ML18324A723

Issuance of Amendment No. 233 Relocation of Surveillance Requirement Frequencies to Inservice Testing Program

ML18324A723
Person / Time
Site:	Nine Mile Point
Issue date:	12/13/2018
From:	Marshall M Plant Licensing Branch 1
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Marshall M, NRR/DORL/LPL, 415-2871
References
EPID L-2018-LLA-0071
Download: ML18324A723 (12)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 13, 2018 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT 1 - ISSUANCE OF AMENDMENT NO. 233 RE: RELOCATION OF SURVEILLANCE REQUIREMENT FREQUENCIES TO INSERVICE TESTING PROGRAM (EPID L-2018-LLA-0071)

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 233 to Renewed Facility Operating License No. DPR-63 for the Nine Mile Point Nuclear Station, Unit 1. The amendment consists of changes to the Technical Specifications in response to your application dated March 13, 2018.

The amendment would revise the Nine Mile Point Nuclear Station, Unit 1, Technical Specifications by relocating surveillance frequencies for Surveillance Requirements 4.2.7.d for "Reactor Coolant System Isolation Valves" and 4.2.7.1.a for "Reactor Coolant System Pressure Isolation Valve (PIV) Leakage" to the Nine Mile Point Nuclear Station, Unit 1, lnservice Testing Program.

A copy of the related Safety Evaluation is also enclosed. Notice of issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Michael L. Marshall, Jr., 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. 233 to DPR-63

2. Safety Evaluation cc: Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 233 Renewed License No. DPR-63

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

A. The application for amendment by Exelon Generation Company, LLC (Exelon, the licensee) dated March 13, 2018, 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 rules and 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

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) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 233, is hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION J:3.::?::-

Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: Dec em be r 13 , 2 0 18

ATTACHMENT TO LICENSE AMENDMENT NO. 233 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 area of change.

Remove Page Insert Page 3 3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 109 109 116 116

(1) Exelon Generation pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (2) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components.

(5) Exelon Generation pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30; Section40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below:

(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 and Environmental Protection Plan The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 233, is hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.

(3) Deleted Renewed License No. DPR-63 Amendment No. 191 thrmigh 210, 211, 213, 214, 215, 21e, 217, 218, 220, 222, 223, 224, 225, 227, 229, 231, 233 CorrestiOA Letter Dated A1:1g1:1st 7, 2012 CorrestioA Letter Dated March 17, 2015 CorrestioA Letter dated J1:1ly 29, 201e

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

c. If Specifications 3.2.7a and b above are not met, c. In accordance with the Surveillance Frequency initiate normal orderly shutdown within one hour Control Program the feedwater and main-steam and have reactor in the cold shutdown condition line power-operated isolation valves shall be within ten hours. exercised by partial closure and subsequent reopening.

d. Whenever fuel is in the reactor vessel and the reactor coolant temperature is less than or equal to 212°F, d. In accordance with the INSERVICE TESTING the isolation valves on the shutdown cooling system PROGRAM the feedwater and main steam line lines connected to the reactor coolant system shall be power-operated isolation valves shall be fully operable except as specified in Specification 3.2.7.e closed and reopened.

below.

e. In the event any shutdown cooling system isolation valve becomes inoperable whenever fuel is in the reactor vessel and the reactor coolant temperature is less than or equal to 212°F, the system shall be considered operable provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, at least one valve in each line having an inoperable valve is in the mode corresponding to the isolated condition.

f. If Specifications 3.2.7.d and 3.2.7.e above are not met, either:

(1) Immediately initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs); or (2) Immediately initiate action to restore the valve(s) to operable status.

AMENDMENT NO. 142, 197, 222, 233 109

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2. 7.1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION 4.2.7.1 REACTOR COOLANT SYSTEM PRESSURE VALVE {PIV} LEAKAGE ISOLATION VALVE {PIV} LEAKAGE Applicability: Applicability:

Applies to the operating status of isolation valves for Applies to the periodic testing of reactor coolant system systems connected to the reactor coolant system. pressure isolation valves.

