ML20086N148
| ML20086N148 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/30/1991 |
| From: | Hagan J, Hollingsworth, Zabielski V Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9112190040 | |
| Download: ML20086N148 (12) | |
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i C PSEG Putac Semte fleune n10cis Ct.mpm>v r o fu :% Hmg om,INy Ne A Jmey OtKGB Hope Cf uk Generating Stubon December 13, 1991 U. S. 11uclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sirs MoliTilLY OPERATIl1G REPORT 110PE CREEK GEllERATIOli STATIolf U111T 1 DOCKET 110. 50-354 In complianco with Section 6.9, Reporting Requirements for the llope Crook Technical Specifications, the operating statistics for liovember are being forwarded to you with the nummary of changen, tests, and experiments for 11ovember 1991 pursuant to the requiroments of 10CFR50.59(b).
Sincor y yours, 7[n%
.J lia an Gen.ral anager -
h flope Qr ok Operations b' Q-R Id Attachments C
Distribution 100004
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911;;190040 911110 l
PDR fiDOCK 05000354 A
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I11DEX NUMBER SECTION OF...PAGIS Average Daily Unit Power Lovel.
1 Operating Data Report.
2 Refueling Information.
1 Monthly operating Summary.
1 Summary of changes, Tests, and Experiments.
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t' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-354 i
UNIT lione creek DATE 12/13/91 COMPLETED BY V.
Zabielski l
TELEPilONE (609) 339-3506 i
MONTil November 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWo-Not)
-1.
1051 17.
1054 2.
1047.
18.
1058 3.
1911 19.
19f2.
4.
1066 20.
1931 5.
125.1 21.
12A1 6.
.1058 22.
1049*
7.
2001 23, 1922 8.
1061 24.
1044 9.
1058 25.
1047*
10.
1054 26, 1059*
11.
1051 27.
1058 12.
1061 28.
1051 13.
1057 29.
1045 14.
1060 30, 1010 35.
1052 31.
HLA 16..
1QE2
- Estimated values, accurate motor readings were unavailable, i
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l OPERATING DATA REPORT DOCKET No.
50-354 UNIT Hone Creek DATE 12/13/91 COMPLETED DY V.
Zabielski TELEPHONE (609) 339-3506 OPERATING STATUS 1.
Reporting Period Hovember 1991 Gross Hours in Report Period llQ 3.
currently Authorized Power Level (MWt) 1111 Max. Depend. Capacity (MWe-Net) 1031 Design Electrical Rating (MWu-Not) 1067 3.
Power Level to which restricted (if any) (MWe-Not)
H2DA 4.
Reasons for restriction (if any)
This Yr To lignth QRg Cumulative 5.
No. of hours reactor was critical 112x2 6635.8 36.417.3 6.
Reactor reserve shutdown hours quQ 212 Q22 7.
Hours generator on line 720.0 SE)1th 35.830.6 8.
Unit reserve shutdown hours Axq 222 Ain 9.
Gross thermal energy generated 2.374.275 21.220.775 113.763.182 (MWH)
- 10. Gross electrical energy 788.000 6.988.361 37.610.034 generated (MWH)
- 11. Not electrical energy generated 757.231 6.683.719 35.940.403 (MWH)
- 13. Reactor service factor 1QQxQ 82.8 RA29
- 13. Reactor availability factor 100.0 B2_sa 84.0
- 14. Unit service factor 100.0 S125 R2xn
- 15. Unit availability factor 100.0 81.6 alts
- 16. Unit capacity factor (using MDC) 102.0 80.9 3D21
- 17. Unit capacity factor 2121 78.1 77.7 (Using Design MWe)
- 18. Unit forced outage rate 222 ixi fal
- 19. Shutdowns scheduled over next 6 months (type, date, & duration):
None
- 30. If shutdown at end of report period, estimated date of start-up:
N/A I
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OPERATING DATA ItEPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKL"r NO.
50-354 UNIT liong_ Creek DATE 12/13/91 COMPLETED BY V. ZabittlaKL TELEPilONE f609) 339-3'JS1 j
MONTl! Noveraber 1991 METilOD OF SilUTTING DOWN Tile TYPE REACTOR OR F= FORCED DURATIOli REASON l'fDUCING CORRECTIVE NO.
DATE S=ScilEDULED (llOURS)
(1)
POWER (2)
ACTION / COMMENTS Nono.
