ML20085E283

Monthly Operating Rept for Sept 1991 for Hope Creek Generating Station Unit 1

ML20085E283
Person / Time
Site:	Hope Creek
Issue date:	09/30/1991
From:	Hagan J, Zabielski V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9110180143
Download: ML20085E283 (11)

Text

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Public Service Electric and Gas Corepany P.O. DOX 230 Hancocks Bndge, New Jersey 08038 l

Hope Creek Generating Station -

October 14, 1991 UU 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-September--are being forwarded to you with the summary of-changes, tests,_and experiments for August 1991 pursuant'to'the requirements of 10CFR50.59(b).

Sincer ly yours,

.-J Hagan-Gen al) Manager -

Hope stek Operations RAR:Id-Attachments C'

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INDEX HUMBER-SECTION OF PAGES Average Daily Unit Power Level.

1 Operating Data Report.

2 Refueling Information.

1 Month)

Operating Summary.

1

"$anges, Tests, and Experiments.

3 Sur' n '.'

1 J

+

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-354 UNIT lippMrcok DATE 1Q/14/91 COMPLETED BY V.

Zabielski TELEPilONE (609) 339-3506 MONTil Scotember 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Not)

(MWe-Net) 1.

1Q11 17.

1Qsl 2.

1QEZ 18.

1QQQ 3.

1Qih 19.

1Q11 4.

1Q16 20.

1Qff 5.

1Q11 21.

1Q11 6.

1911 22.

1qla 7.

1Q21 23.

Egg 8.

1Q21 24.

1Q12 9.

1Qla 25.

LQ23 10.

1Q11 26.

1Q31 11, 1Q2.Q 27.

1Qs1 12.

1951 28.

LQkl 13.

1Q11 29.

1Q12 14.

1915 30.

Eqi 15, 1Q21 31.

L 16.

1QQ1

w_

OPERATING DATA REPORT DOCKET NO.

50-354 UNIT Hone Creek DATE 10/14/91 COMPLETED BY V.

Zabielski TELEPHONE

_(609) 339-3506

' OPERATING STATUS 1.-

Reporting Period SeDtember 1991 Gross Hours in Report Period 12A 2.

Currently Authorized Power Level (MWt) 2222 Max. Depend. Capacity 1031 Design Electrical Ratin(MWo-Net)g (MWe-Net) 1067 3.

Power Level to which restricted (if any) (MWe-Not)

H2n2 4.

Reasons for restriction (if any)

This Yr To Month Dat;g fuglative 5.-

No. of hours reactor was critical

_7_2 0. 0 5170.8 34.952.3 6.

Reactor reserve shutdown hours Q2 929 210 7.

Hours generator on line 720.0 5072.5 34.365.G 8.

Unit reserve shutdown hours HzQ AzQ AzQ 9.

Gross thermal energy generated 2.374.275 11,3B7.297 108.929.705 (MWH)

10. Gross electrical energy 780.640 5.385.601 36.007.274 generated (MWH)

11. Net electrical energy generated 747.67R 5.145.951 34.402.637 (MWH)

12. Reactor service factor 100.0 78.9 83.4

13. Reactor availability factor 100.0.

76.9 83.4

14. Unit service factor 100.0 77.4 82.0

15. Unit availability factor 100.0 77.4 3222

16. Unit capacity factor (using MDC) 100.7 76.2 79.6

17. Unit capacity factor 97.3 73.6 76.9 (Using Design MWe) 18.. Unit-forced outage rate 922 5.7 511

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

None

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

N/A

1

+

OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-354 UNIT Hope Creek DATE 10/14/91 COMPLETED BY V. Zabielski__

TELEPHONE 1609) 339-3506 MONTH Sgp1=mber 1991 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO.

DATE S= SCHEDULED (HOURS)

(1)

POWER (2)

ACTION / COMMENTS 8

9/23 F

0 H

5 Spurious level 4 signal during Jet Pump PASS Sample Valve testing resulted in

'A' and

'B' Recirc Runback Summary

REFUELING INFORMATION DOCKET NO.

