ML18096B229
| ML18096B229 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/25/1993 |
| From: | Labrauna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18096B230 | List: |
| References | |
| LCR-92-10, NLR-N93006, NUDOCS 9302010060 | |
| Download: ML18096B229 (7) | |
Text
Public Service Electric.
and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President
-.Nuclear*
Operations JAN 2 5 1993 NLR-N93006 LCR. 92-10 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
REQUEST FOR AMENDMENT SALEM GENERATING STATION UNIT NO. 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 In accordance with the requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) is transmitting a request to amend Facility Operating License DPR-75, for Salem Generating Station (SGS) Unit No. 2. Pursuant to the requirements of 10CFR50.90 (b) (1), a copy of this request has been sent to the State of New Jersey
- The proposed changes revise the plant heatup and cooldown curves. These changes are a result of data obtained from the analysis of Capsule "X" withdrawn from Salem Unit 2 during the sixth refueling outage. Westinghouse Technical Report WCAP-13366 summarizes the testing of and post-irradiation data obtained from Capsule "X". 1 Attachment A contains further discussion and justification for the proposed revision.
Attachment B is a markup of the existing Unit 2 Technical Specifications and revised pages to reflect the requested changes. PSE&G has reviewed the implementation requirements for the proposed amendment and requests a 60 day implementation period after amendment approval.
Attachments (2) '9302010000 930125 PDR ADOCK p Sincerely, 290016 Document Control Desk NLR-N93006 2
- C Mr. T. T. Martin, Administrator
-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S05) USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 JAN 2 5 1993 REF: NLR-N93006 STATE OF NEW JERSEY COUNTY OF SALEM ) ) SS. ) 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 the above referenced letter, concerning the Salem Generating Station, Unit No. 2, are true to the best of my knowledge, information and belief. ,
Sworn before me this £:)' day of ._j1Jf (l.+/JL , 1993 My Commission expires _..... I I KIMBERLY A. HILL NOTARY PUBLIC OF NEW JERSEY My Commission Expires March 9, 1997 PROPOSED LICENSE CHANGE SALEM GENERATING STATION UNIT NO. 2 ATTACHMENT A FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 I. Description of the Change LCR-92-10 This amendment request revises the Reactor Coolant System Heatup and Cooldown curves, Figures 3.4-2 and 3.4-3 respectively.
II. Reason for the Proposed Change The revised Heatup and Cooldown curves are applicable to 15 EFPY. The updated curves reflect Reactor Vessel material property changes identified from analysis of surveillance Capsule X, removed during the Unit 2 sixth refueling outage. That analysis utilized actual limiting weld chemistry data rather than the previously used default values, thus providing some operational margin (i.e., less restrictive curves) without any reduction in the margin of safety. The actual weld chemistry data is identified in existing Technical Specification Table B 3/4.4-1 and the Salem Unit 2 responses to Generic Letter 92-01 (June 30, 1992 and December 30, 1992). III. Justification for the Proposed Change 10CFR50 Appendix H requires a surveillance program to monitor changes in the fracture toughness properties of Reactor Vessel materials due to neutron irradiation.
Surveillance Capsules are periodically removed and analyzed to determine these irradiation effects. Based on the most recent Capsule data, a change to the Reactor Coolant System Heatup and Cooldown curves is warranted.
These curves define the pressure and temperature to assure prevention of nonductile failures.
The revised curves reflect the Capsule "X" analysis results of WCAP-13366 forwarded to the NRC on October 27, 1992. 1 .*-...
- IV. Significant Hazards Analysis Consideration The proposed Technical Specification changes: 1. Do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes assure that existing safety limits are not exceeded due to changing Reactor Vessel conditions.
These changes reflect the latest material testing results per 10CFR50, Appendix H. Clearly defining the pressure and temperature limits decreases the probability of nonductile failures.
Therefore, it may be concluded that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Do not create the possibility of a new or different kind of accident from any accident previously evaluated.
No physical plant modifications or new operating configurations result from these changes. These changes do not adversely affect the design or operation of any system or component important to safety, rather, they establish limits to assure that operation remains within acceptable boundaries.
Therefore, no new or different accident from any previously evaluated will be created. 3. Do not involve a significant reduction in a margin of safety. Capsule "X" analysis concluded that the Reactor Vessel has sufficient fracture toughness for continued safe operation, providing operation remains within acceptable limits. The heatup and cooldown curves define these acceptable limits. The proposed changes maintain existing margins of safety by modifying operating requirements based on specimen Capsule .* "X" analysis.
This analysis accounts for the actual chemistry data associated with the limiting weld, rather than the previously used default values, thus providing some additional operating margin with no reduction in the margin of safety. Actual weld chemistry data is specified in existing Technical Specification Table B 3/4.4-1. Therefore, it may be concluded that the proposed changes do not involve a significant reduction in a margin of safety. 2 V. Conclusions Based on the information presented above, PSE&G has concluded that the proposed changes satisfy the criteria for a no significant hazards consideration.
3 ATTACHMENT B