NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process
| ML22084A062 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/25/2022 |
| From: | Strope M Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2022-0003 | |
| Download: ML22084A062 (7) | |
Text
{{#Wiki_filter:March 25, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 RE: Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 NEXTera ENERGY£& POINT BEACH NRC 2022-0003 10 CFR 50.90 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process In accordance with the provisions of 10 CFR 50.90, NextEra Energy Point Beach, LLC (NextEra) is submitting a request for an amendment to the technical specifications (TS) for Facility Operating Licenses DPR-24 and DPR-27 to Point Beach Nuclear Plant (Point Beach), Units 1 and 2, respectively. The proposed amendment would delete Technical Specification (TS) 5.5.3, "Post Accident Sampling System (PASS)," and thereby eliminate the requirements to have and maintain the PASS at Point Beach Units 1 and 2. The changes are consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-366, "Elimination of Requirements for a Post-Accident Sampling System (PASS)." The availability of this technical specification improvement was announced in the Federal Register on October 31, 2000 as part of the consolidated line item improvement process (CLIIP). Technical justification for this change is included in WCAP-14986-A, Revision 2, "Westinghouse Owners Group Post Accident Sampling System Requirements: A Technical Basis," (ADAMS Accession No. ML003740248) and approved by the NRC in the associated Safety Evaluation dated June 14, 2000 (ADAMS Accession No. M L003723268). The enclosure to this letter contains a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications. Attachment 1 to the enclosure provides the existing Technical Specification (TS) page marked-up to show the proposed change. Attachment 2 provides the revised clean TS page. Attachment 3 provides a summary of the regulatory commitments made in this submittal. There are no changes to the TS Bases proposed in this amendment request. NextEra requests approval of the proposed License Amendments by September 2022, with the amendment being implemented by February 28, 2023. NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 NRC 2022-0003 Page 2 of 2 In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated State of Wisconsin official. If you should have any questions regarding this submittal, please contact Eric Schultz, Licensing Manager, at (920) 755-7854. I declare under penalty of perjury that the foregoing is true and correct. Executed on March 21, 2022. Sincere!~~ ~---=:::>- ~Strope Site Vice President NextEra Energy Point Beach, LLC cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Public Service Commission of Wisconsin Enclosure Attachments
- 1.
Proposed Technical Specification Changes (Mark-Up)
- 2.
Proposed Technical Specification Changes (Clean copy)
- 3.
Summary of Regulatory Commitments
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301
1.0 DESCRIPTION
ENCLOSURE DESCRIPTION AND ASSESSMENT NRC 2022-0003 Enclosure Page 1 of 5 The proposed License Amendment deletes the program requirements of the Point Beach Nuclear Plant (Point Beach) TS (5.5.3), "Post Accident Sampling System (PASS)." The changes for PASS elimination are consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-366. The availability of this technical specification improvement was announced in the Federal Register on October 31, 2000 as part of the consolidated line item improvement process (CLIIP). 2.0
2.1 ASSESSMENT
Applicability of Published Safety Evaluation NextEra Energy Point Beach, LLC (NextEra) has reviewed the safety evaluation published on October 31, 2000 as part of the CLIIP. This verification included a review of the NRC staff's evaluation as well as the supporting information provided to support TSTF-366 (i.e., WCAP-14986-A, Rev.2, "Post Accident Sampling System Requirements: A Technical Basis," submitted October 26, 1998, (ML20155D882) as supplemented by letters dated April 28, 1999 (ML003740248), April 10, 2000 (ML003703586) and May 22, 2000. NextEra has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Point Beach and justify this amendment for the incorporation of the changes to the Point Beach Technical Specifications. 2.2 Optional Changes and Variations NextEra is not proposing any variations or deviations from the technical specification changes described in TSTF-366 or the NRC staff's model safety evaluation published on October 31, 2000. Requirements for installing and maintaining PASS were included in a confirmatory order for Point Beach issued on September 30, 1982 (ML20063N629). This amendment request includes superseding the requirements imposed by that confirmatory order. 3.0
3.1 REGULATORY ANALYSIS
No Significant Hazards Determination NextEra has reviewed the proposed no significant hazards consideration determination published on October 31, 2000 as part of the CLIIP. NextEra has concluded that the proposed determination presented in the notice is applicable to Point Beach and the determination is hereby incorporated by reference to satisfy the requirements of 1 O CFR 50.91 (a).
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 NRC 2022-0003 Enclosure Page 2 of 5 3.2 Verification and Commitments As discussed in the notice of availability published in Federal Register on October 31, 2000 for this technical specification improvement, plant-specific verifications were performed as follows:
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NextEra has drafted contingency plans for obtaining and analyzing highly radioactive samples of reactor coolant, containment sump, and containment atmosphere. The contingency plans will be contained in plant procedures and implemented with the implementation of the License Amendment. Establishment of contingency plans is considered a regulatory commitment.
