LR-N07-0217, Supplement to License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications
| ML072480611 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/23/2007 |
| From: | Barnes G Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LCR H06-02, LR-N07-0217 | |
| Download: ML072480611 (3) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0PSEG Nuclear LLC 10 CFR 50.90 LR-N07-0217 LCR H06-02 AUG 2 3 2007 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Supplement to License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications
Reference:
- 1) Letter from George P. Barnes (PSEG Nuclear LLC) to USNRC, November 15, 2006, "License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications" In Reference 1, PSEG Nuclear LLC (PSEG) requested an amendment to Facility Operating License NPF-57 and the Technical Specifications (TS) for the Hope Creek Generating Station (HCGS) to remove valve component lists and references to the lists from the Technical Specifications (TS).
This letter provides additional information regarding the control of the Technical Requirements Manual (TRM). Reference 1 stated that the information contained in the deleted tables would be relocated to the HCGS TRM, and that changes to the TRM will be reviewed pursuant to 10 CFR 50.59.
The TRM will be controlled in a manner consistent with procedures fully or partially described in the HCGS updated final safety analysis report (UFSAR). A description of the TRM and the requirement to control TRM changes under 10 CFR 50.59 will be included in the UFSAR when the proposed change to the TS is implemented. The controls for the HCGS TRM will be in accordance with NEI 98-03, Rev. 1, "Guidelines for Updating Final Safety Analysis Reports."95-21J REV.9
LR-N07-0217 LCR H06-02 AUG 2 3 2007 Page 2 PSEG has determined that the information contained in this letter does not alter the conclusions reached in the 10CFR50.92 no significant hazards analysis previously submitted.
The regulatory commitment for control of TRM changes is provided in Attachment 1 to this letter.
Should you have any questions regarding this submittal, please contact Mr. Paul Duke at 856-339-1466.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on 8/123/07 (date)
Sincerely, George P. Barnes Site Vice President Hope Creek Generating Station cc:
S. Collins, Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE
ATTACHMENT I Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354 Supplement to License Amendment Request to Relocate Component Lists for Primary Containment Isolation Valves from Technical Specifications Summary of Commitments The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.)
COMMITMENT COMMITTED COMMITMENT TYPE DATE OR One-Time Programmatic "OUTAGE" Action (Yes/No)
(Yes/No)
PSEG will control changes to the Hope Implement with Creek Technical Requirements Manual amendment No Yes under 10 CFR 50.59.