ML20044C136

Monthly Operating Rept for Feb 1993 for Hope Creek Generating Station Unit 1

ML20044C136
Person / Time
Site:	Hope Creek
Issue date:	02/28/1993
From:	Hollingsworth, Hovey R, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9303180142
Download: ML20044C136 (10)

Text

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on Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 L-..[.,.

Hope Creek Generating Station f

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March 12, 1993 1

U. ' S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 I~

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~ February are being forwarded to you'with.the summary of changes, tests, and experiments that-were.

implemented during. February 1993 pursuant to the requirements-r of 10CFR50.59(b).

sincerely yours, W_

R;.J.Hovhy

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General Manager -

-. 4 f Hope Creek Operations

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INDEX NUMBER 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.

3 I'

4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-354 UNIT Hone Creek DATE 3/12/93 i

COMPLETED BY V.

Zabielski TELEPHONE. (609) 339-3506 MONTH Februarv~1993 DAY. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

1053 17.

1063 2.

1086 18.

1065 3.

1062 19.

1062 4.

1068 20.

1053 5,

1063 21.

. jIl 6.

1065 22.

lain 7.

1075 23.

1066 8.

1057 24.

1066 9.

1070.

25.

1071 10.

1068 26.

1066 11.

1065 27.

1066 12.

1073 28, 1070 13.

1073 29.

HiA 14.

1055 30.

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15.

1071 31.

HIA 16.

1020 I

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4 OPERATING DATA REPORT-DOCKET NO. 354 x.

UNIT:~ Hope Creek DATE 3/12/93 COMPLETED BY:

V.

Zabielski' l

TELEPHONE. (609) 339-3506 l

. OPERATING STATUS i

'1.

Reporting Period February 1993 Gross Hours in Report Period'521' 2.

. Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) lQ11 1

Design Electrical Rating-(MWe-Net) 2QAZ:

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 672.0 1416.0 45.671.6

6.

Reactor reserve shutdown hours 222 0.0 22g 7.- ' Hours generator on line 672.0 1416'.0 44.920.9 l

8.

Unit reserve shutdown hours AJ1 222

.ptn' 9.

' Gross thermal energy generated 2.180.131.

- 4.620.917-142;834.136 (MWH)-

10. Gross electrical energy 736.470

- 1.561.880 47.309.934 generated-(MWH)

Lil.-Net electrical energy generated 705.671-1.496.593 45,198;977-(MWH) 1;

12. Reactor' service factor 100.0 100.0 84,1 13.: Reactor' availability factor 100.0 100.0 84,1

14. Unit' service factor 100.0 100.0 82.7 1

f

15. Unit availability factor 100.0-100.0 82.7

16. Unit capacity factor'(using MDC) 101.9

.'1 0 2. 5 80.7 11'.' Unit capacity factor 1Eti 99.1 78.0 7

(Using Design MWe).

18. Unit forced outage rate 1,_q 22Q 321.'

4

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

y

~ None-1

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

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OPERATING DATA REPORT i

UNIT SHUTDOWNS AND POWER-REDUCTIONS DOCKET NO.

50-354 UNIT Hope Creek DATE 3/12/93 COMPLETED BY V.

Zabielski TELEPHONE (609) 339-3506 MONTH February 1993 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR I

F= FORCED DURATION REASON REDUCING CORRECTIVE NO.

DATE S= SCHEDULED (HOURS)

(1)

POWER (2)

ACTION / COMMENTS 1

2/20 F

0 A

5 Condenser Waterbox.

leaks I

Summary t

4

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e REFUELING INFORMATION DOCKET NO.

50-354 UNIT Hope Creek DATE 3/32/93 COMPLETED BY S.

Hollinasworth TELEPHONE (609) 339-1051 i

MONTH February 1993 1.

Refueling information has changed from last month:

Yes X No 2.

Scheduled date for next refueling:

3/5/94 3.

Scheduled date for restart following refueling:

4/23/94 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?

2/18/94 5.

Scheduled date(s) for submitting proposed licensing action:

HJA 6.

Important licensing considerations associated with refueling:

- Fuel will be highly similar to current fuel but not identical.

Changes should be conservative and introduce no new considerations.

7.

Number of Fuel Assemblies:

A.

Incore 764

.B.

In Spent Fuel Storage (prior to refueling) 1008 C.

In Spent Fuel Storage (after refueling) 1240 l

8.

Present licensed spent fuel storage capacity:

4006 Future spent fuel storage capacity:

4006 9.

Date of last refueling that can be discharged 5/3/20QE to spent fuel pool assuming the present (EOC13) licensed capacity:

(poes allow for full-core offload)

(Assumes 244 bundle reloads every 18 months until then)

(Does Dat allow for smaller reloads due to improved fuel)

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4 HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

FEBRUARY 1993 Hope Creek entered the month of February at approximately 100%

power.

On February 20, power was reduced to repair leaks in the condenser waterbox.

Power was returned to approximately 100% and

- the unit operated throughout the remainder of the month without experiencing any shutdowns or other reportable power reductions.

As of February 28, the plant had been on line for 85 consecutive days.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS' FOR THE HOPE CREEK GENERATING STATION FEBRUARY 1993 l

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The following items have been evaluated to determ! to:

1.

If the probability of occurrence or.the constquences of an accident or malfunction of equipment important to safety previously evaluated in.the safety aralysis report may be increased;'or 2.

If a possibility for an accident or malfunction'of a different type han any evaluated previously in the safety analysis report may be created; or 3.

If the margin of safety as de. fined 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.

)

nCE Descriotion of Safety Evaluation 4EC-3211/01 This DCP modified the start logic to the deep well pumps to prevent the administration building from running out of water under normal conditions.

The DCP added a low level switch contact to provide a signal to the deep well pump start control circuitry to start the lead deep well pump and send a signal to open the Domestic Water Storage Tan'ks Supply Valves.

This DCP will reduce the number of deep well pump starts while ensuring that both the Domestic Water Storage Tanks and the Administration Building Fresh Water Storage Tanks are getting filled.

This DCP does not affect the operation of the Domestic Water or the Fire Water Systems, nor does it prevent them from performing their intended functions.

Therefore, this DCP does not involve any Unreviewed Safety Questions.

4EC-3301/01 This DCP implemented the Emergency Response Data System.

Data can be transmitted to the Emergency Response Data System from the Safety Parameter Display System.

The Emergency Response Data System and the modifications to the Safety Parameter Display System do not affect any safety system functions.

Neither are they essential for the safe shutdown of the plant.

Therefore, this DCP does not involve any Unreviewed safety Questions.

.