ML19301B005

Issuance of Amendment No. 239 Administrative Edits to the Technical Specifications

ML19301B005
Person / Time
Site:	Nine Mile Point
Issue date:	11/25/2019
From:	Marshall M Plant Licensing Branch 1
To:	Bryan Hanson Exelon Nuclear
Marhsall M, NRR/DORL/LPL, 415-2871
References
EPID L-2019-LLA-0137
Download: ML19301B005 (19)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 25, 2019 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. 239 RE: ADMINISTRATIVE EDITS TO THE TECHNICAL SPECIFICATIONS (EPID L-2019-LLA-0137)

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 239 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 June 17, 2019 (Agencywide Documents Access and Management System Accession No. ML19169A105).

The amendment makes several editorial changes (e.g., pagination, redundancy, number sequencing, alignment, justification, etc.) to the Nine Mile Point Nuclear Station, Unit 1, Technical Specifications.

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

Sincerely,

~f-~

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. 239 to DPR-63

2. Safety Evaluation cc: Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC NINE MILE POINT NUCLEAR STATION, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 239 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 June 17, 2019, 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.

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:

Enclosure 1

(2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 239, 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 45 days.

FOR THE NUC REGULATORY COMMISSION es G. Danna, Chief 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: November 2 5, 2 O1 9

• ATTACHMENT TO LICENSE AMENDMENT NO. 239 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 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 29 29 29a 29a 30 30 45 45 66 66 67 67 96 96 102 102 108 108 247c 247c 247e 247e

(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; Section 40.41 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 The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 239, 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 thF01::1gh 210,211, 21J, 214,215, 21e, 217,218,220,222, 22J, 224,225,227,229, 2J1, 2JJ, 2J4,

~.W,239 CorFOotion Letter Datec:l A1::1§1::1st 7, 2012 CorFOotion Letter Datec:l Marsh 17, 2015 Correotion Letter dated J1::1ly 29, 2016

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.1.1 CONTROL ROD SYSTEM 4.1.1 CONTROL ROD SYSTEM Applicability: Applicability:

Applies to the operational status of the control rod Applies to the periodic testing requirements for the control system. rod system.

Objective: Objective:

To assure the capability of the control rod system to To specify the tests or inspections required to assure the control core reactivity. capability of the control rod system to control core reactivity.

Specification: Specification:

The control rod system surveillance shall be performed as indicated below.

a. Reactivity Limitations a. Reactivity Limitations (1) Reactivity margin - core loading (1) Reactivity margin - core loading (a) The Shutdown Margin (SOM) under all The SOM shall be verified within limits:

operational conditions shall be equal to or greater than: (a) Prior to each in vessel fuel movement during the fuel loading sequence, and 0.38% i1k/k, with the highest worth control rod analytically determined, or (b) Once within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after criticality following fuel movement within the reactor pressure 0.28% i1k/k, with the highest worth control vessel or control rod replacement.

rod determined by test.

AMENDMENT NO. 142, 180, 239 29

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT (b) If one or more control rods are determined to be inoperable as defined in Specification 3.1.1 a(2) while in the power operating condition, then a determination of whether Specification 3.1.1a(1 )(a) is met must be made within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. If a determination cannot be made within the specified time period, then assume Specification 3.1.1a(1)(a) is not met.

(c) If Specification 3.1.1a(1)(a) is not met while in the power operating condition, restore compliance with Specification 3.1.1a(1 )(a) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in a shutdown condition within the following 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

(d) If Specification 3.1.1a(1)(a) is not met while in the hot shutdown condition or the cold shutdown condition, then:

Immediately initiate action to fully insert all insertable control rods, and Initiate action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore secondary containment to operable status, and Initiate action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore one emergency ventilation system to operable status, and Initiate action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore isolation capability in each required AMENDMENT NO. +SG, 239 29a

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT secondary containment penetration flow path not isolated.