Objective: Objective:

To increase the reliability of reactor coolant system To increase the reliability of reactor coolant system pressure isolation valves thereby reducing the pressure isolation valves thereby reducing the potential of an intersystem loss of coolant accident. potential of an intersystem loss of coolant accident.

Specification: Specification:

---

NOTES----------------------------- -------------------------------NOTE---------------------------

1. Separate specification entry is allowed for each Not required to be performed in the hot shutdown flow path. reactor operating condition.

2. Enter applicable specifications for systems made inoperable by PIVs. a. The equivalent leakage of each reactor coolant system PIV shall be verified to bes 0.5 gpm per nominal inch of valve size up to a maximum of

a. The integrity of each pressure isolation valve shall 5 gpm, at a reactor coolant system pressure be demonstrated. Valve leakage shall be within ~ 1010 psig ands 1050 psig, in accordance with limit during the power operating and hot shutdown the INSERVICE TESTING PROGRAM.

reactor operating conditions.

AMENDMENT NO. 142, 206, 233 116

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 233 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-63 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, UNIT 1 DOCKET NO. 50-220

1.0 INTRODUCTION

By letter dated March 13, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18072A182), Exelon Generation Company, LLC (the licensee) submitted a license amendment request (LAR) for changes to the Nine Mile Point Nuclear Station, Unit 1 (Nine Mile Point 1), Technical Specifications (TSs). The proposed amendment would relocate the frequencies for Surveillance Requirement (SR) 4.2.7.d and 4.2.7.1.a to the Nine Mile Point Nuclear Station lnservice Testing Program.

On July 10, 2018, a correction notice was issued in the Federal Register(83 FR 31981) to correct the hearing date in the original notice. The correction notice did not change the U.S. Nuclear Regulatory Commission (NRC or the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on July 3, 2018 (83 FR 31184).

2.0 REGULATORY EVALUATION

The regulatory requirements and guidance that the NRC staff considered in its review of this LAR are described below.

2.1 Regulatory Requirements Title 10 of the Code of Federal Regulations (10 CFR) 50.36, "Technical specifications,"

establishes the regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) SRs; (4) design features; and (5) administrative controls.

The regulation does not specify the particular requirements to be included in a plant's TSs.

Enclosure 2

Section 50.36(a)(1) to 10 CFR requires that a summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the TSs.

Section 50.36(c)(3) to 10 CFR requires that TSs include SRs, which are requirements relating to test, calibration, or inspection, 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.

Section 50.55a of 10 CFR requires, in part, that inservice testing of certain American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 pumps and valves be performed in accordance with the specified ASME Operation and Maintenance of Nuclear Power Plants (OM Code) and applicable addenda incorporated by reference in the regulations.

2.2 Applicable Guidance The guidance that the NRC staff considered in its review of this LAR includes the following from NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition" (hereinafter referred to as the SRP).

Relevant sections of the SRP used in the review of this LAR include the following:

SRP Section 16.0, Revision 3, "Technical Specifications," March 2010 (ADAMS Accession No. ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared Standard Technical Specifications (STS) for each of the light-water reactor nuclear designs. The STS contain guidance for the format and content of TSs that meet the requirements of 10 CFR 50.36. For this review, the NRC staff used NUREG-1433, Revision 4.0, "Standard Technical Specifications, General Electric BWR [Boiling-Water Reactor]/4 Plants, Volume 1, Specifications," April 2012 (ADAMS Accession No. ML12104A192), for guidance on the TS format.

3.0 TECHNICAL EVALUATION

The NRC staff evaluated the licensee's application in accordance with the regulatory requirements and guidance discussed in Section 2.0 of this safety evaluation. In determining whether an amendment to a license will be issued, the Commission is guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate. The application also included proposed changes to the TS bases; however, the changes to the TS Basis are not part of the staff's review and were not considered by the staff.

3.1 Description of Proposed TS SR Changes 3.1.1 Proposed Revision to SR 4.2.7.d The proposed TS SR changes would revise SR 4.2.7.d for "Reactor Coolant System Isolation Valves," which currently states:

At least once per plant cold shutdown the feedwater and main steam line power-operated isolation valves shall be fully closed and reopened, unless this test has been performed within the previous 92 days.

