ML18094A757
| ML18094A757 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/04/1989 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N89205, NUDOCS 8910160099 | |
| Download: ML18094A757 (3) | |
Text
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 KT@t IE9 NLR-N89205 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
EXIGENT REQUEST REVISED AMENDMENT IMPLEMENTATION DATE LICENSE DPR-70 AND DPR-75 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 By letter dated August 28, 1989, the NRC issued License Amendment Nos. 101 and 78 for Salem Generating Station Unit Nos. 1 and 2, respectively.
These License Amendments added Reactor Vessel Head Vent Technical Specifications (Section 3/4.4.12) based on PSE&G submittals dated September 12, 1988, March 3, 1989 and June 8, 1989.
The amendments were effective as of the date of issuance and required implementation within 45 days (i.e.,
October 12, 1989).
The purpose of this exigent request is to defer implementation of Technical Specification 3/4.4.12, for Salem Units 1 and 2, until prior to restart following the next entry into Operational Mode 3 (Hot Standby).
Surveillance requirement 4.4.12.1 requires that all manual isolation valves in the reactor vessel head vent path be verified locked open as part of the demonstration of system operability.
During a pre-implementation review of the amendments, PSE&G personnel noted that the provisions of 4.4.12.1 would not be met by the amendment's current implementation date, unless valves 1RC45 and 1RC900 (Unit 1) and 2RC900 (Unit 2) were physically locked open.
Because the valves are behind a biological shield, radiation exposure considerations preclude personnel from locking them during power operation.
The reactor vessel head vent system was used during fill and vent operations following the most recent refueling at each of the Salem units.
The valves in question were verified open using an approved valve checklist prior to plant startup; however, prior to receipt of the subject amendment, were not required to be locked.
There is, therefore, a high level of assurance that the reactor vessel head vent systems are functional, but since
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Document Control Desk NLR-N89205 2
surveillance requirement 4.4.12.1 cannot be met without locking the valves open, PSE&G would be forced to enter mode 3 (Hot standby) to comply with the action statements of 3/4.4.12 and/or lock open the valves, given the present implementation requirement of the amendments.
Therefore PSE&G hereby requests that the implementation requirements of Salem License Amendments 101 and 78 be amended as follows:
This license amendment is effective as of its date of issuance, and to be implemented prior to reactor startup following the next plant shutdown to Mode 3, Hot Standby.
This would require implementation no later than prior to restart following the next refueling outages, which are scheduled to begin March 31, 1990 for Unit 2 and October 6, 1990 for Unit 1.
PSE&G has reviewed this exigent request against the previous submittals.
No changes to the Technical Specifications themselves are proposed herein.
Based on past operation of the reactor vessel head vent system, there is a high level of assurance of system availability.
Therefore, PSE&G has determined that the No Significant Hazards Consideration remains valid and that the proposed changes do not constitute a Significant Hazards Consideration.
Since this exigent request does not constitute a Significant Hazards Consideration, involves no change to the type or amount of effluent that may be released offsite nor any* increase in:
occupational radiation exposure, it qualifies for a categorical**
exclusion as defined in 10 CFR 51.22.
Pursuant to 10 CFR 50.4(b) (2) (ii), this submittal includes one (1) signed original and thirty-seven (37) copies and, in accordance with 10 CFR 50.9l(b) (1), PSE&G has provided a copy to the State of New Jersey.
An unwarranted shutdown of Salem Units 1 and 2 is required unless the request contained herein is processed on an expedited basis and approved no later than October 12, 1989.
Therefore, PSE&G believes that, per 10 CFR 50.9l(a) (6), this change can be processed as an exigent request.
Should you have any questions, please feel free to contact us.
Sincerely,
Document Control Desk NLR-N89205 c
Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector 3
Mr. w. T. Russell, 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 Mr. Walter Butler, Director Directorate 1-2