ML20112J500

Monthly Operating Rept for May 1996 for Hope Creek Generation Station Unit 1

ML20112J500
Person / Time
Site:	Hope Creek
Issue date:	05/31/1996
From:	Bezilla M, Harris R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606200237
Download: ML20112J500 (9)

Text

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          .. O PSEG                                                                                                          l Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236                   l Nuclear Business Unit
                                                                                                                             ?

June 14,1996 l

                                                                                                                             )

l U. S. Nuclear Regulatory Commission Document Control Desk Washington,DC 20555 .

Dear Sir:

MONTHLY OPERATING REPORT i t 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 May 1996 are being forwarded to you with the , 8 summary of changes, tests, and experiments that were implemented during April 1996 pursuant  ; to the requirements of 10CFR50.59(b). 1 Sincerely yours,

                                                                               .- /                      4
                                                                          &  Y/;$                  f Mark B. Bezilla [

General Manager - Hope Creek Operations RH:DL:DS Attachments l C Distribution 9606200237 960531 PDR ADOCK 05000354 R PDR i i Thepowerisinyourhands. y ' 9E2168 REV 694

INDEX,

                                                                                                                                   .I NUMBER     l SECTION                                                                                                       OF PAGES   i i

i Average Daily Unit Power Level .. . ...... . ........ . . . .. . . . . . . . . . .1 1 4 Operating Data Report . .. . . ... .. .. . .... ... .. . . . . . . . . . . . . . . . . . . . . . . . . . .2 I t Refueling Information..... .. ..... . . . . .. .. ... ... . . .. ..... .. . ..............I l

                                                                                                                                   )
        - Mo nt hly Operating S ummary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
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Summary of Changes, Tests, and Experiments.. .. ..... .. . ..... . . . . . . . . . . .2 l i i i l i 1 1 i J P l l

l DOCKET NO.: 50-354 UNIT; Hope Creek DATE: 6/10/96 COMPLETED BY: R. Harris  ; TELEPHONE: (609) 339-1777 AVERAGE DAILY UNIT POWER LEVEL MONTH MAY 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i 1051 17 1012 2 1063 18 1053 i 3 1082 19 1034 4 1050 20 1026 5 1052 21 1018 6 1054 22 1078 7 LQ60 23 1028 8 1061 24 1046 9 969 25 1050 10 11L3 26 1054 11 212 27 1055 12 1048 28 1042 , 13 1059 29 1057 I 14 1061 30 1053 15 1056 31 1054 16 1012

h DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 6/In/96 COMPLETED BY: R. Harris TELEPHONE: (609) 339-1777 OPERATING DATA REPORT OPERATING STATUS

1. Reporting Period May 1996 Gross Hours in Report Period 744.

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) No_ns i

4. Reasons for restriction (if any)

This Month Yr To Date Cumulative

5. No. of hours reactor was critical 744.0 1785.2 68709.I

6. Reactor reserve shutdown hours 0.0 0.0 0.0

7. Hours generator on line 744.0 1627.4 67569.0

8. Unit reserve shutdown hours 00

_ M M 9 Gross thermal energy generated (MWH) 2406954 5051328 215825577

10. Gross electrical energy generated (MWH) 812190 1698681 71524303 4

11. Net electrical energy generated (MWH) 779470 1601862 68319097

12. Reactor service factor 100.0 48.9 83.0

13. Reactor availability factor 100.0 48.9 83.0

14. Unit service factor 100.0 44.6 81.6

15. Unit availability factor 100.0 44.6 81.6

16. Unit capacity factor (using MDC) 101.6 42.6 80.0

17. Unit capacity factor (using Design MWe) 98.2 41.2 77.3

18. Unit forced outage rate M 0.0 5.0 19 Shutdowns scheduled over next 6 months (type, date, & duration):

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

DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 6/10/96 COMPLETED BY: R. Harris TELEPHONE: (609)339-1777 OPERATING DATA REPORT UNIT SIIUTDOWNS AND POWER REDUCTIONS MONTil MAY 1996 ' I METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S= SCHEDULED (HOURS) (1) POWER (2) ACTION / COMMENTS NONE I l 1 I I

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           .                                                                                                     I DOCKET NO.: 50-354 UNIT: HODC CrCCk DATE: 6/10/96 COMPLETED BY: R. Harris             i TELEPHONE: (609)339-1777 REFUELING INFORMATION MONTH MAY 1996

1. Refueling information has changed from last month:

Yes _ No X

2. Scheduled date for next refueling (RF07): 9/6/97

3. Scheduled date for restart following refueling: 11/5/97 4A. 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 (SORC)? . Yes _ No X If no, when is it scheduled? To Be Determined for Cycle 8 COLR

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

Not required.

6. Important licensing considerations associated with refueling:

MA ,

7. Number ofFuel Assemblies:  !

A. Incore 764 l B. In Spent Fuel Storage J.472  :

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

9. Date oflast refueling that can be discharged 5/3/2006 l to spent fuel pool assuming the present licensed capacity: (EOCl3)

(Does allow for full-core off-load) (Assumes 244 bundle reloads every 18 months until then) (Does n01 allow for smaller reloads due to improved fuel) l I l l

e, DOCKET NO.: 50-354 UNIT: Hope ueek DATE- 6/10/06 COMPLETED BY: R. Harris TELEPHONE: (609)339-1777 MONTHIN OPERATING

SUMMARY

MONTH MAY 1996

• The Hope Creek Generating Station remained on-line for the entire month and i

operated at essentially 100% power for the month ofMay 1996

• Power was reduced on May 11,1996 for repairs to the "B" Reactor Feed Pump and performance of monthly turbine valve testing.

                     +  At the end of the month the unit had been on-line for 68 days.

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7 DOCKET NO.: 50-354 UNIT: Hone Creek DATE: 5/30/96 COMPLETED BY: D. W. Lyons TELEPHONE: (609)339-3517

SUMMARY

OF CIIANGES, TESTS AND EXPERIMENTS FOR TIIE IIOPE CREEK GENERATING STATION MONTII MAY 1996 The following items completed during April 1996 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 repon 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 may 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 i to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant efiluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved. Emergency Plan Summary of Safety Evaluation e IIECG - ATT 2,3,4 & 8/ E. PLAN SECTION 6, IIOPE CREEK ECG ATTACilMENTS 2,3,4,8/ EMERGENCY PLAN SECTION 6 This change reassigns the task of mitiating Emergency Response Organization (ERO) activation from the Communicator 2 (CM2) to the Emergency Coordinator (EC) who at that time in the emergency is the Senior Nuclear Shift Supervisor (SNSS). This change enhances the call out system by eliminating a potential time delay without negatively impacting other emergency response actions. At the stan of the event, the CM2 may not be immediately available if completing assigned duties outside the Control Room. The EC who is the SNSS is there, has been tramed on this task as part of the EC training and can complete the task in less than two minutes. Therefore, this change will ensure the task is done sooner and with minimal, less than two minute delay, on subsequent EC tasks. There were, also, other editorial improvements made at this time. The Nuclear Business Unit (NBU) Emergency Plan (EP) is part of the UFSAR. Since this change requires a change to Section 6 of the NBU EP, this is a change to a procedure in the UFSAR. There are no affects on any plant parameters or systems, operational transients, or postulated design basis accidents either previously evaluated or of a different type from any previously evaluated in the UFSAR. Therefore, this condition does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

Desien Changes UFSAR Chanee Notices Temporary Modifications Deficiency Reports Procedures Other There were no changes in any of these categories implemented during April 1996. a}}