ML20082G922
| ML20082G922 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/31/1991 |
| From: | Hagan J, Zabielski V Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9108220095 | |
| Download: ML20082G922 (16) | |
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.J August'9, 1993 O. S. Nuclear Hogulatory Comminnion Document Control Doak washington, DC 20555 Dear Sir l
MONTilLY OPERATING REPORT llOPE CREEK GENERATION. STATION UNIT 1 DOCKET NO. 50-354 In complianco with Section G.9, Reporting Requiromantn-for-the liopo crook Technical Specifications, the oporating utatlatico for July aro boing forwarded toLyou with the nummary of changon, tontu, and experimentn for. July 1991 pursuant to the requiromonto of -10CFR50.59 (b).-
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INDEX NUMBER HECTION QF PAGES Average Daily Unit Power Level.
1 0porating Data Report.
2 Refueling Information.
1 Monthly operating Summary.
1 Summary of Changes, Tests, and Experiments.
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AVERAGE EAILY UNIT POWER LEVEL DOCKET
- 50-354 Hone Creek 8/9/9:
COMPLET.
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Zab:.eloki TELEPilONE (609) 339-3506 MONTH July 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Not)
(MWo-Net) 1.
1208 17, 1024 2.
1QH 18.
2006 3.
1Q.11 19.
1047 4.
1068 20.
1Q22 5.
1016 21.
1033 6.
1003 22.
1023 7.
1006 23.
122 8.
Sil 24.
1033 9.
H2s 25.
1031 10.
212 2 6..
1007 l
11.
1055 27.
1023 12.
22.2 28, 1015
.13. -
1013 29.
1029 14.
1T2 30.
- 1027, 15.
1034 31.
1067
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1 16.
1017 Due to various errors in recording the meter readings,-the exact average daily power levels for several oays.are unknown.
The. average for the month is correct.
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OPERATING DATA REPORT DOCKET NO.
50-354 UNIT Uppp_ Creek DATE
_Bj9/9:
COMPLETED SY V.
Zab:.elski TELEPHONE 1b09) 339-3506 OPERATING STATUS 1.
Reporting Period Juiv 1991 Gross Hours in Report Period 11A 2.
Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity 1031 Design Electrical Ratin(MWe-Net) g (MWe-Net) 2211.
3.
Power Level to which restricted (if any) (MWe-Net)
None 4.
ReLsons for restriction (if any)
^
This Yr To Month Date Cumulative 5.
No. of hours reactor was critical 744.0 3706.8
.33.488.3 6.
Reactor reserve shutdown hours 922 222 Ema 7.
Hours generator on line 744.0 3608.5 32.901.6 8.
Unit reserve shutdown hours 222 922 Exp 9.
Gross thermal energy generated 2.451.817 112 575.975 104.118.383 (MWH)
- 10. Gross electrical energy 803.330 3.810.891 34.432.554 generated (MWH)
- 11. Net electrical energy generated 758.590 3.638.628 32.895.312 (MWH)
- 12. Reactor service factor 1QQuq 72.9 82.8
- 13. Reactor availability factor 100.0 72.9 82.8
- 14. Unit service factor 100.0 70.9 81.4
- 15. Unit availability factor 100.0 70.9 81.4
- 16. Unit capacity factor (using MDC)
.100.2 1221 78.9
- 17. Unit capacity factor 96.8 67.0 76.2 (Using Design MWe)
- 18. Unit forced outage rate 222 222 Et1
- 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
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OPERATING DATA REPORT UNIT S!!UTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-354 UNIT lione Creek D?.TE 8/9/91 COMPLETED BY V. Zabielski TELEPilONE f609) 339-3506 MONTH July 1991 METHOD OF SilUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO.
DATE S=SC11EDULED (HOURS)
(1)
POWER (2)
ACTION / COMMENTS NONE N
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1 Summary _
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REFUELING INFORMATION DOCKET NO.
50-354 UNIT Hong_ Creek DATE 8/9/91 COMPLETED BY S.
Hol1ingD_WQILb TELEPHONE (609) 339-1051 MONTH July 1991 1.
Refueling information has changed from last month:
Yes X
No 2.
Scheduled dato for next refueling:
9/5/92 3.
Schedulod dato for restart following refueling:
11/4/92 4.
A.
Will Technical Specification changes or other licenso amendments be required?
Yes No X
B.
Han the reload fuel design boon reviewed by the Station Operating Review Committoo?
Yes No X
If no, when is it scheduled?' not scheduled (on or-prior to 7/24/92) 5.
Scheduled dato(s) for submitting proposed licensing action:
HlA 6.
Important licensing considerations associated with refueling:
- Samo fresh fuel as current cycle:
no now considerations 7.
Number of Fuol Assemblies:
l A.
