ML20059N934: Difference between revisions

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| number = ML20059N934
| number = ML20059N934
| issue date = 09/30/1990
| issue date = 09/30/1990
| title = Monthly Operating Rept for Sept 1990 for Hope Creek Unit 1. W/901015 Ltr
| title = Monthly Operating Rept for Sept 1990 for Hope Creek Unit 1
| author name = Johnson C, Zapolski M
| author name = Johnson C, Zapolski M
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY

Latest revision as of 19:57, 6 January 2021

Monthly Operating Rept for Sept 1990 for Hope Creek Unit 1
ML20059N934
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/30/1990
From: Clay Johnson, Zapolski M
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HSE-90-342, NUDOCS 9010240129
Download: ML20059N934 (11)


Text

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h g pggg Pubhc Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08030 Hope Creek Generating Station October 15, 1990 HSE-90-342-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 September are being forwarded to you with the summary of changes, tests, and experiments for September 1990 pursuant to the requirements of 10CFR50.59(b).

Sincerely-pours, C. Pf ,dohnson Gengral Manager -

Hope Creek Operations QAh:ld

-Attachments C Distribution AII g R -

f. gn= gov eeopie. in e_ -. DS P173 (5M) 12 B8

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INDEX NUMBER SECTION OF PAGES Average Daily Unit Power Level. . . . . . . . . . . 1 Operating Data Report . . . . . . . . . . . . . . . 3 Refueling Information . . . . . . . . . . . . . . . 1 Monthly Operating Summary . . . . . . . . . . . . . 1 Summary of Changes, Tests, and Experiments. . . . . 3 e

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AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO. 50-354 UNIT Hoce Creek DATE 10/15/90.

COMPLETED BY M. Zanolski ,

TELEPHONE (609) 339-3738 I i

l MONTH Seotember 199,Q

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)  ;

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1. 1921- 17.- 1047
2. 1046 18. 1058 i A. 3. 1027 19. 1053 l
4. 1041 20. 1039 q
5. 1041 21. JR11 l
6. 1033 22. 212 1 L 7. 1025 23. 1049 1
8. 1048 24. 1Ria
9. 1033 25. 1050 l 10. . 1038 26. 1049
11. 1036 ,
27. 1073 i

la. 3031 28. 1031 1'

L 13 . - 1045 29. 1045

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'144 1030 30. 1037 15.. 1222 31.

'16. 1048 i

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OPERATING DATA REPORT 50-354 DOCKET UNITNO.- ~HoDe Creek DATE -9/14/90 COMPLETED BY M. ZaDolski TELEPHONE -

(609) 339-3738 OPERATING STATUS 1.1 REPORTING PERIOD Aucust 1990_ GROSS HOURS IN REPORTING 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) None
4. . REASONS FOR RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE

5. NO. OF HOURS REACTOR WAS CRITICAL 744.0 5515.8 27277.3 6.- REACTOR RESERVE SHUTDOWN HOURS- 0.0 0.0 0.0 7.. HOURS GENERATOR ON LINE 744.0 5479.3 _26'.830.5
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) _2.433.912_ _17.666.457 _84,622.833'
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 798.010 5.826.830 _27.983.093
11. NET ELECTRICAL ENERGY GENERATED

. (MWH) -763.866 5.581.446 _26.737.995

12. REACTOR SERVICE FACTOR 100.0 94.6 84.1
13. REACTOR AVAILABILITY FACTOR 100.0 94.6 84.1
14. UNIT SERVICE FACTOR 100.0 94.0 82.8
15. UNIT AVAILABILITY FACTOR 100.0 94.0 82.8
16. UNITECAPACITY FACTOR

.(Using MDC) 99.6 92.8 80.0

17. . UNIT' CAPACITY FACTOR (Using Design MWe) 96.2 89.7 77.3 18 .- UNIT, FORCED. OUTAGE RATE 0.0 3.6 5.2 J19. SHUTDOWNS SCHEDULED OVER.NEXT 6 MONTHS (TYPE, DATE, & DURATION):

Refueling, 12/26/90, 50 days

~2 0. : IF' SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP:

N/A II

OPERATING DATA REPORT DOCKET No. 50-354 UNIT Hope Creek DATE- 10/15/90 COMPLETED BY M. Zanolski TELEPHONE (609) 339-3738 OPERATING STATUS l'. Reporting Period Sentember 1990 Gross Hours in Report Period 222