(e) If Specification 3.1.1a(1)(a) is not met while in the refueling condition, then:

Immediately suspend core alterations, except for fuel assembly removal, and Immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

(2) Reactivity margin - stuck control rods (2) Reactivity margin - stuck control rods Control rods which cannot be moved with Each withdrawn control rod shall be control rod drive pressure shall be considered exercised in accordance with the Surveillance inoperable. Inoperable control rods shall be Frequency Control Program after the valved out of service, in such positions that control rod has been withdrawn and power Specification 3.1.1 a( 1)(a) is met. In no case level is greater than the low power set point shall the number of non-fully inserted rods of the RWM. Insert each withdrawn control valved out of service be greater than six rod at least one notch.

during power operation. If this specification is not met, the reactor shall be placed in the This test shall be performed at least once per cold shutdown condition. If a partially or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event power operation is fully withdrawn control rod drive cannot be continuing with two or more inoperable moved with drive or scram pressure the control rods or in the event power operation reactor shall be brought to a shutdown is continuing with one fully or partially condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless withdrawn rod which cannot be moved and investigation demonstrates that the cause of for which control rod drive mechanism the failure is not due to a failed control rod damage has not been ruled out. The drive mechanism collet housing. surveillance need not be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the number of inoperable rods has been reduced to less than two and if it has been demonstrated that control rod drive mechanism collet housing failure is not the cause of an immovable control rod.

AMENDMENT NO. 142, 180, 200,222,239 30

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

c. The liquid poison tank shall contain a minimum of Remove the squibs from the valves and verify that 1325 gallons of boron bearing solution. The no deterioration has occurred by actual field firing of solution shall have a sufficient concentration of the removed squibs. In addition, field fire one squib sodium pentaborate enriched with Boron-10 from the batch of replacements.

isotope to satisfy the equivalency equation.

Disassemble and inspect the squib-operated valves Q_ X 628300 X Q X _E__ ~ 1 to verify that valve deterioration has not occurred.

13% wt M 86 GPM 19.8% Atom (2) In accordance with the Surveillance Frequency Where: C = Sodium Pentaborate Solution Control Program -

Concentration (Wt % )

Demineralized water shall be recycled to the test M = Mass of Water in Reactor Vessel and tank. Pump discharge pressure and minimum flow Recirculation piping at Hot Rated rate shall be verified.

Conditions (501500 lb)

b. Boron Solution Checks:

Q = Liquid Poison Pump Flow Rate (30 GPM nominal) (1) In accordance with the Surveillance Frequency Control Program -

E = Boron-10 Enrichment (Atom%)

Boron concentration shall be determined.

d. The liquid poison solution temperature shall not be less than the temperature presented in Figure (2) In accordance with the Surveillance Frequency 3.1.2.b. Control Program -

e. If Specifications "a" through "d" are not met, Solution volume shall be checked. In addition, the initiate normal orderly shutdown within one hour. sodium pentaborate concentration shall be determined and conformance with the requirements of the equivalency equation shall be checked any time water or boron are added or if the solution temperature drops below the limits specified by Figure 3.1.2.b.

AMENDMENT NO. 142, 166,222,239 45

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until APLHGR at all nodes is within the prescribed limits.

b. Linear Heat Generation Rate (LHGR) b. Linear Heat Generation Rate (LHGR)

During power operation, the LHGR of any rod in The LHGR as a function of core height shall be any fuel assembly at any axial location shall not checked in accordance with the Surveillance exceed the limiting value specified in the Core Frequency Control Program during reactor Operating Limits Report. operation at ~25% rated thermal power.

If at any time during power operation it is determined by normal surveillance that the limiting value for LHGR is being exceeded at any location, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If the LHGR at all locations is not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until LHGR at all locations is within the prescribed limits.

c. Minimum Critical Power Ratio {MCPR) c. Minimum Critical Power Ratio (MCPR)

During power operation, the MCPR for all fuel at (1) MCPR shall be determined in accordance with rated power and flow shall be within the limit the Surveillance Frequency Control Program provided in the Core Operating Limits Report. during reactor power operation at >25% rated thermal power.

If at any time during power operation it is determined by normal surveillance that the above (2) MCPR operating limit shall be determined limit is no longer met, action shall be initiated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of completing scram time within 15 minutes to restore operation to within testing as required in Specification 4.1.1(c).

