LR-N16-0124, License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule
| ML16190A248 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 06/30/2016 |
| From: | Sindoni J Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16190A349 | List: |
| References | |
| LAR H16-06, LAR S16-06, LR-N16-0124 | |
| Download: ML16190A248 (14) | |
Text
Attachments 1 and 4 of this letter contain Security-Related Information Withhold Under 10 CFR 2.390 PSEG Nuclear LLC P.O. Box 236J Hancocks Bridge, NJ 08038-0236 0 11SE<i l\h.tdear [J,C JUN S 0 2016 10 CFR 50.90 LR-N16-0124 LAR S16-06 LAR H16-06 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
Subject:
License Amendment Request for Approval of the Revised PSEG Nuclear Cyber Security Plan Milestone 8 Implementation Schedule Pursuant to 10 CFR 50. 90, PSEG Nuclear LLC (PSEG) requests an amendment to the renewed facility operating licenses listed above. This amendment proposes a change to the PSEG Cyber Security Plan Milestone 8 full implementation date as set forth in the PSEG Cyber Security Plan Implementation Schedule. of this submittal provides an evaluation supporting the proposed changes. provides the No Significant Hazards Consideration that supports the technical evaluation in Attachment 1. Attachment 3 provides the marked-up Facility Operating License (FOL) pages, with the proposed changes indicated. Attachment 4 provides the revision to Milestone 8 of the Salem-Hope Creek Cyber Security Plan Implementation Schedule.
PSEG requests that Attachments 1 and 4, which contain security-related information, be withheld from public disclosure in accordance with 10 CFR 2.390.
There is one new regulatory commitment associated with this amendment, as provided in Attachment 5.
The changes in this License Amendment Request (LAR) are not required to address an immediate safety concern; PSEG requests approval of this LAR by June 1 5, 2017. Once approved, the amendment will be implemented within 60 days from the date of issuance.
Page 2 LR-N16-0124 10 CFR 50.90 Attachments 1 and 4 of this letter contain Security-Related Information Withhold Under 10 CFR 2.390 These proposed changes have been reviewed by the Plant Operations Review Committee.
PSEG has concluded that the proposed changes present no significant hazards consideration under the standards set forth in 10 CFR 50.92. PSEG is notifying the State of New Jersey of this LAR by transmitting a copy of this letter and its attachments to the designated State Official.
If you have any questions or require additional information, please contact Mr. Paul Duke at (856) 339-1466.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on {I {36 {(g
( ate)
Sincerely, Joseph M. Sindoni Senior Director- Regulatory Affairs Attachments:
- 1. Evaluation of Proposed Changes (contains Security-Related Information)
- 2. No Significant Hazards Consideration
- 3. Salem and Hope Creek Facility Operating License Pages with Proposed Changes
- 4. Salem-Hope Creek Cyber Security Plan Implementation Schedule (contains Security-Related Information)
- 5. List of Regulatory Commitments cc: D. Dorman, Administrator, Region I, USNRC C. Parker, Project Manager, USNRC NRC Senior Resident Inspector, Hope Creek NRC Senior Resident Inspector, Salem P. Mulligan, Manager IV, NJBNE T. MacEwen, Commitment Tracking Coordinator, Hope Creek T. Cachaza, Commitment Tracking Coordinator, Salem L. Marabella, Corporate Commitment Tracking Coordinator
LR-N16-0124 Attachment 2 No Significant Hazards Consideration
LR-N16-0124 No Significant Hazards Consideration PSEG Nuclear LLC (PSEG) requests an amendment to the Salem and Hope Creek Operating Licenses. The amendment would change the PSEG Cyber Security Plan (CSP) Milestone 8 (M8) full implementation date as set forth in the PSEG CSP Implementation Schedule.
PSEG Nuclear has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change to the CSP Implementation Schedule is administrative in nature. This change does not alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The proposed change does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents and has no impact on the probability or consequences of an accident previously evaluated.
