ML20024F812

Monthly Operating Rept for Nov 1990 for Hope Creek Generating Station Unit 1.W/901214 Ltr

ML20024F812
Person / Time
Site:	Hope Creek
Issue date:	11/30/1990
From:	Hagan J, Zapolski M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9012210135
Download: ML20024F812 (14)

Text

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. n psEG Putific Servk o E iectric ard Gas Company P O Ban ?30 Hancocks BrK1ge New Jersey 08038 Hopo Creek Operations December 14, 1990 U. S. 11uclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

MOllTIILY OPERATIl4G ltEPORT llOPE CREEK GEllERAT10!1 STAl' ION UllIT 1 DOCKET 110. 50-354 In compliance with Section 6.9, Reporting Requirements for the llope Crock Technical Specifications, the operating statistics f or 11ovember aro being forwarded to you with the summary of changes, tests, and experiments for 11ovember 1990 pursuant to the requirements of 10CFR50.59(b).

Sincer.ly yours,

. J. Ihgan Gener Manager -

llope Crook Operations Sb AR:IdAttachments C Distribution 3

l 9012210135 901130 PDR ADOCK 05000354 R PDR The Energy Peopk 210077

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INDEX NUMBER SECTION OF PAGES Avorage Daily Unit PoWor Lovel. . . . . . . . . . . 1 Operating Data Report . . . . . . . . . . . . . . . 2 Refueling Information . . . . . . . . . . . . . . . 1 Monthly Operating Summary . . . . . . . . . . . . . 1 Summary of Changes, Tosts, and Experiments. . . . . 7 t

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AVERAGE DAILY UNIT POWER LEVEL  ;

I DOCKET NO. 50-354 UNIT ligpe Creek DATE 12/14/90 COMPLETED BY M. Zanolski TELEPHONE (609) 339-3738 l

MONTH llovember 1990 l l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWo-Not) (MWo-Not)

1. 1124 17. All 3.- 1025 18. 2

3. 1041 19. 21 4.- 2 20. 211

5. p 21. 1055

-6. 2 22. 1062

7. -D 23. 193.1

8. 2 24'.- 1033

9. 2 25.- 10.25

10. a 26. 221

' 11. - 2 27. 1053

12. A 28. . 1912

13. 2 2 9. - lQ11

14. .A 30. 1006

15. 122 31.

16. 212 L . - . . - - . - - - . -_. . . - - - - - - _ - - -

-. . . - . . - .= - - . - - . .-_. _-.-. . . .. . - . .- . . - .

OPERATING DATA REPORT DOCKET NO. 50-354 UNIT Happ Creek DATE 12/14/90 COMPLETED BY M. Zanolski TELEFHONE 1609) 339-3738 OPERATING STATUS

1. Reporting Porlod Epvomber 1990 Gross Hours in Report Period 212

2. Currently Authorized Power Levol (MWt) 3293 Max. Depend. Capacity (MWe-Not) lall Design Electrical Rating (MWo-Hot) 1067

3. Power Lovel to which restricted (if any) (MWo-Net) Nono

4. Reasons for rostriction (if any)

This Yr To Month Dato Cumulative S. No. of hours reactor was critical 437.2 7418.0 29.179.5

6. Reactor reservo shutdown hours 222 222 A22

7. -llours generator on lino 396.6 .. 7340.9 28.692.1

8. Unit reservo shutdown hours M Azq 222

9. Gross thermal energy generated 1.201.978 23.672.603 90.52Et979 (MWH)

10. Gross electrical energy _ 399.000 7.816.330 29.972.593 generated (MWH) 11..Not electrical onergy generated 375.517 7.480.537 28.637.086 (MWil)