AMENDMENT NO. 142, 143, 1Q3, 222, 239 66

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT the prescribed limit. If all the operating MCPRs are not returned to within the prescribed limit within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until MCPR is within the prescribed limit. For core flows other than rated, the MCPR limit shall be the limit identified above times Kt where Kt is provided in the Core Operating Limits Report.

d. Power Flow Relationship During Operation d. Power Flow Relationship This power/flow relationship shall not exceed the Compliance with the power flow relationship in limiting values shown in the Core Operating Limits Section 3.1. 7 .d shall be determined in accordance Report. with the Surveillance Frequency Control Program during reactor operation.

If at any time during power operation it is determined by normal surveillance that the limiting value for the power/flow relationship is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If the power/flow relationship is not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until the power/flow relationship is within the prescribed limits.

e. Partial Loop Operation e. Partial Loop Operation During power operation, partial loop operation is Under partial loop operation, surveillance permitted provided the following conditions are requirements 4.1. 7, a, b, c and d above are met. applicable.

AMENDMENT NO. 142, 143,222,239 67

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.3 COOLANT CHEMISTRY 4.2.3 COOLANT CHEMISTRY Applicability: Applicability:

Applies to the reactor coolant system chemical Applies to the periodic testing requirements of the requirements. reactor coolant chemistry.

Objective: Objective:

To assure the chemical purity of the reactor coolant To determine the chemical purity of the reactor water. coolant water.

Specification: Specification:

a. The reactor coolant water shall not exceed the Samples shall be taken and analyzed for conductivity, following limits for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the coolant chloride and sulfate ion content in accordance with temperature ~200 degrees F and reactor thermal the Surveillance Frequency Control Program. In power ::,; 10%, or a shutdown shall be initiated addition, if the conductivity becomes abnormal (other within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the reactor shall be shutdown than short term spikes) as indicated by the continuous and reactor coolant temperature be reduced to conductivity monitor, samples shall be taken and

<200 degrees F within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Conductivity 1 µmho/cm* When the continuous conductivity monitor is Chloride ion 100 ppb inoperable, a reactor coolant sample shall be taken Sulfate ion 100 ppb and analyzed for conductivity, chloride and sulfate ion content at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

• During Noble Metal Chemical Addition (NMCA), the limit is 20 µmho/cm. Post NMCA, the conductivity limit is 2 µmho/cm for up to a 5 month period at power operation.

AMENDMENT NO. 142, 163, 16Q, 222,239 96

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

b. Any time irradiated fuel is in the reactor vessel b. The following surveillance shall be performed on and reactor coolant temperature is above 212°F, each leakage detection system:

at least one of the leakage measurement channels associated with each sump (one for the (1) An instrument calibration in accordance drywell floor drain and one for the equipment with the Surveillance Frequency Control drain) shall be operable. Program.

If the conditions a or b cannot be met, the reactor will (2) An instrument functional test in accordance be placed in the cold shutdown condition within 24 with the Surveillance Frequency Control hours. Program.

AMENDMENT NO. 142, 222, 239 102

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES 4.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES Applicability: Applicability:

Applies to the operating status of the system of Applies to the periodic testing requirement for the isolation valves on lines connected to the reactor reactor coolant system isolation valves.

coolant system.

Objective: Objective:

To assure the capability of the reactor coolant system To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear event of a rupture of a line connected to the nuclear steam supply system, and to minimize potential leakage steam supply system, and to limit potential leakage paths from the primary containment in the event of a loss- paths from the primary containment in the event of a of-coolant accident. loss-of-coolant accident.

Specification: Specification:

a. Whenever fuel is in the reactor vessel and the reactor The reactor coolant system isolation valves coolant temperature is greater than 212°F, all reactor surveillance shall be performed as indicated below.

coolant system isolation valves on lines connected to the reactor coolant system shall be operable except a. In accordance with the Surveillance as specified in Specification 3.2.7.b below. Frequency Control Program the operable automatically initiated power-operated

b. In the event any isolation valve becomes isolation valves shall be tested for automatic inoperable whenever fuel is in the reactor vessel and initiation and closure times.

the reactor coolant temperature is greater than 212°F, the system shall be considered operable b. Additional surveillances shall be performed as 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 required by the INSERVICE TESTING PROGRAM.

each line having an inoperable valve is in the mode corresponding to the isolated condition, except as noted in Specification 3.1.1.e.

