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.

Docket No. 50-220

Enclosures:

1. Amendment No. 239 to DPR-63

2. Safety Evaluation cc: Listserv Sincerely,

~f-~

Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

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:

(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.

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance:

November 2 5, 2 O 1 9

• FOR THE NUC REGULATORY COMMISSION es G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

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 3

Insert Page 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 29 29a 30 45 66 67 96 102 108 247c 247e Insert Pages 29 29a 30 45 66 67 96 102 108 247c 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

3.1.1 LIMITING CONDITION FOR OPERATION CONTROL ROD SYSTEM Applicability:

Applies to the operational status of the control rod system.

Objective:

To assure the capability of the control rod system to control core reactivity.

Specification:

a.

Reactivity Limitations (1) Reactivity margin - core loading (a) The Shutdown Margin (SOM) under all operational conditions shall be equal to or greater than:

0.38% i1k/k, with the highest worth control rod analytically determined, or 0.28% i1k/k, with the highest worth control rod determined by test.

AMENDMENT NO. 142, 180, 239 4.1.1 SURVEILLANCE REQUIREMENT CONTROL ROD SYSTEM Applicability:

Applies to the periodic testing requirements for the control rod system.

Objective:

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

Specification:

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

a.

Reactivity Limitations (1) Reactivity margin - core loading The SOM shall be verified within limits:

(a) Prior to each in vessel fuel movement during the fuel loading sequence, and (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 vessel or control rod replacement.

29

LIMITING CONDITION FOR OPERATION (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 SURVEILLANCE REQUIREMENT 29a

LIMITING CONDITION FOR OPERATION 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 Control rods which cannot be moved with control rod drive pressure shall be considered inoperable. Inoperable control rods shall be valved out of service, in such positions that Specification 3.1.1 a( 1 )(a) is met. In no case shall the number of non-fully inserted rods valved out of service be greater than six during power operation. If this specification is not met, the reactor shall be placed in the cold shutdown condition. If a partially or fully withdrawn control rod drive cannot be moved with drive or scram pressure the reactor shall be brought to a shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless investigation demonstrates that the cause of the failure is not due to a failed control rod drive mechanism collet housing.

AMENDMENT NO. 142, 180, 200,222,239 SURVEILLANCE REQUIREMENT (2)

Reactivity margin - stuck control rods Each withdrawn control rod shall be exercised in accordance with the Surveillance Frequency Control Program after the control rod has been withdrawn and power level is greater than the low power set point of the RWM. Insert each withdrawn control rod at least one notch.

This test shall be performed at least once per 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 continuing with two or more inoperable control rods or in the event power operation is continuing with one fully or partially withdrawn rod which cannot be moved and for which control rod drive mechanism damage has not been ruled out. The 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.

30

LIMITING CONDITION FOR OPERATION

c.

The liquid poison tank shall contain a minimum of 1325 gallons of boron bearing solution. The solution shall have a sufficient concentration of sodium pentaborate enriched with Boron-10 isotope to satisfy the equivalency equation.

Where:

d.

e.

Q_ X 628300 X Q

X

_E __ ~ 1 19.8% Atom 13% wt M

86 GPM C =

Sodium Pentaborate Solution Concentration (Wt % )

M =

Mass of Water in Reactor Vessel and Recirculation piping at Hot Rated Conditions (501500 lb)

Q =

Liquid Poison Pump Flow Rate (30 GPM nominal)

E =

Boron-10 Enrichment (Atom%)

The liquid poison solution temperature shall not be less than the temperature presented in Figure 3.1.2.b.

If Specifications "a" through "d" are not met, initiate normal orderly shutdown within one hour.

AMENDMENT NO. 142, 166,222,239 SURVEILLANCE REQUIREMENT Remove the squibs from the valves and verify that no deterioration has occurred by actual field firing of the removed squibs. In addition, field fire one squib from the batch of replacements.

Disassemble and inspect the squib-operated valves to verify that valve deterioration has not occurred.

(2) In accordance with the Surveillance Frequency Control Program -

Demineralized water shall be recycled to the test tank. Pump discharge pressure and minimum flow rate shall be verified.

b.

Boron Solution Checks:

(1) In accordance with the Surveillance Frequency Control Program -

Boron concentration shall be determined.

(2) In accordance with the Surveillance Frequency Control Program -

Solution volume shall be checked. In addition, the 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.

45

LIMITING CONDITION FOR OPERATION 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)

During power operation, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the limiting value specified in the Core Operating Limits Report.

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)

During power operation, the MCPR for all fuel at rated power and flow shall be within the limit provided in the Core Operating Limits Report.

If at any time during power operation it is determined by normal surveillance that the above limit is no longer met, action shall be initiated within 15 minutes to restore operation to within AMENDMENT NO. 142, 143, 1Q3, 222, 239 SURVEILLANCE REQUIREMENT

b.

Linear Heat Generation Rate (LHGR)

The LHGR as a function of core height shall be checked in accordance with the Surveillance Frequency Control Program during reactor operation at ~25% rated thermal power.

c.

Minimum Critical Power Ratio (MCPR)

(1) MCPR shall be determined in accordance with the Surveillance Frequency Control Program during reactor power operation at >25% rated thermal power.

(2) MCPR operating limit shall be determined 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 testing as required in Specification 4.1.1(c).