-Summary
e REFUELING INFORMATIOh DOCKET MO.
50-354 UNIT Hppe Creek DATE 12/13/9:
COMPLETED BY E. HollLnggyQrlh TELEPilONE (609) 339-1051 MONTH November 1991 1.
Refueling information has changed from last month:
Yes No 8
Scheduled date for next_ refueling:
t/12/92 3.
Scheduled date for restart following refueling:
11/11/92 4.
A.-
Will Technical Specification changes or other license amendments be required?
Yes No X
Br lias the reload fuel design been reviewed by the Station Operating Review committee?
Yes No X
If no, when is it scheduled?
not schedulqd (on or prior to 7/24/92) 5.-
Scheduled date(s) for submitting proposed licensing action:
HLA 6.
Important licensing considerations associated with refueling
- Same fresh fuel as current cycle:
no new considerations 7.
Number of Fuel Assemblies:
A.
Incore 151 B.. In Spent Fuel Storage (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 11/4, 2010 to spent fuel pool assuming the present (EOC16) licensed capacity:
1
!! OPE CREEK GENERATING STATION MONTilLY OPERATING
SUMMARY
i November 1991 Hope Creek entered the month of November at approximately 100%
power and operated for the entire month without experiencing any shutdowns or reportable power reductions.
On November 30, the plant completed its 203rd day of continuous power operation.
SUMMARY
Or Cl!ANGES, TESTS, AND-EXPERIMENTS FOR Tile il0PE CREEK GENERATING STATION HOVEMBER 1991 t
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The following. items havo been' evaluated to_ determine
- 11. :- If the: probability of occurrence _or-the consequences of an accident-'or malfunction of: equ pment -important to-safety previously evaluated in the sa ety 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.c If the-~ margin of: safety as defined in the basis for any technicel-specification-is reduced.
The-10CFR50.59= Safety Ev luations 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 thht-no unreviewed safety.or environmental questions-are involved.
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s Procedure Revision Eggerintion of Safety Evaluation HC.RE.RW-ZZ-0001(Q)
This procedure describes the special care Rev.
O used in handling and storing highly radioactive material.
The procedure provides guidance for an annual inventory of the highly radioactive material stored in the Spent Fuel Pool and gives guidance for removing or rolocating the highly radioactive material stored in the Spent Fuel Pool.
All movement of highly radioactive material will be done with either the Refuel Bridge Holst or the Iv'otor Building Polar Crane.
This procedure prohibits carrying objects over spent fuel without verifying Secondary Containment.
It also prohib(ts carrying loads over 1200 pounds over triel assemblies.
Consequently, t. hic proceduce does not increase the probability of dropping material onto stored spant fuel.
This procedure does not increase the possibility of a loss of Fuel Pool level because of t'.9 design of the Spent Fuel Pool.
All highly radioactive material stored in accordance with this procedure is stored below the top of the Spent Fuel Racks; therefore, a loss of Fuel Pool level is not made more severe by this procedure.
Due to the above reasons, this procedure does not involve an Unreviewed Safety Question.
NC.NA-AP.ZZ-002S(Q)
This procedure describes the controls Rev.
O established for the erection, inspection, and storage of scaffolding.
It also includes controls to handle transient loads and to prevent.the generation of gravitational missiles.
No Unreviewed Safety Questions were involved because this procedure.is in compliance with, and more conservative than, the SAR.
Additionally, the majority of this program was already in place, changes from it are either editorial or have been included to strengthen the program.
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- Procedure Revision Descriotion of Safety Evaluation NC,NA-AP ZZ-0055(Q)-
This procedure describes the outage Rev. --- management program.
- It is a common-procedure that supersedes'a previously approved Hope Creek. procedure.- There are no major-changes from the previous Hope Creek procedure.
No Unreviewed Safety-Questions were involved because this procedure is in-compliance with,-and more. conservative than, the SAR.
Additionally the majority of this program t s already kn place, changes from it are either editorial or have been included to strange the program.-
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. UPSAR Section1 DescriotiOn of Safety-Evaluation
.9.3-This UFSAR Change Notice supports the installation of aving check valves in the
- drain lines from Emergency Core Cooling System rooms to the. Reactor Building Floor Drain-Sumps..This returns the; system to its-original design.
No-Unreviewed Safety Questions wereLinvolved because-several different types of check valves could provide the required-backflow--
prevention.
These valves provide the required backflow protection-and have the required seismic certification.
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