ML20114A730

Monthly Operating Rept for Jul 1992 for HCGS Unit 1.W/

ML20114A730
Person / Time
Site:	Hope Creek
Issue date:	07/31/1992
From:	Hagan J, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9208200251
Download: ML20114A730 (12)

Text

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OPSEG PutAc ScN;de Electuc and G% Company P O Box P36 HantorR. fUely New Jert ey 08038 Hope Creek Generating Station August 14, 1992 U. S. Nuclear Regulatory Commiss.i.on Document Control Desk Washington, DC 20555 Dear Sirt MONTHLY OPERATING REPORT HOPE CREEK GENERATION STATION UNIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operatir,g statistics for July are being forwarded to you along with the summary of changes, tests, and experin.ents for July 1992 persuant to the requirements of 10CFR50.59(b).

Sincer ly yours,

/ '

J. . Hag.n ene 1 Me. nager -

Hope C ed Operations q R: 1d

, Attachments y

C Distribution The Enercly People 1 9208200251 920731 PIM ADOCK 050003S4 y0001u 4 - i

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IPDEX NUMBLR SECTION OF PAGES Average Daily Unit Power Level. . . . . . . . . . . 1 Operating Data Report . . . . . . . . . . . . . . 2 Refueling Information . . . . . . . . . . . . . . . 1 Monthly operating Summary . . . . . . . . . . . . . 1 Summary of Changes, Tests, and Experiments. . . . . 5 s

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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 50-354 UNIT Hope Creek i DATE 8/14/92 COMPLETED BY TI:LEPHONE V.

Zabiolski Q (6091 339-3506 MONTH July 1992 DAY AVERAt,E DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Not) i i

1. 1QM 17. laga 1

2. 10.41 18. 1023 ,

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3. 1047. 19. 1025

4. 1 2.43 20. 1031

5. 1011 21. 1026

6. 2034 22. 2241

7. 1Q12 23. 1033

8. 1024 24. JQil

9. 1058 25. 1093

10. 1026 26. 1022

11. 1025 27. 1029

12. 1RQ1 28. 1QH

13. 1033 J. 1036

14. M1 30. 1032

15. .1032 31. 1Q21

16. 1034 i.

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OPERATING DATA REPORT DOCKET NO. 50-354 UNIT Hope Creek DATE 8/14/92 COMPLETED BY y. Zabielski %- - -

TELEPHONE (609) 339-3506 OPERATING STATUS

1. Reporting Period July 1992 Gross Hours in Report Period 744 l

-2. -Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) iqn Design Electrical Rating (MWe-Net) 1067

3. Power Level to which restricted (if any) (MWe-Net) Eqng

4. Reasons for restriction (if any)

This Yr To lignth Date Egpulative

5. No. of hours reactor was critical 244.0 4793.5 41.954 1

6. Reactor reserve shutdown hours 222 2x2 222

7. Hours generator on line 744.0 4731.4 41.306.q

8. Unit reserve shutdown hours 0.0 O_tQ pig

9. Gross thermal energy generated 2.438.906 15.207.255 131.204.397 (MWH)

10. Gross electrical energy 891.480 5.060.010 13.412.504 generated (MWH)

11. Het electrical energy generated 766.364 1 836.392 41.487 211

12. Reactor service factor 100.0 93.8 65.2

13. Reactor availability factor 100.0 93.8 85.2

14. Unit service factor 100.0 2216 83.9

-15. . Unit availability factor- 100.0 92.6 83.9

16. Unit capacity' factor-(using MDC) 99.9 RJxa 61.8 l

17. Unit capacity factor 96.5 88.7 79.0 (Using Des!?n MWe) 18.. Unit forced outage rate 222 222 4.9

19. Shutdowns scheduled over next 6 months (type, date, & duration):

p Refueling' outage, 9/12/S2, 60 days

20. If-shutdown at end of report period, estimated date of start-up:

N/A l

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OPERATING DATA REPORT UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.30-354 UNIT Hose Creek DATE 8/14/92 COMPLETED BY V. Z a bi e l s};.i__d- --