This SR would be modified as follows:

In accordance with the INSERVICE TESTING PROGRAM the feedwater and main steam line power-operated isolation valves shall be fully closed and reopened.

3.1.2 Proposed Revision to SR 4.2.7.1.a The proposed TS SR changes would revise SR 4.2.7.1.a for "Reactor Coolant System Pressure Isolation Valve (PIV) Leakage," which currently states (underline added for emphasis):

The equivalent leakage of each reactor coolant system PIV shall be verified to be s 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a reactor coolant system pressure ~ 1010 psig and s 1050 psig, at a frequency of 24 months.

This SR would be modified as follows (underline added for emphasis):

The equivalent leakage of each reactor coolant system PIV shall be verified to be s 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a reactor coolant system pressure~ 1010 psig ands 1050 psig, in accordance with the INSERVICE TESTING PROGRAM.

3.2 The Proposed Changes Meet Current Regulations The NRC staff reviewed the proposed changes to the Nine Mile Point 1 TS SRs 4.2.7.d and 4.2. 7.1.a. The SRs themselves are remaining in the TSs, as required by 10 CFR 50.36(c)(3).

This change is analogous with other NRG-approved TS changes in which the SRs are retained in TSs, but the related surveillance frequencies are relocated to licensee-controlled documents, such as surveillances performed in accordance with the lnservice Testing Program.

The Nine Mile Point 1 lnservice Testing Program is required by 10 CFR 50.55a to follow ASME Code,Section XI, which includes periodic testing and test frequencies for all reactor coolant system isolation valves that are necessary to assure their continued operability and isolation capability. This applies to all valves currently covered by TSs SR 4.2.7. ASME OM Code-2004 permits valves to be tested quarterly, or during cold shutdown and refueling outages when it is not practical to perform valve testing during plant operation. The ASME OM Code-2004 considers periodic testing without quarterly testing to be sufficient to assure that reactor coolant system isolation valves mitigate the effects of reactor coolant loss by isolating the reactor coolant system in the event of a line rupture.

This proposed change complies with 10 CFR 50.36(c)(3) by retaining the requirements relating to test, calibration, or inspection 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.

3.3 NRC Staff Summary Nine Mile Point 1 TSs are formatted differently than NUREG-1433. The NRC staff noted the content of SR 4.2.7.d and SR 4.2.7.1.a is similar to the associated SRs in NUREG-1433. The

frequency for the associated SRs in NUREG-1433 is "In Accordance with the lnservice Testing Program."

Based on its review, the NRC staff has determined that the content of the SRs, as modified by the proposed changes, will align with the NRC staff's guidance for the content of TSs in NUREG-1433. The proposed amendment complies with 10 CFR 50.36(c)(3) by retaining the requirements relating to test, calibration, or inspection, 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.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment on October 24, 2018. 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 changes 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 (83 FR 31184; July 3, 2018). 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 staff 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 Commission's 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 Contributors: M Hamm T. Hood Date: December 13 2018

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT 1 - ISSUANCE OF AMENDMENT NO. 233 RE: RELOCATION OF SURVEILLANCE REQUIREMENT FREQUENCIES TO INSERVICE TESTING PROGRAM (EPID L-2018-LLA-0071) DATED DECEMBER 13, 2018 DISTRIBUTION:

PUBLIC PM File Copy RidsNrrDorlLpl 1 RidsRgn1 MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsNrrDeEmib Resource RidsNrrDssStsb Resource MHamm, NRR MBreach, NRR ADAMS Access1on No.: ML18324A723 *biy sa f et[Y eva Iua t'10n **b1y e-ma,*1 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DSS/STSB/BC* DE/EMIB/BC*

NAME THood LRonewicz VCusumano SBailey DATE 11/20/2018 11/29/2018 11/09/2018 12/03/2018 OFFICE OGC-NLO* DORL/LPL 1/BC DORL/LPL 1/PM NAME BHarris JDanna MMarshall DATE 12/11/2018 12/13/2018 12/13/2018 OFFICIAL RECORD COPY