ML18095A658
| ML18095A658 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/27/1990 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18095A659 | List: |
| References | |
| LCR-90-04, LCR-90-4, NLR-N90024, NUDOCS 9101020403 | |
| Download: ML18095A658 (7) | |
Text
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e Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations DEC 2 7 1990 NLR-N90024 LCR 90-04 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOSo DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit 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 deletes Technical Specification Section 3.7.1.2, surveillance requirement 4.7.1.2.c.
This surveillance requires verification of the flow path from the Auxiliary Feedwater Storage Tank to the Steam Generator.
Salem Units 1 and 2 require operation of the Auxiliary Feedwater System to maintain Steam Generator level during heatup.
The proposed change would eliminate an unnecessary surveillance.
The proposed amendment also removes the valve numbers from Technical Specification surveillance requirement 4.7.1.2.a.4.
The valve numbers are being relocated to the bases.
The proposed change will not change the requirement to maintain a flow path to each steam generator. includes a description, reason, justification and significant hazards analysis for the proposed change. contains the Technical Specification pages revised with pen and ink changes.
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v Document Control Desk NLR-N90024 DEC 2 7 1990 We request that the implementation date be established at 60 days following issuance of the approved License Amendment.
Should you have any questions regarding this transmittal, please feel free to contact us.
Attachments C
Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Sincerely, Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
I REF:
NLR-N90024 STATE OF NEW JERSEY
)
)
SS.
COUNTY OF SALEM
- s. LaBruna, 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 our letter dated DEC 2 7 '\\990
, concerning the Salem Generating station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
su:bscribed and Sworn to before me
, this.-?IJ ~ day of ~4u.,/, 1990
J!=v~
~otary Public of New Jersey My Commission expires on ~
.;>3, 1993 NLR-N90024 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS SALEM UNIT NOS. 1 AND 2 AUXILIARY FEEDWATER SYSTEM I.
Description of Change LCR 90-04 Delete Technical Specification surveillance requirement 4.7.1.2.c to verify the flow path from the auxiliary feedwater storage tank to each of the steam generators.
Change Technical Specification surveillance requirement 4.7.1.2.a.4 to read: "Verify the manual maintenance valves in the flow path to each steam generator are locked open."
Relocate the valve list to the bases with an explanation that a spool piece is equivalent to a locked open valve.
II.
Reason for the Change Salem Units 1 and 2 require auxiliary feedwater to maintain steam generator level during heatup.
The use of the auxiliary feedwater system satisfies the verification and a surveillance is redundant.
Relocating the valve list to the bases will allow flexibility in operating should maintenance be required on any of the manual valves.
The flow path to each steam generator will still be required to be verified by the surveillance.
III. Justification for the Change The requirement to verify the flow path from the auxiliary f eedwater storage tank to each of the steam generators is provided to ensure a flow path for water is available following maintenance.
Salem demonstrates compliance by transferring water from the auxiliary feedwater storage tanks to maintain level in the steam generators during normal plant heatup using the motor driven auxiliary feed pumps.
The piping downstream of the flow control valves is common to the turbine driven and motor driven auxiliary feed pumps.
Flow through this piping is verified during normal plant heatup.
When sufficient steam pressure is available, the turbine driven auxiliary feed pump is tested on recirculation in accordance with the inservice testing program and Technical Specification 4.0.5.
Testing on recirculation verifies flow from the auxiliary f eedwater storage tank through the suction piping, the turbine driven pump and the discharge check valve.
In accordance with the inservice testing program and Technical Specification 4.0.5, the flow control valves for the turbine driven pump are exercised every 92 days.
- Also, flow through the control valves is verified following each refueling during exercise testing of the check valves.
The proposed deletion of surveillance requirement 4.7.1.2.c would have no adverse effect on the accident analysis.
The flow paths are verified during plant heatup by normal plant operations and surveillance testing.
This change would not reduce the availability of either the motor driven or the turbine driven auxiliary feed pumps.
There is no effect on the accident analyses associated with the auxiliary feedwater system.
Westinghouse Standard Technical Specifications, Revision 4 do not include this surveillance requirement.
Relocating the valve list to the bases will allow operational flexibility to perform maintenance on the manual isolation valves.
This change will allow a piping spool piece to replace a normally locked open valve when a spare is not available.
This change will not delete any requirements to maintain an operable flow path to each steam generator.
There is no change in the plant configuration or plant procedures.
This is an administrative change.
--1
IV.
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 proposed deletion of the surveillance requirement for verification of the flow path from the auxiliary f eedwater storage tank to each steam generator would not affect the accident analysis.
The normal flow paths are verified during heatup by plant operation using the motor driven auxiliary feed pumps and by surveillance testing of the turbine driven auxiliary feed pump.
Therefore, this change would not increase the probability or consequences of a previously analyzed accident.
The proposed amendment to relocate the valve list to the bases would not change any plant configuration or plant procedures.
This is an administrative change for operating considerations only.
This change would not increase the probability or consequences of a previously analyzed accident.
- 2.
Create the possibility of a new or different kind of
- accident.
There is no change in plant design or in the operating procedures.
The proposed change will delete a surveillance requirement that is satisfied during plant heatup by normal plant operation and surveillance testing.
Additionally, there is no change in the availability of the auxiliary feed pumps and therefore, there are no new failure modes introduced by the proposed change.
Therefore, there can be no impact on plant response to the point where a different accident is created.
The proposed amendment to relocate the valve list to the bases would not change any plant configuration or plant procedures.
This is an administrative change for operating considerations only.
Therefore, there can be no impact on plant response to the point where a different accident is created.
L
- 3.
Involve a significant reduction in a margin of safety.
There is no change in the plant configuration or plant procedures.
The proposed change will delete a surveillance requirement that is satisfied during plant heatup by normal plant operation and surveillance testing.
Therefore, there is no reduction in any margin of safety.
There is no change in plant configuration or plant procedures.
The proposed change will relocate the valve numbers from the surveillance to the bases, while maintaining the requirement to maintain an operable flow path.
Therefore, there is no reduction in any margin of safety.
- v.
Conclusions Based on the information presented above, PSE&G has concluded there is no significant hazards consideration.