ML20210U472
| ML20210U472 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/31/1999 |
| From: | Bezilla M, Ritzman R, Todd F Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N99390, NUDOCS 9908200121 | |
| Download: ML20210U472 (6) | |
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l O PSIEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit I
41B13 see LR-N99390 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 July 1999 are being fonvarded. 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 July 1999.
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Sincerely, Mark B. Bezilla Vice President - Operations RAR Attachments
,I C Distribution
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200012 9908200121 990731 PDR ADOCK 05000354 R
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INDEX NUMBER l
SECTION OF PAGES Ope ratin g D ata Repo rt.............................................................................. 1 Monthly Operating S um ma ry..................................................................... 1 Summary of Changes, Tests, and Experiments........................................ 3 l
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DATE: 08/12/99 COMPLETED BY: F.Todd TELEPHONE: (609) 339-1316 Reporting Period July 1999 1
I OPERATING DATA REPORT l
Design Electrical Rating (MWe-Net)
Maximum Dependable Capacity (MWe-Net) 103 Month Year-to-date Cumulative i
No. of hours reactor was critical 744 l 4006 l 93135 l
l No. of hours generator was on line (service 744 I'8965 91575 l
hours) l l
Unit reserve shutdown hours 0
10 l0 j
Net Electrical Energy (MWH) 760354 l 4031302 l 92628823 UNIT SHUTDOWNS NO.
DATE TYPE DURATION REASON METHOD OF CORRECTIVE ACTIONI l
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 - ManualTrip/ 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
DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 08/12/99 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445 Summary Of Monthly Operating Experience At the beginning of July, Hope Creek was operating at approximately 100%
reactor power.
. ~ On July 1, power was reduced due to a reactor feedpump trip. Power was restored to 100% on July 2.
On July 24, power was reduced to perform turbine control valve testing.
Power was restored to 100% that same day.
At the end of the month, Hope Creek had been online for 122 days.
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3 DOCKET NO.:50-354 UNIT: Hope Creek DATE:08/12/99 COMPLETED BY:R. Ritzman TELEPHONE: (609)339-1445
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE HOPE CREEK GENERATING STATION MONTH July 1999 The following items completed during July 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-3667, Package 1, Control Room Console Upgrade. This design change installed new workstations for the Reactor Operators, Control Room Supervisors, and Shift Technical Advisors. This design change also relocated the voice and data communication device; and control, indication, and annunciation functions to the new workstations. This design change required UFSAR drawings and tables to be modified.
The purpose of this design change is to enhance the overall command and control structure and to improve communications and information availability. The design I
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SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS l
FOR THE HOPE CREEK GENERATING STATION - Cont'd 1
l change did not affect any equipment that has a control function. The new workstations, i
including the raised floors and partition wall, meet the appropriate seismic requirements. This design change does not impact any operational transients or postulated design basis accidents. Therefore, this design change does not increase l
the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, and does not involve an Unreviewed Safety Question.
Temporary Modifications Summary of Safety Evaluations TMR 99-016, Replacement of Safety Auxiliary Cooling System Valves 1EGHV-2317A and 1EGHV-2317B with Blank Flanges. This temporary modification replaced Safety Auxiliary Cooling System (SACS) valves 1EGHV-2317A and 1EGHV-2317B with blank flange assemblies. These valves are normally closed, and are opened when both Fuel Pool Cooling and Cleanup Heat Exchangers are being cooled by a single SACS loop. The safety function of these valves is to close.
The blank flange assemblies are equivalent to the other SACS piping and the pipe stresses are acceptable. This temporary modification does not impact any operational l
transients or postulated design basis accidents. This temporary modification 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.
Procedures Summary of Safety Evaluations NC.NA-AP.ZZ-0009, Rev.15, Work Management. The safety evaluation associated with this administrative procedure addressed the reorganization and deletion of administrative ; rocedures related to work management and corrective actions, it also addressed the installation of the work management and corrective action portion of the SAP software. The changes are primarily limited to the level of detail included in the procedures. The level of detail that was removed from NC.NA-AP.ZZ-0015 was included in a series of work management procedures, which were created in conjunction with this procedure revision.
The implementation SAP does not impact on the ability of plant equipment to perform its design functions, including their ability to prevent and mitigate accidents. The work management and corrective action functions will continue to be performed. This procedure revision does not impact any operational transients or postulated design l
basis accidents. This procedure revision does not increase the possibility or consequences of any accident or malfunction, does not reduce the margin of safety, l
and; therefore, does not involve an Unreviewed Safety Question.
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