66

LIMITING CONDITION FOR OPERATION 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 This power/flow relationship shall not exceed the limiting values shown in the Core Operating Limits Report.

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 During power operation, partial loop operation is permitted provided the following conditions are met.

AMENDMENT NO. 142, 143,222,239 SURVEILLANCE REQUIREMENT

d.

Power Flow Relationship Compliance with the power flow relationship in Section 3.1. 7.d shall be determined in accordance with the Surveillance Frequency Control Program during reactor operation.

e.

Partial Loop Operation Under partial loop operation, surveillance requirements 4.1. 7, a, b, c and d above are applicable.

67

3.2.3 LIMITING CONDITION FOR OPERATION COOLANT CHEMISTRY Applicability:

Applies to the reactor coolant system chemical requirements.

Objective:

To assure the chemical purity of the reactor coolant water.

Specification:

a.

The reactor coolant water shall not exceed the 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 temperature ~200 degrees F and reactor thermal power ::,; 10%, or a shutdown shall be initiated 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 and reactor coolant temperature be reduced to

<200 degrees F within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Conductivity Chloride ion Sulfate ion 1 µmho/cm*

100 ppb 100 ppb 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 4.2.3 SURVEILLANCE REQUIREMENT COOLANT CHEMISTRY Applicability:

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

Objective:

To determine the chemical purity of the reactor coolant water.

Specification:

Samples shall be taken and analyzed for conductivity, chloride and sulfate ion content in accordance with the Surveillance Frequency Control Program. In addition, if the conductivity becomes abnormal (other than short term spikes) as indicated by the continuous conductivity monitor, samples shall be taken and analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

When the continuous conductivity monitor is inoperable, a reactor coolant sample shall be taken 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 />.

96

LIMITING CONDITION FOR OPERATION

b.

Any time irradiated fuel is in the reactor vessel and reactor coolant temperature is above 212°F, at least one of the leakage measurement channels associated with each sump ( one for the drywell floor drain and one for the equipment drain) shall be operable.

If the conditions a or b cannot be met, the reactor will be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

AMENDMENT NO. 142, 222, 239 SURVEILLANCE REQUIREMENT

b.

The following surveillance shall be performed on each leakage detection system:

(1) An instrument calibration in accordance with the Surveillance Frequency Control Program.

(2) An instrument functional test in accordance with the Surveillance Frequency Control Program.

102

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

Applies to the operating status of the system of isolation valves on lines connected to the reactor coolant system.

Objective:

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

Specification:

a.

Whenever fuel is in the reactor vessel and the reactor coolant temperature is greater than 212°F, all reactor coolant system isolation valves on lines connected to the reactor coolant system shall be operable except as specified in Specification 3.2.7.b below.

b.

In the event any isolation valve becomes inoperable whenever fuel is in the reactor vessel and the reactor coolant temperature is greater than 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, except as noted in Specification 3.1.1.e.

AMENDMENT N0.142, 145, 173, 181,197,222,227,239 4.2.7 SURVEILLANCE REQUIREMENT REACTOR COOLANT SYSTEM ISOLATION VALVES Applicability:

Applies to the periodic testing requirement for the reactor coolant system isolation valves.

Objective:

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

Specification:

The reactor coolant system isolation valves surveillance shall be performed as indicated below.

a.

In accordance with the Surveillance Frequency Control Program the operable automatically initiated power-operated isolation valves shall be tested for automatic initiation and closure times.

b.

Additional surveillances shall be performed as required by the INSERVICE TESTING PROGRAM.

108

TABLE 3.6.2m RPV WATER INVENTORY CONTROL INSTRUMENTATION Parameter Minimum No.

of Tripped or Operable Trip Systems PRIMARY COOLANT ISOLATION (2)

Low-Low Reactor Water Level (a) Cleanup 2

(b) Shutdown Cooling 2

(3)

Manual 2

AMENDMENT NO.~. 239 Limiting Condition for Operation Minimum No. of Operable Instrument Channels per Operable Trip System 2(c) 2(c) 1 Set Point

~ 5 inches (Indicator Scale)

~ 5 inches (Indicator Scale)

Reactor Mode Switch Position in Which Function Must Be Operable C:

~

C.

0

"'i "tJ j

j t::

j ns C:

J:

Cl) -

j u,

0:::

u, 0:::

(a)

(a)

(a)

(a)

(a)

(a) 247c

Parameter PRIMARY COOLANT ISOLATION (Cleanup and Shutdown Cooling)

(2)

(3)

Low-Low Reactor Water Level Manual AMENDMENT NO.~. 239 TABLE 4.6.2m RPV WATER INVENTORY CONTROL INSTRUMENTATION Sensor Check Note 1 Surveillance Requirement Instrument Channel Test Note 1 Note 1 Instrument Channel Calibration 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.

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 A ccess1on N ML193018005 o.:

OFFICE DORL/LPL 1/PM DORL/LPL 1/LA NAME MMarshall CSmith DATE 11/06/2019 11/04/2019 1y e-ma1

• b

• 1 OGC-NLO*

DORL/LPL 1/BC RAuqustus JDanna 11/21/2019 11/25/2019 OFFICIAL RECORD COPY DORL/LPL 1/PM MMarshall 11/25/2019