ML20129A827

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

ML20129A827
Person / Time
Site:	Hope Creek
Issue date:	09/30/1996
From:	Bezilla M, Harris R Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N96328, NUDOCS 9610220251
Download: ML20129A827 (9)

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

OCT151996 LR-N96328 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 l

Hope Creek Technical Specifications, the operating statistics for September 1996 are being forwarded to you with the summary of and experiments that were implemented during changes, tests, August 1996 pursuant to the requirements of 10CFR50.59(b).

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.i sincerely yours, a

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fk Ma B. Bezilla General Manager -

1 Hope Creek Operations RH:LK:DS Attachments i

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i INDEX NUMBER SECTION OF PAGES F

Average Daily Unit Power Level............

.I Operating Data Report....

.2 Refueling Information....

....1 Monthly Operating Summary........

.I Summary of Changes, Tests, and Experiments....

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DOCKET NO.: 50-354 UNIT: llooc Creek DATE: 10/04/96 COMPLETED BY:

R. liarris TELEP110NE: (609)339-1777 AVERAGE DAILY UNIT POWER LEVEL MONTII SEPTEMBER 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1026 17 1043 2

1028 18 1047 3

1036 19 J071 4

1090 20 1008 5

977 21 991 6

J021 22 904 7

1023 23 1048 8

1038 24 1049 9

1030 25 1048 10 966 26 1141 11 JJ05 27 1077 12 1035 28 1065 13 1047 29 971 14 1057 30 1007 15 1933d 31 N/A 16 1043

DOCKET NO.: 50-354 UNIT: Llope C.fs_els DATE: 10/04/96 COMPLETED BY: R. Harris TELEPHONE: (609) 339-1777 OPERATING DATA REPORT OPERATING STATUS 1.

Reporting Period September 1996 Gross Hours in Report Period 720 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)

Norte 4.

Reasons for restriction (if any)

This Month Yr To Date Cumulative 5.

No. of hours reactor was critical 720.0 4713.2 71637.1 6.

Reactor reserve shutdown hours M

M M

7.

Hours generator on line 2_.0_S 4555.4 70497.0 2

8.

Unit reserve shutdown hours M

0J OJ 9.

Gross thermal energy generated (Mwn) 2332651 14432521 225206770 10.

Gross electrical energy generated (MWH) 776320 4811431 74637053 11.

Net electrical energy generated (MWH) 744263 4588800 71306035 12.

Reactor service factor 100.0 71.7 83.5 13.

Reactor availability factor 100.0 21 2 83.5 14.

Unit service factor 100.0 69.3 82.2 l.

15.

Unit availability factor 100.0 69.3 82.2 16.

Unit capacity factor (using MDC) 100.3 67.7 80.7 17.

Unit capacity factor (using Design MWe) 96.9 65.4 77.9 3

18.

Unit forced outage rate O_0 0_A M

19.

Shutdowns scheduled over next 6 months (type, date, & duration): Maintenance Outage j

starting November 2,1996; 7 days breaker to breaker.

20.

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

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4 DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 10/04/96 COMPLETED BY: R. Harris TELEPHONE: (609) 339-1777 OPERATING DATA REPORT UNIT SIIUTDOWNS AND POWER REDUCTIONS MONTil SEPTEMBER 1996 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO.

DATE S= SCHEDULED (HOURS)

(1)

POWER (2)

ACTION / COMMENTS n/a 1

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1 DOCKET NO.: 50-354 UNIT: lig.pe Creek DATE: 10/04/96 COMPLETED BY: L. Kepigy j

TELEPHONE: (609) 339-1106 REFUELING INFORMATION MONTII SEPTEMBER 1996 l.

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.

IIas 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 Determinesi for Cycle 8 COI.R 5.

Scheduled date(s) for submitting proposed licensing action:

Not required.

6.

Important licensing considerations associated with refueling:

N/A 7.