TELEPIIONE (609) 339-3506  ;

i MONTil July 1992

. METHOD OF SHUTTING DOWN Tile TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S= SCHEDULED (llOURS) (1) POWER (2) ACTION / COMMENTS None Summary

• I REFUELING INFORMATION DOCKET NO. 50-354 UNIT Hope Creek DATE 8/14/92 COMPLETED BY E,-Hollincsworth TELEPHONE (609) 339-1051 '

MONTH July 1992

.1. Refueling information has changed from last month:

Yes X No

-3. Scheduled date for next refueling: 9/12/92 L

3. Scheduled Gate for restart following refueling: 11/11/92

4. A. Will Technical Specification changes or other license amendments be required?

Yes No X-B. Has the reload fuel design been reviewed by the Station Operating Review Committee?

Yes No X If no, when is it scheduled? The week of Sentember 7

5. Scheduled-date(s)~for submitting proposed licensing action: HIA

6. Important licensing considerations associated with refueling:

- Same fresh fuel asicurrent cycle: no new considerations 1

7. Number of Fuel Assemblies:

A. Incore 764 B. In Spent Fuel Storage (prior to refueling) 760 C. In Spent Fuel Storage (after refueling) 1008

.8. Present-licensed spent fuel storage capacity: 4006 g Future spent fuel storage capacity: 4006 l-L 9. ~Date of last refueling that can.be discharged 11/4, 2010 i- to spent fuel. pool assuming the present (EOC16) licensed' capacity:

(does not allow for full-core offload) l l

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9 IlOPE CREEK GENERATING STATION HONTHLY OPERATING SUhAARY ,

July 1992 Ilope creek entered the month of July at approximately 100% power.

The unit operated for the entire month without experlencing any shutdowns or reportable power reductions. As-of July 31, the plant had been on line for 47 consocutive days.

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SUMMARY

0F CllAliGES, TESTS, AllD EXPERIMENTS FOR Tile IlOPE CREEK GENERATING STATION JULY 1992

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The following items have been evaluated to determine:

1. If the-probability of occurrence or the consequences of an

1 accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report raay be created; or

3. -If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety. Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the -

- safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

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J DCE- Descrintion of Safety Evaluation 4EC-3206/04 This DCP installed two resin samplers on the influent lines to the Cation Regeneration Vessel and Rosin Mix and Hold Vessel to measure the effectiveness of the regeneration backwash process.

The Condensate Demineralizer System has no safety-related functions and is not required to bi cperable following an accident. There is no change to any system's function and no reduction in any system performance as a result of this DCP.

Therefore, tl.is DCP did not involve any Unreviewed Safety Questions.

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Procedure Revision Description of Safety Evaluation HC.OP-FT.EG-0101(Q) This new procedure will individually stroke

.Rev 0 the Safety Auxiliary Cooling System cross-tie valves supplying the Primary Containment Instrument Gas Compressors.

Prior to stroking each valve, the Valve Operation Test and Evaluation System will be inctalled and ready to collect data during the valve cycling.

This procedcre does not functionally change the Safety Auxiliary Cooling System or the Primary Containment Instrument Gas System.

The probability and consequences of either an accident or malfunction are unchanged.

Therefore, this procedure does not involve an Unreviewed Safety Question.

NC.NA-AP.ZZ-0069(Q) This administrative procedure describes the Rev 0 control.orocess for the coordination of work actlvities between implementing work organizations and the operating shift.

This proced- e'will enhance work control coordination by providing controls to ensure that work activities.are performed safely and in compliance with licensing requirements. This procedure complies with the UFSAR in that it provides additional controls for work control coordination.

Therefore, this procedure does not involve an Unroviewed Safety Question.

MFSAR Section Descriotion of Safety Evaluation Table 9.5-20 This UFSAR Change adjusts the calibration Table 9.5-22 frequency of the Standby Diesel Generator Table 9.5-24. instruments based on their maintenance Table 9.5-26 history. A note will be revised to cuate , hat Table 9.5-28 the instrumentation will be= calibrated on an 18 month schedule unti. an analysis is completed. At that time, the frequency will be no based on the Safety Unreviewed completed analysis;involvedtherefore, Questions are with this UFSAR change.

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