LR-N14-0160, Re-Submittal of No Signifcant Hazards Consideration for License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule
| ML14174B239 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 06/23/2014 |
| From: | Duke P Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LAR H13-03, LAR S13-02, LR-N14-0160 | |
| Download: ML14174B239 (5) | |
Text
JUN' 2 3 2014 LR-N14-0160 LAR S13-02 LAR H13-03 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354 PS~:G Nuclear lLC 10 CFR 50.90
Subject:
Re-Submittal of No Significant Hazards Consideration for License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule
Reference:
PSEG Nuclear Letter to NRG (LR-N13-0265), License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule, dated December 24, 2013 In the above reference, PSEG Nuclear (PSEG) submitted license amendment requests LAR S13-02 and LAR H13-03 requesting NRC approval of the revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule. Attachment 1 (Evaluation of Proposed Changes) of the referenced submittal was determined to contain Security-Related Information and therefore requested to be withheld from public disclosure pursuant to 10 CFR 2.390.
A subsequent review of the No Significant Hazards Consideration Section of Attachment 1 from the referenced letter has been performed by PSEG. This review resulted in a determination that this section does not contain security-related information and is therefore subject to public disclosure. Attachment 1 to this letter contains the unaltered No-Significant Hazard Consideration from Attachment 1 of the referenced letter.
Page 2 LR-N 14-0160 10 CFR 50.90 JUN' 2 3 2014 There are no regulatory commitments contained in this letter. If you have any questions or require additional information, please contact Mr. Lee Marabella at 856-339-1208.
Sincerely, CfJ_L~
Paul R. Duke, Jr.
Manager - Licensing
Attachment:
No-Significant Hazards Consideration for LARs S13-02/H13-03 cc:
W. Dean, Administrator, Region I, USNRC J. Lamb, Project Manager, USNRC NRC Senior Resident Inspector, Hope Creek NRC Senior Resident Inspector, Salem P. Mulligan, Manager IV, NJBNE Commitment Tracking Coordinator, Hope Creek Commitment Tracking Coordinator, Salem Corporate Commitment Tracking Coordinator
LR-N14-0160 No-Significant Hazards Consideration for LARs S13-02/H13-03
LR-N14-0160
- r License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule No Significant Hazards Consideration PSEG requests an amendment to the Salem and Hope Creek Operating Licenses. The amendment would change the PSEG CSP Milestone 8 (M8) full implementation date as set forth in the PSEG Cyber Security Plan Implementation Schedule.
PSEG has evaluated the proposed changes to the TS, using the criteria in 10 CFR 50.92, and determined that the proposed changes do not involve a significant hazards consideration. The following information is provided to support a finding of no significant hazards consideration.
- 1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The amendment proposes a change to the PSEG Cyber Security Plan (CSP)
Implementation Schedule Milestone 8 (M8) full implementation date as set forth in the PSEG CSP Implementation Schedule. The revision of the full implementation date for M8 does not involve modifications to any safety-related structures, systems, or components (SSCs).
Rather, the implementation schedule provides a timetable for fully implementing the PSEG CSP. The CSP describes how the requirements of 10 CFR 73.54 are to be implemented to identify, evaluate, and mitigate cyber attacks up to and including the design basis cyber attack, thereby achieving high assurance that the facility's digital computer and communications systems and networks are protected from cyber attacks. The revision of the PSEG CSP Implementation Schedule will not alter previously evaluated design basis accident analysis assumptions, add any accident initiators, modify the function of plant safety-related SSCs, or affect how any plant safety-related SSCs are operated, maintained, modified, tested, or inspected.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The implementation of the PSEG CSP does not introduce new equipment that could create a new or different kind of accident, and no new equipment failure modes are created. No new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of this proposed amendment.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Do the proposed changes involve a significant reduction in a margin of safety?
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LR-N14-0160 Response: No The margin of safety is associated with the confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant pressure boundary, and containment structure) to limit the level of radiation (dose or exposure) to the public. The proposed amendment does not alter the way any safety-related SSCs function and does not alter the way the plant is operated. The CSP provides assurance that safety-related SSCs are protected from cyber attacks. The proposed amendment does not introduce any new uncertainties or change any existing uncertainties associated with any safety limit. The proposed amendment has no effect on the structural integrity of the fuel cladding, reactor coolant pressure boundary, or containment structure. Based on the above considerations, the proposed amendment does not degrade the confidence in the ability of the fission product barriers to limit the level of radiation (dose or exposure) to the public.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based upon the above, PSEG concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
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