ML20045H204
| ML20045H204 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/30/1993 |
| From: | Hollingsworth, Hovey R, Zabielski V Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9307190214 | |
| Download: ML20045H204 (11) | |
Text
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O PSEG Put$c Service Electnc and Gas Cornpany P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station July 12, 1993 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 June are being forwarded to you with the summary of changes, tests, and experiments that were implemented during June 1993 pursuant to the requirements of 10CFR50.59(b).
Sincerely yours, ti Aj l
l R. J.
Hovey General Manager -
l Hope Creek Operations DR:pw Attachments C
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9307190214 930630 i;
PDR ADDCK 05000354 h 3sen psw unr, R
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4 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.
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1 OPERATING DATA REPORT DOCKET NO.
50-354 UNIT Hope Creek j
DATE 7/12/93 i
COMPLETED BY V.
Zabielski TELEPHONE (609) 339-3506 OPERATING STATUS 1.
Reporting Period June 1993 Gross Hours in Report Period 21Q 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 720.0 4262.0 48517.6 6.
Reactor reserve shutdown hours 2x2 222 Aug 7.
Hours generator on line 720.0 4242.0 47747.8 8.
Unit reserve shutdown hours 22Q 222 0.0 9.
Gross thermal energy generated 2364807 13754927 151968145 (MWH)
- 10. Gross electrical energy 778440 4604360 50352414 generated (MWH)
- 11. Net electrical energy generated 744931 4407788 48110172 (MWH)
- 12. Reactor service factor 100.0 98.1 84.8
- 13. Reactor availability factor 100.0 98.1 84.8
- 14. Unit service factor 100.0 97.7 83.4
- 15. Unit availability factor 100.0 97.7 83.4
- 16. Unit capacity factor (using MDC) 100.4 98.4 81.5
- 17. Unit capacity factor 97.0 95.1 78.8 (Using Design MWe)
- 18. Unit forced outage rate 22R 121 4.6
- 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
OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-354 UNIT Hope Creek DATE 7/12/93 COMPLETED BY V.
Zabielski TELEPHONE (609) 339-3506 i
MONTH June 1993 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F= FORCED DURATION REASON REDUCINJ CORRECTIVE NO.
DATE S= SCHEDULED (HOURS)
(1)
POWER (2)
ACTION / COMMENTS 0
0 none t
D t
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-354 UNIT Hone Creek DATE 7/12/93 COMPLETED BY-V.
Zabielski TELEPHONE (609) 339-3506 MONTH June 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
1048 17.
ISJ&
2.
1051 18.
1025 3.
1045 19.
1023 4.
1058 20.
2005 5.
1031 21.
1029 6.
1082 22.
1025 7.
1015 23.
1007 8.
1041 24.
1034 9.
1020 25.
1071 10.
1031 26.
1026 11.
1026 27.
1027 12.
1043 28.
1027 13.
1036 29.
1025 14.
1038 30.
1051 15.
1034 31.
N/A 16.
1028
REFUELING INFORMATION DOCKET NO.
50-354 UNIT Hone Creek 1 DATE 1-July 93 COMPLETED BY S.
Hollinosworth TELEPHONE (609) 339-1051 MONTH July 1993 1.
Refueling information has changed from last month:
Yes No X 2.
Scheduled date for next refueling:
3/5/94 3.
Scheduled date for restart following refueling:
4/23/94 4.
A.
Will Technical Specification changes or other license amendments be required?
Yes No X
B.
Has the Safety Evaluation covering the COLR been reviewed by the Station Operating Review Committee?
l Yes No X
If no, when is it scheduled?
2/18/94 5.
Scheduled date(s) for submitting proposed licensing action:
Egt scheduled yet.
6.
Important licensing considerations associated with refueling:
N/A 7.
Number of Fuel Assemblies:
A.
Incore 764 B.
In Spent Fuel Storage (prior to refueling) 1008 C.
