ML18101A694
| ML18101A694 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/02/1995 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18101A695 | List: |
| References | |
| LCR-94-35, LR-N94212, NUDOCS 9505110141 | |
| Download: ML18101A694 (6) | |
Text
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Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations MAY 0 2 1995 LR-N94212 LCR 94-35 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION AUXILIARY FEEDWATER SALEM GENERATING STATIONS UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric & Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station Units Nos. 1 and 2 respectively.
In accordance with 10CFR50.91(b) (1) requirements, a copy of this request has been sent to the state of New Jersey.
The proposed amendment modifies the Technical Specification for Engineered Safety Feature Actuation System -
Auxiliary Feedwater to eliminate the Manual start requirement.
Manual start will be tested during the quarterly pump test and is not credited in the safety analyses.
This change is consistent with NUREG-1431, Standard Technical Specifications - Westinghouse Plants. includes a description, justification, and significant hazards analysis for the proposed change. contains the Technical Specification pages revised with pen and ink changes.
PSE&G is requesting a 60 day implementation period after amendment approval.
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Document Control Desk LR-N94212 LCR 94-35 2
MAY 0 2 1995 Should there be any questions with regarCJ. to this submittal, please do not hesitate to contact us.
C Mr. T. T. Martin, Administrator -
e
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager -
Salem
- u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville,. MD 20852 Mr. c. Marschall - Salem (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933
STATE OF NEW JERSEY COUNTY OF SALEM
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REF: LR-N94212 J. J. Hagan, being duly sworn according to law deposes and says:
I am Vice President-Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
to before me My Commission expires on 1994 KIMBERLY Jff BROWN NOTARY PUBLIC OF NEW JERSEY My Commission Expires April 21, 1998
ATTACHMENT 1 LR-N94212 LCR 94.-35 ENGINEERED SAFETY FEATURES INSTRUMENTATION AUXILIARY FEEDWATER CAFW)
I.
Description of Change Change Table 3.3-3 Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Table 3.3-4 ESFAS Trip Setpoints, and Table 4.3-2, ESFAS Surveillance Requirements Functional Unit 8.b Auxiliary Feedwater Manual Initiation to read "Not Used".
On Table 3.3-3, Change Action Statement 22 to read "Not Used".
On Table 4,3-2, Change Table Notation (5) to read "Not Used".
II. Justification The AFW system is designed to provide a secondary side heat sink for the reactor in event that the Main *Feedwater System is not available.
The system has two motor driven pumps and one turbine driven pump, making it available during normal operation, during loss of AC power, a loss of Main Feedwater, and during a Feedwater System pipe break.
The normal source of water for the AFW System is the Auxiliary Feedwater Storage Tank.
The AFW System is aligned so tha~
upon* a pump start, flow is initiated to the respective Steam Generators immediately.
There are six automatic actuations of the AFW System which are included in the ESF Actuation Instrumentation Specification.
These include:
Automatic Actuation Logic Steam Generator Water Level low-low RCP Undervoltage Safety Injection Trip of the Main Feedwater Pumps station Blackout Manual initiation of the AFW System is currently included in the specification, however it is not credited in the Salem safety analysis.
Also, NUREG-1431, Standard Technical Specifications - Westinghouse Plants does not include manual initiation.
Manual initiation of the AFW Pumps is performed quarterly on a staggered Test Basis when performing surveillance requirement 4.7.1.2.b.
This test is verification of the AFW Pump performance and requires manual initiation of each pump.
LR-N94212
- 2 e-LCR 94-35 Elimination of the Manual Initiation from the ESF Actuation Instrumentation specification does not change any operating characteristics of the plant.
Manual initiation is still verified quarterly on a staggered test basis in accordance with specification 4.7.1.2~b. Maintaining manual initiation in the ESF Actuation Specification would require each AFW Pump to be started monthly causing unnecessary wear on system components.
AFW Pump surveillance frequency was changed to quarterly on a staggered test basis in accordance with Generic Letter 93-05 and Technical Specification Amendment 153/134.
On Table 3.3-3 and Table 4.3-2, Action 22 and Notation 5 respectively are changed-to "Not Used".
These are editorial changes because the functional unit which requires these items has been deleted.
No other functional units require these actions.
III. Significant Hazards Consideration In accordance with 10CFR50.92, PSE&G has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes would not:
- 1.
Involve a significant increase in the probability or consequences of an accident previously analyzed.
The change to the ESF Actuation Instrumentation specification to eliminate the requirements for manual initiation of the AFW Pumps does not change any operating characteristics of the plant.
The change will eliminate unnecessary AFW Pump starts which increase wear on system components.
Manual initiation is not credited in the Salem safety analyses.
Manual initiation is verified quarterly on a staggered test basis by performance of specification 4.7.1.2.b.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2.
Create the possibility of a new or different kind of accident.
The proposed technical specification modifications do not change system configurations, plant equipment or safety analyses.
Therefore, the proposed modifications will not increase the possibility of a new or different kind of accident from any accident previously identified.
LR-N94212 3
LCR 94-35
- 3.
Involve a significant reduction in a margin of safety.
The proposed change to the ESF Actuation Instrumentation Specification does not affect the ability of the AFW System to perform its design function.
The manual initiation of the AFW Pump is not credited in the Salem safety analyses.
Manual initiation is verified quarterly by performance of specification 4.7.1.2.b.
Therefore, these changes do not involve a significant reduction in any margin of safety.
IV.
Conclusion Based on the information presented above, it is conciuded that the activities associated with this license change request satisfy the no significant hazards considerations of 10CFR50.92.