2. Currently Authorized Power Level (MWt) 1111 Max. Depend. Capacity-(MWe-Net) 1921 Design Electrical Rating (MWe-Net) 1067
3. Power Level to which restricted (if any) (MWe-Net) Egna 4 '. Reasons for restriction (if any)

This Yr To Month Data Cumulative

5. No. of hours reactor was critical 720.0 6235.8 27.997.3
6. Reactor reserve shutdown hours AzQ 222 azQ
7. Hours generator on line 720.0 6199.3 27.550.5 8.~ Unit reserve shutdown hours 222 AzQ AzQ
9. Gross thermal energy generated. 2.366.511 20.032.968 - 86.989.344 (MWH).
10. Gross electrical energy 782.480 6.609.310 28,765.573 generated (MWH)
11. Net electrical energy generated 749.563 6.331.009 27.487.558 (MWH)
12. Reactor service factor 100.0 21x2 Razi
13. Reactor availability factor 100.0 2522 RAzh
14. Unit service factor 100.0 94.6 1221
15. Unit availability factor' 100.0 94.6 1221
16. Unit capacity factor-(using MDC) 101.0 1111 ggzi il7. Unit capacity factor 2L_q EQts 77.7 (Using. Design MWe)
18. Unit forced outage rate 22Q aza 121-
19. Shutdowns scheduled over next 6 months (type, date, & duration):

Refueling, 12/26/90,.50 days

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

N/A

OPERATING DATA REPORT.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-354 UNIT Hone Creek DATE 20/15/90 COMPLETED BY- M. Zapolski TELEPHONE (609) 339-3738

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MONTH September 1990 METIiOD OF SHUTTING POWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S= SCHEDULED (HOURS) (1) POWER (2) ACTION / COMMENTS NONE

' summary

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REFUELING ~INFORMATION l

1 DOCKET NO. 50-354-UNIT HoDe Creek j DATE 10/15/90 '

t COMPLETED BY: C. Brennan TELEPHONE (609)-339-1232- .

MONTH September 1990

1. . Refueling information has changed from last month:

Yes No X

2. Scheduled date for next refueling: 12/26/90 .

-3 Scheduled date for restart following refueling: 02/13/91'

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

4 Yes No X  ;

B. Has the reload fuel design been reviewed by the Station

, Operating Review Committee?

E  !

Yes No X If.no, when is it scheduled? not current 1v schedule'd l h 5. Scheduled date(s) for submitting. proposed licensing' action: N/A 1

L 6. 'Important licensing considerations associated with refueling:

i L - Amendment 34 to the Hope Creek Tech Specs allows the cycle L

' specific operating limits to be incorporated into the. CORE u OPERATING LIMITS REPORT; a submittal is therefore not a L required. . j l

j 7. Number of Fuel Assemblies: ,

? A'. Incore .

261  ;

B .' In Spent Fuel Storage (prior to refueling) A21-  !

C. In Spent Fuel Storage (after refueling) 2ff~ f i

8. _Present licensed spent fuel storage capacity: 4006 l

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Future. spent-fuel storage capacity: 4006 .

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9. Date of'lastorefueling that can be discharged July 22. 2007 to spent fuel-pool-assuming the present licensed capacity:

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__~_ _.______________________i___.______________.__._____

i HOPE CREEK GENERATING STATION l

MONTHLY OPERATING

SUMMARY

SEPTEMBER 1990 Hope Creek entered the. month of September at approximately 100%

. power. The-unit operated throughout the month without-experiencing any shutdowns or reportable power reductions. On September 30 th power operat1on.e plant completed its 187th day of continuousHope Creek's previous lon 175 days.

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SUMMARY

OF' CHANGES, TESTS,.AND EXPERIMENTS

.FOR THE HOPE CREEK. GENERATING STATION SEPTEMBER 1990

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The following Temporary Modification Request (TMR) has been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety R 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- t

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

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The TMR did not create a new safety hazard to the plant nor did it- ..'

affect the safe shutdown of the reactor. The TMR did not change l

the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluation determined that no unreviewed safety or environmental questions are involved.

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.TME: Descrintion of Temocrary Modification Recuest 10 = 90-050 This-TMR added a jumper to the-High oil Temperature Switch in the "A" Control Room Water Chiller.: The

-jumper willidisable the High Bearing 011~

Temperature' trip; but will permit the chiller to operate until replacement parts can-be installed.

Equipment. Operators will monitor the oil-temperatures as a compensatory measure.

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