Therefore, the proposed change does 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?
Response: No Plant safety margins are established through limiting conditions for operation, limiting safety system settings, and safety limits specified in the technical specifications. The proposed change to the CSP Implementation Schedule is administrative in nature. In addition, the milestone date delay for full implementation of the CSP has no substantive impact because 2
LR-N16-0124 other measures have been taken which provide adequate protection during this period of time. Because there is no change to established safety margins as a result of this change, the proposed change does not involve a significant reduction in a margin of safety.
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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LRwN16-0124 Attachment 3 Salem and Hope Creek Facility Operating License Pages with Proposed Changes
LR-N-16-0124 Salem Nuclear Generating Station, Unit 1 Facility Operating License Pages with Proposed Changes The following page for Renewed Facility Operating license No. DPR-70 is affected by this change request: 9.
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evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements In that section, (19) Appendix A of NUREG-2101, "Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station," dated June 20111 and PSEG Nuclear LLC UFSAR supplement submitted pursuant to 10 CFR 54.21 (d), as revised on May 18, 2011, describe certain future programs and activities to be completed before the- period of extended operation. PSEG Nuclear LLC shall complete these activities no later than August 13, 2016, and shall notify the NRC in writing when Implementation of these activities is complete.
(20) All capsules In the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens In the capsule. Any changes to the capsule withdrawal schedule, Including spare capsules, must be approved by the NRC prior to Implementation.
All capsules placed In storage must be maintained for future insertion. Any changes- to storage requirements must be approved by the NRC. Changes to the withdrawal schedule or storage requirements shall be submitted to the NRC as a report in accordance with 10 CFR 50.4.
(21) PSEG Nuclear LLC shall take one core sample In the Unit 1 spent fuel pool west wall, by the end of 2013, and one core sample In the east wall where there have bee* n indications of borated water Ingress through the concrete, by the* end of 2015. The core samples (east and west walls) will expose the rebar, which wHI be examined for signs of corrosion. Any sample showing signs of concrete degradation and/or rebar corrosion Will be entered into the licensee's corrective action program for further evaluation. PSEG Nuclear LLC shall submit a report* in accordance with 1 0 CFR 50.4 no later than three months after each s -ample ls taken on the results, recommendations, ani any additional planned actions.
- 0. Paragraph 2,0, has been combined with paragraph 2.E. per Amendment No. 86, June 27, 1988.
E. The licensee shall fully Implement and maintain In effect all provisions of the Commlsslonapproved physical security, training and qualification, and safeguards contingency plans Including amendments made pursuant to provisions of the Miscellaneous Amen<<ments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50,90 and 10 CFR 50,54(p),
The plans, submitted by letter dated May 19, 2006, are entitled: 11SalemHope Creek Nuclear Generating Station Security Plan," 11Salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan,ll and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan. The plans contain Safeguards Information protected under 10 CFR 73. 21.
PSEG Nuclear LLC shall fully Implement and maintain In effect all provisions of the Commission-approved Cyber Security Plan (CSP), Including changes made pursuant to the authority of 10 CFR 50,90 and 10 CFR 50.54(p), The Salem-Hope Creek CSP was.
approved by License Amendment No. 300 as supplemented by changes approved by License Amendme s 11d. 698.
- Renewed License No. DPR-7'0 Amendment No. 30t3 3 t7;I. 1 3 iJ (, a.l\1;;( X.)(X , -
LR-N16-0124 Salem Nuclear Generating Station, Unit 2 Facility Operating License Pages with Proposed Changes The following page for Renewed Facility Operating License No. DPR 75 is affected by this change request: 11.
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Issuance of the License for FueiNLoading and Low-Power Testing, dated AprU 18, 1980, The facility will operate, to the extent authorized herein, In conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.
E. The licensee shall fully implement and malntaln In effect all provisions* of the Commission-approved physical security, training and quallfl'catlon, and safeguards contingency plans Including amendments made pursuant to provisions of the Miscellaneous -Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR-50.54 (p).