12. Roactor service factor 60.7 2122 84.3

13. Reactor availcbility factor 5222 92.5 84.3

14. Unit service factor 55.1 Elis- 82.9

15. Unit availability factor 55.1 91.6 82.9

16. Unit capacity factor-(using MDC) 50.6 2221 Hail

17. Unit capacity factor 48.9 87.5 77.6 (Using Design MWo)

-18. Unit forced outage rato 1f21 111 Ein

19. Shutdowns scheduled over next 6 months (typo, dato, & duration):

Refueling,-12/26/90, 52 days

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

N/A

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et OPERATI!1G DATA REPORT Ul11T SHUTDOW11S A11D POWER REDUCTIO!!S DOCKET 110. 50-354 UllIT liope Creek DATE 12/14/90 COMPLETED BY M. Zapolski TELEPl!OllE f609) 339-3738 MO!1Til 11ovember_1222 METilOD OF SilUTTIllG DOW11 Ti!E TYPE REACTOR OR F= FORCED DURATIO!1 REASO11 REDUCI!1G CORRECTIVE 11 0 . DATE S= Sci!EDULED (l!OURS) (1) POWER (2) ACTIOli/ COMME!1TS 11 11/4 F 270.3 A 3 Inboard MSIV Instrument Gas Leak LER 104/90-024 12 11/17 F 53 A 3 "A" Moisturo Soparator Drain Tank liigh Lovel LER 354/90-028 Summary i

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REFUELING INFORMATION DOCKET NO. AD-354 UNIT Hopo creeh DATE 1R/14422 COMPLETED BY _S . Hollinasworth TELEP110NE (609) 339-1051 MONTil November 1990

1. Refueling information has changed from last month:

Yes X No

7. 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 requirod?

Yoo No X B. Has the reload fuel design been reviewod by the Station Operating Review Committoo?

Yes No X If no, when is it scheduled? not current 1v TA aulgd S. Scheduled dato(s) for submitting proposed licensing action: ElA

6. Important licensing considerations associated with refueling:

- Amondment 34 to the !! ope Crook Toch Specs allows the cycle specific operating limits to be incorporated into the CORE OPERATING LIMITS REPORT; a submittal is therefore not required.

7. Number of Fuel Assemblies:

A. Incore 764 B. In Spont Fuel Storago (prior to refueling) A21 l C. In Spont Fuol Storago (after refueling) 252

. 8.--Prosont licensed spent fuol storage capacity: 4006 Futuro spent fuel storage capacity: 4006 9.- Date of last' refueling that can be discharged July 22, 2007 to spent fuel pool assuming the present i licensed capacity:

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HOPE CREEK GENERATING STATION MONTHLY OPERATING

SUMMARY

$ NOVEMBER 1990 3

Hope Crook ente od the month of November at approximately 100%

power. On Nove bor 4th, the unit automatically shutdown after completing 321 ( Ya af continuous power operation. The ;cc am occurred due to Average Power Range Monitor Fixed Neutron Flux s Upscale, which was initiated by the closure of the "B" Inboard

) Main Steam Isolatio.1 Valve. The Main Steam Isolation Valve j closure resulted from a failed fitting on a Primary Containment Instrument Gas Supply Line to the valve. The unit was returned to service on November 15th. The unit automatically shutdown on November 17th, due to a high level in the "A" Moisture Separator Drain Tank. The unit was returned to service on November 19th, and on November 30th, completed its lith day of continuous power operation.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION NOVEMBER 1990 i'

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The following Design Change Packages (DCP's) have been evaluat.

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 DCP's did not create a new safety hazard to the plant nor did they af fect the safe shutdown of the rear .or. The DCP's did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unroviewed safety or environm9ntal questions are involved.

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LgE; Descrintion of Desian Chance Packace-4EC-3144 This DCP installed a' reinforced concrete retaining

= basin for the' Low Volume' Oily Waste System's Oily Water Separator and Oil Sludge Tank. The installation of the basin-will prevent the.

discharge of oily water to the environment.

