ML15078A286

Vogtle Electric Generating Station, Unit No. 1 (VEGP-1), Correction for Amendments Regarding Use of 10 CFR 50369

ML15078A286
Person / Time
Site:	Vogtle
Issue date:	03/27/2015
From:	Martin R E Plant Licensing Branch II
To:	Pierce C R Southern Nuclear Operating Co
Martin R E
References
Download: ML15078A286 (5)

Text

Mr. C. R. Pierce Regulatory Affairs Direqtor UNITED STATES NUCLEAR .REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 27, 2015 Southern Nuclear Operating Company, Inc. Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295

SUBJECT:

VOGTLE ELECTRIC GENERATING STATION, UNIT NO. 1 (VEGP-1), CORRECTION FOR AMENDMENTS REGARDING USE OF 10 CFR 50.69

Dear Mr. Pierce:

On November 25, 2008, the NRG issued Amendment No. 154 to Renewed Facility Operating License NPF-68 for VEGP-1 that added a condition to NPF-68 related to control room emergency ventilation systems to establish more effective and appropriate actions to ensure the habitability of the control room envelope (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082480712). This revision was reflected in Appendix D "Additional Conditions" of NPF-68 and was identified in Appendix Das being associated with Amendment No. 154. On July 28, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 162 to Renewed Facility Operating License NPF-68 for VEGP-1 that revised the facility operating license to reflect approval of the Cyber Security Plan (ADAMS ML 11178A018). This was accomplished by adding second paragraph to section 2.E on NPF-68 license page 5. On December 17, 2014, the NRC issued Amendment No. 173 to Renewed Facility Operating License NPF-68 revising the licensing basis for the VEGP by adding a license condition that allows implementation of the regulation in Title 10 of the Code of Federal Regulations (1 O CFR) Section 50.69, "Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors" (ADAMS No. ML 14237A034). The amendment issued on December 17, 2014, made changes to NPF-68 license page 5 and to the Appendix D "Additional Conditions" to reflect the use of 10 CFR 50.69. However in doing so, parts of the changes made by the earlier amendments discussed above were not carried over to the revised pages issued with the December 17, 2014 amendment. These omissions are by the NRC staff as having been inadvertently introduced by the staff in its administrative processing activities associated with issuance of the amendment. The administrative based omission of certain parts of the first two amendments discussed above did not constitute an amendment to NPF-68. Such changes were not the subject of any licensee request or review by the NRC staff, and accordingly, such changes were not noticed in the Federal Register as prospective changes to NPF-68.

C.R. Pierce Please find enclosed a corrected page for the Appendix D Additional Conditions that reinstates the text of conditions added by prior amendments, specifically, reinstatement of, the Implementation Date column information for previous amendments and reinstatement of the words" ... test, or within 138 days if not performed previously." at the end of the second condition. Also please .find enclosed a corrected page 5 for the main body of NPF-68, which includes reinstatement of the second paragraph of Section 2.E regarding the Cyber Security Plan, as made by Amendment No. 162. License amendment nos. 154, 162 and 173 for NPF-68 are independent of each other; accordingly the NRC safety reviews and Federal Register notices for each amendment are independent of those developed for the other amendments. There is no change to the

• regulatory basis for the issuance of these amendments. This correction is an administrative change to produce an integrated version of the NPF-68 license pages that includes the results of the three amendments as discussed above. Docket No. 50-424 Sincerely, . Robert Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Enclosure:

Corrected NPF-68 license page 5 and NPF-68 Appendix D page D-2 cc w/encl: Distribution via Listserv

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of: 1. Water spray scrubbing 2. Dose to onsite responders . (11) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 173 are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Additional Conditions. D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include (a) an exemption from the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area, and (b) an exemption from the requirements of Paragraph lll.D.2(b)(ii) of Appendix J of 10 CFR 50, the testing of containment air locks at times when containment integrity is not required. The special circumstances regarding exemption b .are identified in Section 6.2.6 of SSER 5. . An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1967, issued August 21, 1986, and relieved GPC. from the requirement of having a criticality alarm system, GPC and* Southern Nuclear are hereby exempted from the criticality alarm system provision of 1 O CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

• 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. The exemptions i.n item band c above are granted pursuant to 10 CFR 50.12. With 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 Commission. E. Southern Nuclear shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendmen_ts m*ade 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 plan, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Southern Nuclear Operating Company Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan," with revisions submitted* through May 15, 2006. Southern Nuclear 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 Southern Nuclear CSP was approved by License Amendment No. 162.

• F. GPC shall comply with the antitrust conditions delineated in Appendix C to this license. Renewed Operating License No. NPF-68 Amendment No.173 Amendment Additional Condition Implementation Number Date 102 The licensee will implement all applicable crane, load path and Before and height, rigging and load testing guidelines of NUREG-0612 and during reracking ANSI Standard 830.2, as described in the licensee's letters dated operations, as September 4, 1997, May 19 and June 12, 1998, .and evaluated in appropriate. the staff's Safety Evaluation dated June 29, 1998 154 Upon implementation of the Amendment adopting TSTF-448, Revision 3, the As stated in the determination of CR.E unfiltered air inleakage as required by SR 3,7.10.5, in Additional

• accordance with TS 5.5.20.c.(i), and the measurement of CFE pressure as Condition required by Specification 5.5.20.d, shall be considered met. Following implementation: (a) The first performance of SR 3. 7.10.5, in accordance with Specification 5.5.20.c.(i), shall be within the specified frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from March 23, 2004, the date of the most recent successful tracer gas test, as stated in the June 16, 2004 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years. (b) The first performance of the periodic assessment of CRE habitability, specification 5.5.20.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from March 23, 2004, the date of the most recent successful tracer gas test, as stated in the June 16, 2004 letter response to Generic Letter 2003-01 , or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years. The first performance of the periodic measurement of CRE pressure, specification 5.5.20.d, shal.1 be within 18 months, plus the 138 days allowance of SR 3.0.2, as measured from March 23, 2004, the date of the most successful pressure measurement test, or within 138 days if not performed previously. 173 Southern Nuclear Operating Company (SNC) is approved to implement 1 O As stated in the CFR 50.69 using the processes for categorization of Risk-Informed Safety Additional Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and Condition components (SSCs) specified in the licensee amendment request submittals dated August 31, 2012, May 17, 2013, July 2, 2013, September 13, 2013, May 2, 2014, July 22, 2014 and August 11, 2014 .. The licensee shall implement the items listed in enclosure 1, Implementation items of SNC letter NL-14-0960, dated July 22, 2014, prior to categorizing systems under the process. NRC prior approval, under 10 CFR 50.90, is required for a change to a categorization process that is outside the bounds specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment aooroach) .. Vogtle Unit 1 0-2 Amendment No. 173

ML 15078A286 OFFICE NRR/LPL2-1 /PM NRR/LPL2-1/LA OGCINLO NRR/LPL2-1/BC NAME RMartin SFigueroa BMizuno RPascarelli (SWilliams for) DATE . 03/25/15 03/23/15 03/26/15 03/27/15