ML20083L238

Monthly Operating Rept for Apr 1995 for Hope Creek Unit 1.W/

ML20083L238
Person / Time
Site:	Hope Creek
Issue date:	04/30/1995
From:	Hovey R, Lyons D Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9505180223
Download: ML20083L238 (9)

Text

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'170 PSEG 1

Pubhc Service Electric and Ge s Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station May 15, 1995 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ,

Dear Sir:

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 operating statistics for April are being forwarded to you with the summary of changes, tests, and experiments that were implemented during April 1995 pursuant to the requirements of 10CFR50.59 (b) .

Sincerely yours, i

$YkyffMJ R. J. Hovey ff General Manager -

Hope Creek Operations

@ 4 14 DR:WS:JC Attachments C Distribution hDR DO K 05000 54 R PDR i

I I The Energy People / I\ l 95 2173(25W 12 89

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. l INDEX NUMBER SECTION OF PAGES l

Average Daily Unit Power Level. . . . . . . . . . . 1 1 Operating Data Report . . . . . . . . . . . . . . . 3 Refueling Information . . . . . . . . . . . . . . . 1 Monthly Operating Summary . . . . . . . . . . . . . 1 Summary of Changes, Tests, and Experiments. . . . . 1 l

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-354 UNIT Hooe Creek DATE 05/03/95 COMPLETED BY D. W. Lyons TELEPIIONE (609) 339-3517-MONTH ADril 1995 1

. DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I (MWe-Net) (MWe-Net) y

1. 1061 17. 1056 j l

2. 221 18. 1053 1

3. 1068 19. 1035 l

'4. 1052 20. 1053

5. 1062 21. 1046

6. 1061 22. 1042

7. 1056 23. 1045

8. 211 24. 1059

9. 1D_41 25. 1053

10. 1057 26. 1053

11. 1062 27. 1053

12. 1047 28. 1042

13. 1055 29. 899

14. .1056 30. 1049

15. 1056 31. NLA

16. 1051

4 OPERATING DATA REPORT DOCKET NO. 50-354 UNIT Hope Creek DATE 05/03/95 COMPLETED BY D. W. Lvons TELEPHONE (609) 339-3517 OPERATING STATUS

1. Reporting Period April 1995 Gross Hours in Report Period 712

2. Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 1031 Design Electrical Rating (MWe-Net) 1067

3. Power Level to which restricted (if any) (MWe-Net) None

4. Reasons for restriction (if any)

This Yr To Month Date Cumulative

5. No. of hours reactor was critical 719.0 2719.6 62655.5

6. Reactor reserve shutdown hours 0.0 0.0 0.0

7. Hours generator on line 719.0 2698.0 61701.4

8. Unit reserve shutdown hours 0.0 0.0 02 1

9. Gross thermal energy generated 2340290 8739235 197153581 (MWH)

10. Gross electrical energy 781187 2928349 65356015 generated (MWH)

11. Net electrical energy generated 750262 2807300 62460616 (MWH)

12. Reactor service factor 100.0 94.5 85.5

13. Reactor availability factor 100.0 94.5 85.5

14. Unit service factor 100.0 93.7 84 2

15. Unit availability factor 100.0 93.7 84.2

16. Unit capacity factor (using MDC) 101.2 94.6 82.7

17. Unit capacity factor 97.8 91.4 79.9 (Using Design MWe)

18. Unit forced outage rate 0.0 6.3 4.8

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

Refueling Outage #6 scheduled to begin November 8, 1995 j

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

N/A

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. 1 Desian Chances Summary of Safety Evaluation 4HE-00083: This Design Change Package installs 1 inch vent and drain valves in various locations in the Residual Heat Removal Piping system. These valves will improve the venting and draining of the system and reduce the draining time involved. The design basis of the RHR system will not be changed. They will be closed during normal operation and there is no reason to reposition these valves. FSAR Figure 5.4-13 (P&ID M51-1) will require revision to address these changes to plant configuration.

