ML20196A151
| ML20196A151 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/31/1999 |
| From: | Bezilla M, Todd F Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N99301, NUDOCS 9906220136 | |
| Download: ML20196A151 (6) | |
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OPSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge. New Jersey 08038-0236 Nuclear Business Unit JUN151999 LR-N99301 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
MONTHLY OPERATING REPORT HOPE CREEK GENERATING 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 May 1999 are being forwarded. Also being forwarded to you, pursuant to the requirements of 10CFR50.59(b), is the summary of changes, tests, and experiments that were implemented during May 1999.
Sincerely, 7
/
~
s Mark B. Bezilla 7
General Manager -
J' 2 p Hope Creek Operations RAR Attachments C Distribution 9906220136 990531 PDR ADOCK 05000354 R
PDR Tirjowrisiniourimis.
95-2168 REV 6,94
i INDEX NUMBER
'SECTION OF PAGES O pe ra ting D at a Repo rt............................................................................ 1 Monthly Operating Summary.................................................................... 1 Summary of Changes, Tests, and Experiments........................................ 2
DATE: 06/11/99 COMPLETED BY: F.Todd TELEPHONE: (609) 339-1316 Reporting Period May 1999 OPERATING DATA REPORT Desi n Electric &l Rating (MWe-Net)
C Maximum Dependable Capacity (MWe-Net) 1031 Wlonth Year-to-date Cumulative No. of hours reactor was critical 744 l 2542 l 91671 l
No. of hours generator was on line (service 744 l2501 90111 hours) l Unit reserve shutdown hours 0
l0 l0 l
Net Electrical Energy (MWH) 767837 l 2538676 l 91136197 l
UNIT SHUTDOWNS NO.
DATE TYPE DURATION REASON METHOD OF CORRECTIVE ACTION /
F= FORCED (HOURS)
(1)
SHUTTING COMMENT S= SCHEDULED DOWN THE REACTOR (2)
(1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip / Scram C - Refueling 3 - Automatic Trip / Scram D - Regulatory Restriction 4 - Continuation E - Operator Training / License Examination 5 - Other (Explain)
F - Administrative G - Operational Error (Explain)
H - Other
e DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 06/11/99 COMPLETED BY: R. Ritzman i
TELEPHONE: (609) 339-1445 l
Summary Of Monthly Operating Experience j
Power was reduced on May 12 for Main Condensor Tube repairs. Power was restored to 100% on May 13.
At the end of the month, Hope Creek had been online for 61 days.
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DOCKET NO.:50-354 UNIT: Hope Creek DATE:06/11/99 COMPLETED BY:R. Ritzman TELEPHONE: (609)339-1445
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH May 1999 The following items completed during May 1999 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 environmentalimpact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
Design Changes Summary of Safety Evaluations 4EC-3658, Package 1, Plant Historian. This design change installed a plant historian system to collect data from the Control Room Indicator Display System (CRIDS) and store the data for historical information.
The plant historian system is not safety-related and is not required for the safe shutdown of the plant. A failure of the plant historian interface cards can only affect CRIDS, which also is not safety-related and is not required for the safe shutdown of the plant. The plant historian does not affect any previously evaluated accidents and does not introduce any new accidents. The plant historian meets the guidelines established
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS
,c FOR THE HOPE CREEK GENERATING STATION - Cont'd by EPRI and the FCC guidelines for EMI/RFI emissions. There are no seismic concerns and no heat load impacts on control room habitability. Therefore, this design change does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and; therefore, does not involve an
{
Unreviewed Safety Question.
Temporary Modifications Summary of Safety Evaluations There were no reportable changes in this category implemented during May 1999.
Procedures Summary of Safety Evaluations There were no reportable changes in this category implemented during May 1999.
UFSAR Change Notices Summary of Safety Evaluations There were no reportable changes in this category implemented during May 1999.