Incore 764 l
B.-
.In Spent Fuel Storago (prior to refueling)-
212 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
' July 22. 2007 l
to spent fuel pool assuming the present (EOC14) licensed capacity:
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!! OPE CREEK GENERATING STATION MONTIILY OPERATING
SUMMARY
July 1991 Hope Creek entered the month of July at approximately 100% power and operated for the entire month without experiencing any shutdowns or reportable power reductions.
On July 31, the plant completed its 80th day of continuous power operation.
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SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION JULY 1991 4.
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f The following Design Change Packages (DCP's) 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 DCP's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor.
The DCP's did not change the plant effluent releases and did not alter the existing environmental impact.
The Safety Evaluations determined that no unreviewed safety or environmental questions-are involved.
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9 DC1' Df31Crl11k1QIL9 f_DRS190_C h 0 D GLhtch a99 4EC-3010 Thin DCP upgraded the Cooling Tower Hanin Wator Temperaturo Monitoring Inntrumont Loop by adding four tronomittorn, a nignal roulutor unit, and n signal nummator.
The previous temperaturo monnuromont mothod renultod in inaccurato valuun duo to the difficulty involved in compennating tho tranumitter lond wiro ronistancop with n ninglo calibration.
In the now configuration, each transmitter output uignal in noparately enlibrated.
The uignal nummator will provido a truo repronontation of tho instantaneoun averago cooling Tower Bauln Water tempornturo.
411C-02 00 Thin DCP provided a maintenanco platform at a accurity enmora at the Sorvico Water Intako Structuro.
Tho uccurity camora lu not affected by the DCP.
41tC-0290/ 04 Thin DCP installed redundant Cooling ToWor Blowdown Monitoring equipment.
Thin includon n Chlorino Analyzer Samplo Station and a coolir.g Tower lilowdown Tomparaturo Recording Loop in the Dochlorinntion Syntom and n atrip chart recordor in the Low Volumo Olly Wauto Syntom.
Thin equipmont in requirod to conform with the !!cw Jorooy Pollutanto Diochargo Elimination Byatom parmit.
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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 previously evaluated in the safety analysis report may be increased; or a
2.
If a possibility for an accident cr malfunction of a dif ferer.t 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 did not create a Jafety hazard to the plant nor did it affect the safe uhutdown c
, reactor.
The TMR did not change did not alter the existing the plant effluent releases t
environmental impact.
The be ety Evaluation determined that no unroviewed safety or environmental questions are involved.
t THR D_qccription _of Temporary ModifIcatigfLRgqqqat 91-032 This TMR lifted a load and installed a jumper to provent tho /4B Foodwater lleator from tripping on spurioua liigh Wator Loyal signals.
The transmitter providing input to the liigh and liigh/Iligh Lovel Switchen has boon failing and providing spurious signals.
I The following Technical Specification Interpretation has boon ovaluated to datormino:
1.
If the probability of occurrence or the consequences of an accident or malfunction of squipment important to safety previously evaluated in the safety analysis report may bo increased; or 2.
If a possibility for an accident or malfunction of a different type than any eva.uated 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 Technical Specification Interpretation did not create a now safety hazard to the plant nor did it affect the safo shutdown of the reactor.
The Technical Specification Interpretation did not chango the plant offluent releases and did not_ alter the existing environmental impact.
The Safety Evaluation datormined that no unroviewed safety or environmental questions are involved, b
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Tech Spec
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Interpretation Description of Tech Spec Interpret Dtion i
LCO 3.7.1.3.b Tech Spec 3.7.1.3.b states that the ultimate heat sink (Delaware River) shall be OPERABLE with an average river water temperature of less than or equal to 90.S'F.
The Spec is interpreted as stating that the ultimate heat sink is OPERABLE with an average river water temperature of less than or equal to 88.1*F with preplanned actions to adjust the Safety Auxiliaries Cooling System flow for specific design basis accident mitigation.
4 Tno following Updated Final Safoty Analysis Report Chango Notico has boon ovaluated to datormino 1.
If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safoty analysis report may be increasod; 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 Updated Final Safety Analysis Report Chango Notice did not create a now safety hazard to the plant nor did it affect the safo shutdown of the reactor.
The Updated Final Scfoty Analysis Report Chango Notico did not change the plant offluent releases and did not alter the existing environmental impact.
The Safety Evaluation determined thr.t no unroviewed safety or environmental questions are involved, s
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UFSAR Section Descrintion of UPSAR Chance 1.8.1.88 The UFSAR is being modified to take the following exceptions to the requirements for a Records Storage Facility:
comply with NFPA 232-1991 instead of NFPA 232-1975 inclusion of a cable tray, enclosed with a three-hour rated symmetrical wrap system to assure its presence will not offect the room contents or fire protection features inclusion of drainage lines and ventilation ducts, along with fire dampers and a drip pan to minimize the potential for the inadvertent wetting of records.
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