50-354 UNIT Hone Creek DATE 10/14/91 COMPLETED BY S. Hollinaswort.h TELEPHONE (609) 339-1051 MONTH SeDtember 1991 1.

Refueling information has changed from last month:

Yes No X

3.

Scheduled date for next refueling:

9/5/92 3.

Scheduled date for restart following refueling:

11/4/92 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?

not scheduled (on or prior to 7/24/92) 5.

Scheduled date(s) for submitting proposed licensing action:

HfA 6.

Important licensing considerations associated with refueling:

- Same fresh fuel as current cycle:

no new considerations 7.

Number of Fuel Assemblies:

A.

Incore 25A 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 Future spent fuel storage capacity:

4006 9.

Date of last refueling that can be discharged 11/4, 2001 to spent fuel pool assuming the present (EOC16) licensed capacity:

l

~

l HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

September 1991 1

Hope' Creek entered the month of September at approximately 100%

power and operated for the entire month without experiencing any shutdowns or reportable power reductions.

On September 23, a spurious level 4 signal occurred during Jet Pump PASS Sample Valve testing _and resulted in an

'A' and

'B' Reactor Recirculation runback.

This power reduction is being reported as a conservative measure even though it does not meet the reportability criteria of Regulatory Guide 1.16.

On September 30 141st day of continuous power operation, the plant completed its 1

l l

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION SEPTEMBER 1991

e

--The followingLitems_haveLbeen; evaluated to. determine:

11.

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;1or:

2.

If.a-possibility for an accident or malfunction of-a-different-

._ type than any evaluated-previouslyLin the safety analysis l report may=be created; or 3..

If the. margin of safety as defined in the basis for any

- technical specification is reduced.

Thel 10CFR50.59 Safety Evaluations ~showed that these items did not create a new safety hazard to the plant nor did they-affect the safe 1 shutdown _ofsthe reactor.- These items did not change the plant effluent-releases and did not alter-the existing environmental impact.

TheJ10CFR50.59 Safety. Evaluations determined that no unreviewed safety ~or environmental questions.

are: involved.

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IME Dancrintion of Safely Evaluation 91-046 This TMR modified the circuit for the measurement of river water-temperature.

The river water temperature measurement was obtained from four temperature detectors whose measurements are averaged into a single reading.

This TMR changes the circuit to obtain the temperature measurement from a single temperature detector.

This TMR is being installed because three of the four temperature detectors are currently providing unreliable readings.

No Unroviewed Safety Questions were involved because the these instruments are non-Q components.

Additionally, alternate methods are available to obtain the temperature readings if this temperature detector fails.

An alarm will display on the Control Room Integrated Display System to alert the operators that alternate measures should be used if this temperature detector fails.

s.

Procedure RevisiRD Description of Safety Evaluation NC.NA-AP.ZZ-0004(Q)

This administrative procedure revision Rev.

2-changed the membership requirements of the Hope Creek and Salem Station Operation Review Committees to agree exactly with the composition specified in the Technical Specifications.

It also allows a member and his alternate to vote at the same meeting, but not on the same issue.

The UFSAR will also be revised to delete the requirement to name alternates on a temporary basis.

No Unreviewed Safety Questions were involved becan se this procedure includes a F

requirement tnat alternates meet the ANSI qualifications specified for the appropriate member.

This prevents the quorum from beinn weakened due to the presence of an alternate.

Additionally, this procedure complies with, and is more conservative than, Technical Specifications and the UFSAR.

NC.NA-AP.ZZ-0049(Q)

This administrative procedure describes the Rev.

O controls and responsibilities that are in effect during fuel' handling and core 4

alterations.

No Unreviewed Safety Questions were 4

involved because this procedure does not affect the use of the fuel assembly lifting mechanism and does not increase the possibility of improper loading of a fuel bundle.

It requires the use of fuel verification procedures and fuel transfer

. documents.

Additionally, it does not change the configuration of the fuel stored in the spent fuel pool.

.