Therefore, this DCP does not increase the probability or consequences of an accident previously described in the SAR and does not involve any Unreviewed Safety Question. ,

1 Other Summary of Safety Evaluation Incident Report 95-096: This incident report was issued due to the Safety Auxiliary Cooling System (SACS) ECCS valves air Regulator failing high. This review describes failing open of numerous SACS Supply Valves to the Diesel Generator room cooler, HPCI room coolers, RHR room coolers, Core Spray Pump room coolers, and FRVS coolers. The valves described all have Hiller Actuators.

Of the 32 valves identified as having Hiller Actuators, 9 valves have conoflow style air regulators. To date we have tested 2 of the valves with this style air regulator and none have failed. Of the remaining 23 valves 15 have been tested. Of these 15, there have been five failures. Testing of the remaining 8 valves with the old style regulators (C.A.Norgren Co) is in progress but for the purpose of analysis it is assumed that the remaining 8 valves also fail.

The UFSAR mentions that each SACS valve is interlocked with and will close when the associated ECCS, D/G, and FRVS Room Cooler fan is out of service. Failing these valves to the open position bypasses the interlock between the fans and the SACS valves. The UFSAR illustrates these valves in the closed position. Therefore 4 this changes the facility as described in the SAR. I The SACS system has sufficient cooling flow and heat removal capacity to satisfy the service and cooling requirements of the Engineered safety Feature (ESP) equipment and Turbine Auxiliary during normal and emergency conditions. For emergencies the valves in question are equipped with a fail open feature. During a LOP or LOCA the valves will already be in the correct conditions. The SACS pumps are adequately designed and have sufficient excess capacity to provide flow with all the valves in question failed open.

Therefore, this Safety Evaluation for Incident Report 95-096 does not increase the probability or consequences of an accident previously described in the SAR and does not involve an Unreviewed Safety Question.

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OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS 1

DOCKET NO. 50-354 i UNIT HoDe Creek i DATE 05/03/95 '

COMPLETED BY D. W. Lyons TELEPHONE (609) 339-3511 l MONTH ADril 1995 ,

METHOD OF SHUTTING  !

DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S= SCHEDULED (HOURS) (1) POWER (2) ACTION / COMMENTS

1. NONE 1

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, 5 REFUELING INFORMATION DOCKET NO. 50-354 UNIT HoDe Creek 1 DATE 05/03/95 COMPLETED BY R. Schmidt TELEPHONE (609) 339-3740 MORS4 poril 1995

1. Refueling information has changed from last month:

Yes X No

2. Scheduled date for next refueling: 11/11/95

3. Scheduled date for restart following refueling: 12/10/95

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

Yes No X B. Has the Safety Evaluation covering the COLR been reviewed by the Station Operating Review Committee?

Yes No X If no, when is it scheduled? Auaust 28, 1995

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

Hg1 recuired.

6. Important licensing considerations associated with refueling:

N/A

7. Number of Fuel Assemblies:

A. Incore 26_4 B. In Spent Fuel Storage (prior to refueling) 1240 C. In Spent Fuel Storage (after refueling) 1472

8. Present licensed spent fuel storage capacity: 4006 Future spent fuel storage capacity: 4006

9. Date of last refueling that can be discharged 5/3/2006 to spent fuel pool assuming the present (EOC13) licensed capacity:

(Does allow for full-core offload)

(Assumes 244 bundle reloads every 18 months until then)

(Does nqt allow for smaller reloads due to improved fuel) i i

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. 8 HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

April 1995 Hope Creek entered the month of April operating at 100% power. It ;

continued to operate at essentially 100% power throughout the month.

Two small power reductions were made to facilitate repairs to plant equipment. On April 8 & 9, 1995 power was reduced for condensate polisher bed cleaning. On April 29, 1995 power was reduced to facilitate a leak repair for a turbine bypass valve.

As of April 30, 1995 the unit has been on line for 35 days.

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SUMMARY

OF CHANGES, TESTS,.AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION i.

T April 1995 i

E 1 The following items have been evaluated to determine:

1. If the probability of occurrence or the consequences of an 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 i report may be created; or

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

1 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. l 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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