NumberofFuel Assemblies:

A. Incore 764 B. In Spent Fuel Storage 1472 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 to spent fuel pool assuming the present licensed capacity:

(EOCl3)

(Dnes allow for full-core off-load) e (Assumes 244 bundle reloads every 18 months until then)

(Does not allow for smaller reloads due to improved fuel)

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DOCKET NO.: 50-354 UNIT: Hooc Creek DATE: 10/04/96 COMPLETED BY: R. Harris TELEPHONE: (6091339 1777 MONTHLY OPERATING

SUMMARY

I MONTH SEPTEMBER 1996 The Hope Creek Generating Station remained on-line for the entire month and e

operated at essentially 100% power for the month of September 1996 except two load reductions identified below.

Power was reduced to 87% on September 1,1996 starting at 0317 hours0.00367 days <br />0.0881 hours <br />5.241402e-4 weeks <br />1.206185e-4 months <br /> to perform monthly turbine valve testing. The unit was returned to 100% power on September 3, 1996 at 0822 hours0.00951 days <br />0.228 hours <br />0.00136 weeks <br />3.12771e-4 months <br />.

Power was reduced to 80% on Se?tember 20,1996 starting at 2203 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.382415e-4 months <br /> to perform deep shallow rod swap and month.y turbine valve testing. The unit was returned to 100% power on September 21,1996 at 1017 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.869685e-4 months <br />.

At the end of the month the unit had been on-line for 190 days.

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j DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 10/04/96 COMPLETED BY:

L. Keoley TELEPHONE: HiO9) 339 3517

SUMMARY

OF CIIANGES, TESTS, AND EXPERIMENTS FOR TIIE IIOPE CREEK GENERATING STATION MONTII SEPTEMBER 1996 The following items completed during August 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 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 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 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.

Design Changes Summary of Safety Evaluations The design changes that were implemented during the month of August will be discussed in a later report.

UFSAR Chanac Notices Summary of Safety Evaluations UFSAR CIIANGE NOTICE CN 95-05, UFSAR ORGANIZATIONAL UPDATE.

e The Nuclear Business Unit (NBU) has been re-organized to improve the direction, control, oversight, and accountability over plant operations and support functions. These organizational changes required changes to the llope Creek UFSAR.

The NBU organizational changes addressed by this proposal are any changes which became effective through August 7,1996. There is no reduction in the level of management control, responsibilities, training and qualifications, authority or commitments.

The revised organizational structure should improve alignment of responsibilities and management focus on activities related to safety.

l These changes are administrative in nature and have no effect on failure modes, j

o 3erational transients, postulated design basis accidents, or assumptions contained in the p' ant safety analysis. Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

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e UFSAR CIIANGE NOTICE CN 96-09, FIRE LOAD CIIANGE FOR ROOM 3356 Room 3356 is located in the north end of the Radwaste Building 102' elevation and is separated from safety related cable and components in Fire Area AB3 by Branch Technical position 9.5-1 (BTP) fire barriers. This change notice was required due to the storage of approximately 4 gallons of a combustible solvent used as a parts cleaning solution. The solvent used in the parts cleaner is EPA 2000 which is a mineral oil having a flash point of 141 degrees F. The storage of these containers in the room required a revision to the fire load values in Table 9A-1 and Table 9A-6 of the Hope Creek UFS AR.

The addition of the solvent results in an approximate increase in fire load of 0.4 minutes in room 3356 and only 0.002 minutes in Fire Area AB3 These increases are insignificant and have no effect on the fire barriers encompassing the area. This additional load does not impact or limit the performance of the detection or suppression system in the area, nor is the performance of these systems impacted if the maximum quantity of solvent (42 gallons) is utilized in the future. The increased loading does not impact the structural steel fire? roofing program, nor is there any impact to safe shutdown systems, functions, or Rac! waste processes as discussed in table 9A-6 of the UFSAR.

This UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.

Temporary Modifications Summary of Safety Evaluations There were no temporary modifications installed in the plant during the month of August,1996.

Deficiency Reports Summary of Safety Evaluations There were no new Deficiency Report safety evaluations completed in the month of August, 1996.

Procedures Summary of Safety Evaluations There were no new procedure related safety evaluations completed for the month of August, 1996.

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