In Spent Fuel Storage (after refueling) 1240 8.
Present licensed spent fuel storage capacity:
4Q05 Future spent fuel storage capacity:
4006 9.
Date of last refueling that can be discharged 5/3/2006 to spent fuel pool assuming the present (EOC13) licensed capacity:
(Does allow for full-core offload)
(Assumes 244 bundle reloads every 18 months until then)
(Does H2t allow for smaller reloads due to improved fuel)
a h0PE CREEK GENERATING STATION MONTHLY OPERATING
SUMMARY
June 1993 Hope Creek entered the month of June at approximately 100% power.
The unit operated throughout the month without experiencing any shutdowns or. reportable power reductions.
As of June 30, the plant has been on line for 42 consecutive days.
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION June 1993 The following items 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 10CFR50.59 Safety Evaluations 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 that no unreviewed safety or environmental questions are involved.
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IMB Descrintion 2f Safety Evaluation This TMR installs jumpers in panels 1A-C-102,ip1B-C-93-012 102 and 1C-C-102 to jumper out hi/hi level tr switches (1AFLSHH-1453A,B,C and 1AFLSHH -1481A,B,C) for #2 feedwater heater.
These jumpers do not affect any safety related components or systems.
These switches cause a spurious high level trip signals during low power levels due to inleakage in the reference leg.
Once the level signals have stabilized, the jumpers were removed.93-013 This TMR installs a jumper in Panel 10-C-623 which disables 1BGTISH-N008.
This temperature switch isolates valve 1BGHV-F004 on high regenerative heat exchanger outlet temperature.
This isolation ic to protect the RWCU Filter /Demin resin from damage due to high temperature.
Disabling the temperature switch will allow 1BGHV-F)004 to be opened.
This will not prevent the isolation signal on RWCU non-regenerative heat exchanger high outlet temperature.
This T-Mod will not affect any other 1BGHV-F004 isolation signals,93-017 This TMR affects the 2" copper drain piping which drains condensate from the following HVAC Units: 1A-VH407, 1B-VH407, 1A-VH406, 1B-VH408 and 1A-VH401 to 1D-VH401.
These HVAC Units are the Control Equipment Room Supply Units, 1E Panel Room Supply Units and the Switchgear Room Supply Units.
This change re-routes the condensate via tygon tube to a Chemical Waste drain approximate 2ft. from the currently used Normal Waste drain.
The sources and the destination of the waste water will remain unchanged.
However, by re-routing the condensation through the Chemical Waste portion of the system, copper impurities may be removed from the water at the Neutralization Tank.
This will remove some copper sources to LVOW and reduce the possibility of future NJPDES permit exceedances.
THB CONT.
DescriDtion gf Safety Evaluation 93-018 This TMR installs a temporary pipe clamp on a 3" diameter Instrument Air Pipe which exhibits a small leak at a " TEE" joint until such time as it is reworked or repaired.
The are will be reinforced with a pipe clamp bolted around the pipe and a clamp l
between a riser and existing support to prevent joint blowout.
This addition of this pipe clamp and restraint is a change to the facility in that it goes beyond the pipe design criteria requirements for the system as referenced on UFSAR Figure 9.3-1 (pipe class JDD).
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Descrintion 21 Safety Evaluation 1
4EC-03348 This DCP installs a throttle valve in the HB System Pkg 8 Radwaste Evaporator Recirc Pump (OA/B-P-352) discharge to add system resistance so that the pump can operate at an adequate point on its curve.
An 18" pipe must be cut so that flanges can be installed to provide access for the valve.
The valve is manual; no controls or interlocks are invol'/ed.
An orifice is also being installed upstream of the throttle valve to decrease the required loss across the throttle valve.
This DCP changes the facility as described in the SAR since the modification results in a revision to HB System P&ID.
The design bases for the Radwaste Evaporator are described in UFSAR Section 11.2.2.2.5 and Figure 11.2-5 sht 2 of 2.
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