4EC-3186- This-DCP-installed additional temporary instrumentation to monitor: vibration levels on the Reactor Recirculation System. Pumps Suction-Elbows =

-- and the' inner and. outer-radius instrument lines attached to the pump suction elbows. The vibration

' monitoring instrumentation will be~used for subsequent testing to measure and record piping strains,: accelerations, and displacements.

4EC-3199 This DCP replaced schedule 40 pipe nipples with schedule 80 pipe nipples. The nipples are connected to_the taps in the aluminum solenoid manifold actuator block of the Inboard Main Steam

- Isolation Valves. The DCP.also-added ...loro and replaced flanges with other-fittings Thit is an upgrade--that_: increases reliability.

4hC-0245/01 This:DCP added.new flow-indicato?1 and heplaced-

- existing pressure indicators. inis will eliminate

- the.need to use portable Measurement and Test Equipment during the performance of-the Diesel Fuel Oil. Transfer 7 Pump. Surveillance Test..

4HM-0654 This DCP modified level switches used to= sense - ,

asphalt level"inside the Extruder Evaporator Stear Domes ~. -The modification will-eliminate the high le"el alarm during-normal 1 operations.

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The following Temporary Modification Requests (TMR's) have been ovaluated to determine:

1. If tha 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 TMR's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. The TMR's did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unroviewed safety or environmental questions are involved.

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-6 -j 1191- Descriotion~of Temocrary Modification Request 90-054 This TMR removed the ovorload heaters from the breakers for the Reactor Water-Cleanup Discharge to-Condenser Valve and the Reactor Water Cleanup Discharge to Equipment Drain Valve. Removing.the overload heaters from the breakers will prevent the valves from-inadvertently opening during an Appendix R fire.90-055 This TMR removed the overload heaters from the breaker for the Residual Heat Removal Outboard Shutdown Cooling Isolation Valve. Removing the overload heaters from the breaker will prevent the-valve from inadvertently opening during an Appendix R fire.90-056 This-TMR-jumpered the High/High Level Trip from the

1. 2 "A",. "B", and "C" Feedwater Heaters. Spurious High Level signals have been observed at low power levels due to inloakage in the reference legs.

This TMR was installed only.until the level signals stabilized.-

90-057. -This TMR jumpered the High/High Level Trip from the

/2 "A", "B", and-:"C" Feedwater Heaters. Spurious High Level signals have been observed at low power levels due to inleakage in the reference-legs.

This-TMR was installed only until-the level signals stabilized.90-072 This TMR removed the-overload heaters from the ~

breakers for the Reactor Water Cleanup Discharge to Condenser Valve and the Reactor Water Cleanup Discharge to Equipment Drain Valve. . Removing the overload heaters from the breakers will prevent:the valven-from inadvertently opening during an Appendix R fire.

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The following procedure revisions have been evaluated to j determine:

1. If the probability of occurrence or the consequences of an accioent or malfunction of equipment important to safety previously evaluated in the safety analysi.4 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 procedure revisions did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. The procedure revisions did not change the plant effluent releases and did not alter the existing environmental impact. The Safety Evaluations determined that no unroviewed safety or environmental questions are involved.

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.- ' .? y Procedure .

Revision Description of Procedure Revision 1 NC.NA-AP.ZZ-0001(Q) _This procedure revision moves material to Rev. 2 NC.NA-AP.ZZ-0032(Q) and makes several other changes that are administrative in nature.  ;

This revision also added'a new topic, the Nuclear Department Procedure System, to Section 13.5 of the UFSAR.

NC.NA-AP.ZZ-0003(Q) This procedure describes the document Rev. O control program for the PSE&G Nuclear Department. It changes the overall responsibility for the document control program from the Station General Manager to the General Manager - Information Systems and External Affairs.

NC.NA-AP.ZZ-0032(Q) This procedure describes the new process Rev. O for preparing, reviewing, and approving procedures. This procedure requires a change to Section 13.5 of the UFSAR because it refers to Nuclear Administrative Procedures rather than-to Station Administrative Procedures.