The plans, submitted by letter dated May 19, 2006, are entitled: "Salem-Hope Creek Nuclear Generating Station Security Plan. '*salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan," and "Salem-Hope Creel< Nuclear Generating Station Security Contingency Plan." The plans Contain Safeguards Information protected under 10 CFR 73.21.
PSEG Nuclear LLC shall fully implement and maintain In effect all provisions *of the Commissl.on-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The sa*lem-Hope Creek CSP was approved by License Amendment No. 283 jS supplemented by changes ap.eel1J'f....r--
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.1 License Amendment N:os ..
oJ.!lJ/ tf tfL,fL.r/
F. A temporary exemption from General Design Criterion 57 found In Appendix A xx-x.
10 CFR Part 50 Is described In the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No.5,. Section 6*.2.3.1. This Exemption Is authorized by law and wlll not endanger life or property or the common defense and security and Is otherwise in the public Interest. The exemption, therefore, Is hereby granted and shall remain In effect through the first refueling outage*as discussed In Section 6.2.3.1 of Supplement 5 to the Safety Evaluation Report. The granting of the exemption Is*
authorized with the Issuance of the Fac\\lty Operating* License, dated May 20, 198.1. The facility will operate, to the extent authorized herein, In conformity with the application as amended, the provisions of the Act, and the regulations of the Comm*lsslon.
G. This renewed license Is subject to the following additional condition for the protection of the:environment:
Before engaging In additional construction or operational activities which may result In an environmental impact that was not evaluated by the Commission, PSEG Nuclear LLC shall prepare and record an environmental evaluation of such activity. When the evaluation Indicates that such activity may result In a significant adverse environmental Impact that was not evaluated, or that Is significantly greater than that evaluated In the Final Environmental Statement or any addendum thereto, PSEG Nuclear LLC shall provide a written evaluation of such activities and obtain prior approval from the Director of Nuclear Reactor Regulation.
H. If PSEG Nuclear LLC plans to remove or to make significant changes In the normal operation of equipment that controls the amount of radioactivity In effluents from the Salem Nuclear Generation Station, the NRC shall be notified In writing regardless of whether the change affects the amount of radioactivity In effluents.
I. DELETED Renewed License No. DPR-75
- Amendment No. 288
LR-N-16-0124 Hope Creek Generating Station Facility Operating License Pages with Proposed Changes The following page for Renewed Facility Operating License No. NPF-57 is affected by this change request: 16.
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exempting Type C testing for instrument lines and lines containing excess ftow check vatves (Section 6.2.6 of SSER 6); and an *exemption from Appendtx J, exempting Type C testing of thermal relief valves (Section 6.2."6 of SSER 5).
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are* consistent with the .common defense and security, These exemptions are hereby granted. The special circumstances regarding each exemption are Identified In the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. Wi1h these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations-of the Commis-sion.
E. The licensee shall fully implement and maintain in effect all provisions of the Commissionapproved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revislons to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, submitted by letter dated May 19, 2006 are entitled: "Sa!emHope Creek Nuclear Generating Station Securi_ty Training and Qualification Plan,u and 11Salem-Hope Creek Nuclear Generating Station Security Contingency Plan!' The plans contain Safeguards Information protected under 10 CFR 73.21.
PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commis-sion-appr-oved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem-Hope Creek cs-p was approved by License Amendment No. 189 as supplemented by changs approved. by License Amendment Nos. 4-92 an-d-1-9-1-.
- F. DELETED G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
Renewed License No. NPF-57 Amendment No. 197
LR-N16-0124 Attachment 5 List of Regulatory Commitments
LR-N16-0124 List 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 Date or Commitment Type
OutageH One*Time Action Programmatic (Yes/No) (Yes/No)
PSEG will implement December 15, 2017 Yes No the revised Milestone 8 schedule as defined in Attachment 3 of this submittal. 1 **-
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