ML18102A927
| ML18102A927 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/14/1997 |
| From: | Storz L Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N97144, NUDOCS 9703240150 | |
| Download: ML18102A927 (4) | |
Text
Louis F. Storz Senior Vice President - Nuclear Operations Public Service Electric and Gas Company Public Service Electric an_d GNi8ARm:r? 1gg:f *Box 236, Hancocks Bridge, NJ 08038 LR-N97144 United States Nuclear Regulatory Commission Document Coptrol Desk Washington, DC 20555 SUPPLEMENT TO REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS PRESSURIZER POWER OPERATED RELIEF VALVES SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
By letter LR-N97055, dated January 31, 1997, Public Service Electric & Gas Company (PSE&G) submitted a request to amend Salem Generating Station Units 1 and 2 respective Technical Specifications (TSs) 3.4.3 and 3.4.5 pertaining to the pressurizer power operated relief valves (PORVs).
This letter provides a supplement to that request.
609-339-5700 The previously submitted request proposed a revision to the actions associated with inoperable PORVs to ensure that the automatic capability to relieve pressure is maintained when these valves are isolated by closure of the block valves.
The change was based on PSE&G's review of a spurious operation of the Safety Injection System during power operation.
Since the original submittal, PSE&G has taken additional actions to eliminate single failure vulnerabilities in the PORV circuitry and upgrade the circuitry to qualify the PORVs as safety related.
The modifications consist of:
- 1) elimination of the non-safety related controller, PC455K, from the valve control circuitry and relocation of the PORV circuitry into the protection racks from the control racks and 2) separation of the channels such that failure of any one channel or power supply will render, at most, one PORV inoperable.
PSE&G will complete these upgrades for the Salem Units prior to increasing Reactor Coolant System temperature above 312°F for the respective units.
As a result of the changes being made to the circuitry, the
. I valves and associated controls will be safety related, redundant l
and independent.
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MAR 141997ii 2
The proposed TS changes are in accordance with that presented in Generic Letter 90-06 since the the changes encompass Salem's design basis of automatic and manual PORV operation for event mitigation, including the inadvertent safety injection event.
However, in upgrading the PORVs to safety grade, PSE&G has taken improvement actions beyond that which are required subsequent to the TMI-2 accident and those of the Generic Letter.
PSE&G requests that the proposed TS changes be reviewed as submitted previously in light of the additional justification provided above.
PSE&G has reviewed the previously submitted evaluation in accordance with the three standards set forth in 10CFR50.92 and has concluded that no change is necessary as a result of the revised pages and the conclusion of no significant hazards consideration remains valid.
The previously submitted evaluation stated that no new protection system logic is proposed and, therefore, there is no additional signal that can spuriously actuate the Safety Injection System.
Though the control circuitry for the PORVs has been modified, the protection systems for the Reactor Trip and Engineered Safety Feature Actuation are not impacted and the statement remains valid.
Should you have any questions regarding this supplement, we will be pleased to discuss them with you.
Sincerely, Attachment 95-4933
' Document Control Desk LR-N97144 3
C Mr. H. J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. 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 (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 MAR 141991 95-4933
REF:
LR-N97144 STATE OF NEW JERSEY SS.
COUNTY OF SALEM Louis F. Storz, being duly sworn according to law deposes and says:
I am Senior 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, Units 1 and 2, are true to the best of my knowledge.
Subscribed and Sworn~before me this /4-fA day of 1-L(-(1~, 1997 My Commission expires on l<IM,BERLV JO BROWN NOTl\\RY PUBLIC OF NEW JERSEY My Cornrnis~ion Expires April 21, 1998