- 2.
The capability for classifying fuel damage events at the Alert level threshold has been established for Point Beach at radioactivity levels of 300 µCi/gm dose equivalent iodine. This capability will be described in emergency plan implementing procedures and implemented with the implementation of the License Amendment. The capability for classifying fuel damage events is considered a regulatory commitment.
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NextEra has established the capability to monitor radioactive iodines that have been released to offsite environs. This capability is described in our emergency plan implementing procedures. The capability to monitor radioactive iodines is considered a regulatory commitment. 4.0 ENVIRONMENTAL EVALUATION NextEra has reviewed the environmental evaluation included in the model safety evaluation published on October 31, 2000 as part of the CLI IP. NextEra has concluded that the staff's findings presented in that evaluation are applicable to Point Beach and the evaluation is hereby incorporated by reference for this application. 5.0 5.1 5.2
5.3 REFERENCES
lndustry/TSTF Standard Technical Specification Change Traveler TSTF-366 "Elimination of Requirements for a Post-Accident Sampling System (PASS)." Federal Register, Vol. 65, No. 211, "Notice of Availability for Referencing in License Amendment Applications Model Safety Evaluation on Technical Specifications Improvement to Eliminate Requirements on Post Accident Sampling Systems Using the Consolidated Line Item Improvement Process," dated October 31, 2000. WOG Safety Evaluation, WCAP-14986, Revision 1, "Westinghouse Owners Group Post Accident Sampling System Requirements," June 14, 2000 (ML003723268).
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 ATTACHMENT 1 NRC 2022-0003 Enclosure Page 3 of 5 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP) Programs and Manuals 5.5 5.5 Programs and f1Jlanuals 5.5.2 Primary Coolant Sources Outside Containment 5.5.3 Point Beach This program provides controls to minimize leakage from those portions of systems outside containment that coufd contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Containment Spray, Safety Injection (High Head} and Safety Injection (Low Head} systems. The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
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Integrated leak test requirements for each system at refueling cycle intervals or less. Past AeeiElenl SampliRg-- DELETED This l)f6!:Jfflffl pFo,ides-6fltrel-s-that-eflstffe--lhe ea13ability ta ablain a1lEI aflalyze Feaetof eoola11t, Fadioaeli',e gases, afld partiettlates ifl plafll -{laseous efflueA~ 1ul-e-0AtaiAn~enl aln1espl:lern samples undel'-a(;{;ide111 eanElilians. Tl'le pragrani sl'lall include ll'le fellawing:
- a.
Trainiflg-Gf-peFS9AAel~ C eedttfes fof samplifl!:J afld :malysis; afld Pcovisioos tor nninl.,llance gf san1pling-iind analysis equipmettt:- 5.5-2 Unit *1 - Amendment No.~ Unit 2 - Amendment No. ~
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 NRC 2022-0003 Enclosure Page 4 of 5 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION PAGES (CLEAN PAGES) 1-'rograms ano Manums 5.5 5.5 Programs and fl, anuals 5.5.2 Primarv Coolant Sources Outside Containmen 5.5.3 Point Beach This progrnm provides controls lo minimize leakage from those por1!ions o systems oulside containmen ha could contain highl)* radioactive fluids during a serious transient or accidenl o levels as low as practicable. T e systems include Con ainment Spray, Safety lnje&lion (High Head) and Safety lnjec *on {low Head) s}*sten s. The program shall include the following:
- a.
Pre*. entive maintenance and p,eriodic visual inspection requirements; and
- b.
In egrated leak tesl requirements for each system at refueling cycle intervals or less. Deleted 5.5-2 Unit 1 - Amendment No. XXX Unit 2 - Amendment No. YYY
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS NRC 2022-0003 Enclosure Page 5 of 5 The following table identifies those actions committed to by Point Beach Nuclear Plant in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Regulatory Commitments Due Date/Event NextEra has drafted contingency plans for obtaining and analyzing highly radioactive samples of reactor coolant, containment sump, and containment atmosphere. The contingency plans will be contained within site procedures CAMP 611, CAMP 612, and EPIP Complete 8.4.3. and implemented with the implementation of the License Amendment. Establishment of contingency plans is considered a regulatory commitment. The capability for classifying fuel damage events at the Alert level threshold has been established for Point Beach at radioactivity levels of 300 uCi/gm dose equivalent iodine. This capability will be described in plant implementing procedures and implemented with Complete the implementation of the License Amendment. The capability for classifying fuel damage events is considered a regulatory commitment. NextEra has established the capability to monitor radioactive iodines that have been released to offsite environs. This capability is described in our emergency plan implementing procedures. The Complete capability to monitor radioactive iodines is considered a regulatory commitment.}}