AMENDMENT N0.142, 145, 173, 181,197,222,227,239 108

TABLE 3.6.2m RPV WATER INVENTORY CONTROL INSTRUMENTATION Limiting Condition for Operation Minimum No. of Operable Instrument Reactor Mode Switch Minimum No. Channels per Position in Which of Tripped or Operable Function Must Be Parameter Operable Trip Systems Trip System Set Point Operable C:

~

0 C.

"tJ "'i j t::

j j C:

J: Cl) ns j u, 0::: u, 0:::

PRIMARY COOLANT ISOLATION (2) Low-Low Reactor Water Level (a) Cleanup 2 2(c) ~ 5 inches (a) (a)

(Indicator Scale)

(b) Shutdown Cooling 2 2(c) ~ 5 inches (a) (a)

(Indicator Scale)

(3) Manual 2 1 --- (a) (a)

AMENDMENT NO.~. 239 247c

TABLE 4.6.2m RPV WATER INVENTORY CONTROL INSTRUMENTATION Surveillance Requirement Instrument Instrument Channel Parameter Sensor Check Channel Test Calibration PRIMARY COOLANT ISOLATION (Cleanup and Shutdown Cooling)

(2) Low-Low Reactor Water Note 1 Note 1 Level (3) Manual Note 1 AMENDMENT NO.~. 239 247e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 239 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 June 17, 2019 (Agencywide Documents Access and Management System Accession No. ML19169A105), Exelon Generation Company, LLC (Exelon or the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station, Unit 1 (Nine Mile Point 1), Technical Specifications (TSs). The requested changes would make several editorial changes (e.g., pagination, redundancy, number sequencing, alignment, justification, etc.) to the Nine Mile Point 1 TSs. In the request, the licensee refers to the editorial changes as administrative changes.

2.0 REGULATORY EVALUATION

Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR) requires that each licensee operate a station in accordance with plant-specific TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation:

1) safety limits, limiting safety system settings, and limiting control settings;

2) limiting conditions for operation;

3) surveillance requirements;

4) design features; and

5) administrative controls.

The requirements in 10 CFR 50.36 do not specify the particular requirements to be included in a station's TSs nor the format or style of a station's TSs. The proposed changes to the Nine Mile Point 1 TSs are editorial in nature and, as such, do not make meaningful changes to operational requirements.

Enclosure 2

3.0 TECHNICAL EVALUATION

The proposed amendment would make several editorial changes to the Nine Mile Point 1 TSs.

The proposed changes are described on pages 1 and 2 of Attachment 1 and Attachment 2 to Exelon's letter dated June 17, 2019.

None of the proposed changes to the Nine Mile Point 1 TSs would change the operation of the station or the implementation of the Nine Mile Point 1 TSs. Since the changes are editorial in nature and do not change the permissible operation of the station (i.e., they do not change the requirements in the TSs), the U.S. Nuclear Regulatory Commission (the Commission) staff finds the proposed changes acceptable.

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 28, 2019. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment relates to editorial or other minor revisions to the license. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration in the Federal Register on September 10, 2019 (84 FR 47547), and there has been no public comment on such finding.

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 Contributor: Michael Marshall Date: November 25, 2019

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT 1 - ISSUANCE OF AMENDMENT NO. 239 RE: ADMINISTRATIVE EDITS TO THE TECHNICAL SPECIFICATIONS (EPID L-2019-LLA-0137) DATED NOVEMBER 25, 2019 DISTRIBUTION:

PUBLIC PM File Copy RidsNrrDorlLpl1 RidsRgn1 MailCenter RidsACRS_MailCTR RidsNrrLALRonewicz Resource RidsNrrPMNineMilePoint RidsNrrDssStsb Resource ADAMS Access1on No.: ML193018005 *b1y e-ma1*1 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA OGC- NLO* DORL/LPL 1/BC DORL/LPL 1/PM NAME MMarshall CSmith RAuqustus JDanna MMarshall DATE 11/06/2019 11/04/2019 11/21/2019 11/25/2019 11/25/2019 OFFICIAL RECORD COPY