ML24268A338

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Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
ML24268A338
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/16/2024
From: Richard Guzman
NRC/NRR/DORL/LPL1
To: Rhoades D
Constellation Energy Generation, Constellation Nuclear
References
EPID L-2023-LLA-0146
Download: ML24268A338 (12)


Text

October 16, 2024 David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT 1 - ISSUANCE OF AMENDMENT NO. 253 REGARDING THE MODIFICATION OF TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENT 4.3.6.A RELATED TO ADOPTION OF TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-425, REVISION 3 (EPID L-2023-LLA-0146)

Dear David P. Rhoades:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 253 to Renewed Facility Operating License No. DPR-63 for the Nine Mile Point Nuclear Station, Unit 1 (NMP1). The amendment consists of changes to the technical specifications (TSs) in response to your application dated October 18, 2023.

The amendment revises the NMP1 TSs by relocating surveillance requirement (SR) 4.3.6.a to the licensee-controlled surveillance frequency control program (SFCP). The SFCP was previously implemented at NMP1 by License Amendment No. 222 dated May 16, 2016; however, the SR was not fully revised with the adoption of NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-425, Revision 3, Relocated Surveillance Frequencies to Licensee Control - RITSTF

[Risk-Informed TSTF] Initiative 5b. Specifically, the amendment corrects the SR specification to include the surveillance frequency for the verification of the operability of the valves, position switches, and position indicators and alarms, in the SFCP, consistent with TSTF-425, Revision 3.

D. Rhoades A copy of the related safety evaluation is enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosures:

1. Amendment No. 253 to DPR-63
2. Safety Evaluation cc: Listserv NINE MILE POINT NUCLEAR STATION, LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 253 Renewed License No. DPR-63 1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Constellation Energy Generation, LLC dated October 18, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-63 is hereby amended to read as follows:

2.C.(2)

Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 253, is hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.

3.

This amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: October 16, 2024 HIPOLITO GONZALEZ Digitally signed by HIPOLITO GONZALEZ Date: 2024.10.16 11:09:19 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 253 NINE MILE POINT NUCLEAR STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page Insert Page 4

4 Replace the following page of Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page Insert Page 153 153 Renewed License No. DPR-63 Revised by letter dated February 21, 2007 Amendment No. 195, 209, 214, 219, 220, 247, 250-252, 253 (1)

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 253, is hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.

(3)

Deleted D.

This license is subject to the following additional conditions:

(1)

NMP LLC will complete construction of a new radwaste facility in conformance with the design defined and evaluated in the FES, to be operational no later than June 1976.

(2)

Deleted by License Amendment No. 51 (3)

Deleted by License Amendment No. 51 (4)

Security, Training and Qualification and Safeguards Contingency Plans Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to the 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 combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21 is entitled Nine Mile Point Nuclear Station, LLC Physical Security, Safeguards Contingency, and Security Training and Qualification Plan, Revision 1, and was submitted by letter dated April 26, 2006.

Constellation Energy Generation, 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 licensees CSP was approved by License Amendment No. 209 and modified by License Amendment No. 219. The licensee has obtained Commission authorization to use Section 161A preemption authority under 42 U.S.C 2201a for weapons at its facility.

(5)

Paragraph 2.D(5) of the license has been combined with paragraph 2.D(4) as amended above into a single paragraph.

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.3.6 VACUUM RELIEF Applicability:

Applies to the operational status of the primary containment vacuum relief system.

Objective:

To assure the capability of the vacuum relief system in the event of a loss-of-coolant accident to:

a.

Equalize pressures between the drywell and suppression chamber, and b.

Maintain containment pressure above the vacuum design values of the drywell and suppression chamber.

Specification:

a.

When primary containment is required, all suppression chamber - drywell vacuum breakers shall be operable except during testing and as stated above. Suppression chamber - drywell vacuum breakers shall be considered operable if:

(1) The valve is demonstrated to open fully with the applied force at all valve positions not exceeding that equivalent to 0.5 psi acting on the suppression chamber face of the valve disk.

4.3.6 VACUUM RELIEF Applicability:

Applies to the periodic testing of the vacuum relief system.

Objective:

To assure the operability of the containment vacuum relief system to perform its intended functions.

Specification:

a.

Periodic Operability Tests In accordance with the Surveillance Frequency Control Program and following any release of energy to the suppression chamber, each suppression chamber -

drywell vacuum breaker shall be exercised.

Operability of valves, position switches, and position indicators and alarms shall be verified in accordance with the Surveillance Frequency Control Program and following any maintenance on the valves and associated equipment.

AMENDMENT NO. 142, 222, 253 153 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR AMENDMENT NO. 253 TO RENEWED FACILITY OPERATING LICENSE NO DPR-63 CONSTELLATION ENERGY GENERATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-220

1.0 INTRODUCTION

By letter dated October 18, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23291A246), Constellation Energy Generation, LLC (CEG, the licensee) submitted a license amendment request (LAR) to revise the technical specifications (TSs) for Nine Mile Point Nuclear Station, Unit 1 (NMP1).

