORTING PERIOD. N gem ' mew & M N m f9Cemm-t 649Z2 - 6-M e + me e b eme w = d O a 9, -.

::. ~, --- -.,.,.

--, :.:,- - - - :~~ - -.., - -- - - - -..... - - - - - - - - -,.

PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR July, 1983 None during this reporting period. t 9 e ...w 4 e < l t I i I I I 1 t I i i ) + --

r DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS Unit 1 PT 17.5 Containment Subsurface Drainage Pump ~ Performance was not comp 1eted within the grace period (4-19-83 + 7 days). The test was completed on 4-27-83 with all results. acceptable. s. I t e / J 1 s d e 9 s e-4 ~ s 4 4 4 s ~ * ~ _. ;~ --~ ~,r -- ^ .._#:r__-__.._-_~.2,__.

's s. ' ~ MAINTENANCE OF'54FETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS _ UNIT NO. 1 MECHANICAL MAINTENANCE ~. ' 3... i. t / s 'N s + 4 e g l (/ s**' ( -a, \\ 'A r', t 4 ,w, o-w f i I 3 1 \\ s b l Ts ( - \\ e k I L +, ' i [ s . ti

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F HEALTH PHYSICS None during this reporting period. \\ g. e e e l t e -a_

o o O *g.., PROCDURE DEVIA" IONS REVIEk"LD ET STATIO : FJCLEAR SAFETY AND OPEFJ. TING CO:fi!TTEE AFTER TEE LnIITS SPECIFIED Ii TECFEICAL SPECIFICATIONS JULY, 1983 DATE DATE SNSOC PROCEDURE NO. UNIT TITLE DEVIATED REVIEJED PT 14.2 1 Main Steam Trip valves and Main 6-16-83 7-07-83 Steam Non-Return Valves CAL-MM-13b 1,2 Calibration Procedure for Sigma 7-05-83 7-21-83 Theta Loop PT 16.4 2 Containment Isolation Valve 7-02-83 7-28-83 Leakage 7-03-83 7-05-83 7 83 7-11-83 e S .e ?.* O e e i ( e l . _. - -}}

ML20024F069

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ML20024F069

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