The proposed changes would modify the NMP1 TSs by relocating Surveillance Requirement (SR) 4.3.6.a to the licensee-controlled Surveillance Frequency Control Program (SFCP). The SFCP was previously implemented at NMP1 by License Amendment No. 222 (ML16081A256) dated May 31, 2016. The SR 4.3.6.a was within the scope of Amendment No. 222; however, it was not fully revised with the adoption of Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-425, Revision 3, Relocated Surveillance Frequencies to Licensee Control -

RITSTF [Risk-Informed TSTF] Initiative 5b (ADAMS Package ML090850642). Specifically, the proposed change would correct the SR specification to include the surveillance frequency for the verification of the operability of the valves, position switches, and position indicators and alarms, in the SFCP, consistent with TSTF-425, Revision 3.

2.0 REGULATORY EVALUATION

2.1 Applicable Regulatory Requirements and Guidance The regulation at section 50.36(c)(3) of Title 10 or the Code of Federal Regulations (CFR) requires that TSs include items in the category of SRs, which are requirements relating to test, calibration, or inspection needed to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the Limiting Conditions for Operation will be met.

NRC Regulatory Guide 1.177, An Approach for Plant-Specific, Risk-Informed Decision-making:

Technical Specifications, Revision 1, provides a framework for evaluating the risk impact of proposed changes to surveillance frequencies which requires identification of the risk contribution from impacted surveillances, determination of the risk impact from the change to the proposed surveillance frequency, and performance of sensitivity and uncertainty evaluations. The application of NEI Energy Institute (NEI) 04-10, Revision 1, in accordance with the SFCP administrative controls in NMP1 TS Section 6.5.9 satisfies the intent of Regulatory Guide 1.177.

2.2 Proposed Changes to NMP1 TS SR 4.3.6.a Currently, NMP1 TS SR 4.3.6.a, Vacuum Relief, states:

In accordance with the Surveillance Frequency Control Program and following any release of energy to the suppression chamber, each suppression chamber-drywell vacuum breaker shall be exercised. Operability of valves, position switches, and position indicators and alarms shall be verified monthly and following any maintenance on the valves and associated equipment.

The proposed amendment would revise SR 4.3.6.a to read as follows:

In accordance with the Surveillance Frequency Control Program and following any release of energy to the suppression chamber, each suppression chamber-drywell vacuum breaker shall be exercised. Operability of valves, position switches, and position indicators and alarms shall be verified in accordance with the Surveillance Frequency Control Program and following any maintenance on the valves and associated equipment.

3.0 TECHNICAL EVALUATION

3.1 Background

On May 31, 2016, the NRC issued License Amendment No. 222 for NMP1 in response to the LAR dated May 12, 2015 (ML15134A232) submitted by Exelon Generation Company, LLC (Exelon, the licensee at the time). The amendment revised the NMP1 TSs by relocating specific SR frequencies to a licensee-controlled program (i.e., the Surveillance Frequency Control Program (SFCP)) in accordance with NEI 04-10, Revision 1, Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies (ML071360456). The changes were consistent with the adoption of NRC-approved TSTF-425, Revision 3.

In its LAR dated October 18, 2023, CEG (the current licensee) requested to fully relocate SR 4.3.6.a to the licensee-controlled SFCP as it was identified that the SR was implemented into the NMP1 TS as part of License Amendment No. 222, but the associated change was not completely revised into SR 4.3.6.a specification.

3.2

NRC Staff Evaluation

The licensee proposed to relocate SR 4.3.6.a to the licensee-controlled SFCP. The licensee adopted TSTF-425, Revision 3, following NRCs approval of the associated NMP1 LAR (ML15134A232) on May 31, 2016 (ML16081A256). The NRC staff reviewed the NMP1 LAR to adopt TSTF-425 and determined that SR 4.3.6.a was within the scope of the SFCP; however, the second sentence of SR 4.3.6.a was not fully revised to correctly reflect the intended change per the TSTF-425 adoption. Specifically, the term monthly was not replaced with in accordance with the Surveillance Frequency Control Program. Currently, SR 4.3.6.a states in part, Operability of valves, position switches, and position indicators and alarms shall be verified monthly and following any maintenance on the valves and associated equipment.

The proposed change would include the surveillance frequency for the verification of the operability of the valves, position switches, and position indicators and alarms, in the SFCP, and therefore, would correct the partial change made to the SR in the adoption of TSTF-425.

Section 2.0 of TSTF-425 states that, the proposed change relocates all periodic Surveillance Frequencies from the Technical Specifications and places the Frequencies under licensee control in accordance with the SFCP, except for surveillance frequencies that meet the four exclusion criteria in Section 2.0.

The NRC staff considers the proposed change as administrative in nature. The staff reviewed the proposed change to SR 4.3.6.a and determined that the change is consistent with the intent of the TSTF-425 revision as requested in the original May 12, 2015, LAR, and as evaluated in the approved License Amendment No. 222 for NMP1. The staff finds that that the proposed change to SR 4.3.6.a is a periodic frequency, does not meet any of the exclusion criteria listed in Section 2.0 of TSTF-425, and continues to meet the requirements of 10 CFR 50.36(c)(3).

Therefore, the NRC staff concludes that the change is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the New York State official was notified of the proposed issuance of the amendment on August 27, 2023. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and involves changes to SRs. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (88 FR 88983, December 26, 2023). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: T. Sweat, NRR Date: October 16, 2024

ML24268A338 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DSS/STSB/BC NAME RGuzman KZeleznock SMehta DATE 09/24/2024 09/26/2024 08/26/2024 OFFICE OGC (NLO)

NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME MCarpentier HGonzález RGuzman DATE 10/11/2024 10/11/2024 10/15/2024