Text

Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
	ML24211A122
Person / Time
Site:	FitzPatrick
Issue date:	07/29/2024
From:	David Gudger; Constellation Energy Generation
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	JAFP-24-0036
	Download: ML24211A122 (1)
	v • d • e

Constellation Energy Generation, LLC 200 Exelon Way Kennett Square, PA 19348 10 CFR 50.90 JAFP-24-0036 July 29, 2024 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333

Subject:

Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis

References:

1. Letter from D. Gudger (Constellation Energy Generation, LLC) to U.S.

Nuclear Regulatory Commission, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis, JAFP-23-0040, dated August 3, 2023 (Accession Number ML23215A012)

2. Letter from D. Gudger (Constellation Energy Generation, LLC) to U.S.

Nuclear Regulatory Commission, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis, JAFP-23-0048, dated August 31, 2023 (Accession Number ML23243A946)

3. Letter from D. Gudger (Constellation Energy Generation, LLC) to U.S.

Nuclear Regulatory Commission, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis, JAFP-24-0009, dated February 28, 2024 (Accession Number ML24059A130)

4. Letter from D. Gudger (Constellation Energy Generation, LLC) to U.S.

Nuclear Regulatory Commission, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis, JAFP-24-0014, dated March 25, 2024 (Accession Number ML24085A234)

License Amendment Request Fuel Handling Accident Docket No. 50-333 July 29, 2024 Page 2 By letter dated August 3, 2023, Constellation Energy Generation, LLC (CEG) requested a change to the James A. FitzPatrick Technical Specifications (TS) Bases in accordance with the provisions of Title 10 of the Code of Federal Regulations with the provisions of 10 CFR 50.90. The proposed amendment changes to the Technical Specification (TS) Bases to change the Fuel Handling Accident Analysis (FHA) due to new Refuel Bridge Mast NF400 to NF500 and definition for Recently Irradiated Fuel Assemblies at James A. FitzPatrick Nuclear Power Plant (JAF). The impact of the proposed amendment would increase the consequences of the FHA analysis as well as reduce future refueling outage burden.

Through email conversations with J. Kim, NRC Project Manager and CEG, between July 22, 2024, and July 26, 2024, the NRC identified and communicated a concern regarding changes to the term Recently Irradiated Fuel Assemblies in the referenced License Amendment Request.

The NRC Office of General Counsel (OGC) concern is that the term Recently Irradiated Fuel Assemblies is consistently used throughout the TS but is not defined in the TS. The value of 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months is stated in all applicable TS bases. The term recently was added to the TS and TS Bases from a 2002 TS amendment (ML022350228). With that amendment, the value of 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months was only added to the TS bases. That amendment established 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months for all TSs as the time period beyond which fuel is no longer considered recently irradiated.

References 1 thru 4 established different values for when fuel would be considered recently irradiated however the changes were only documented in the TS Bases which raised a concern that the different TSs would use the same term, recently irradiated but the applicable time, per the TS Bases, would be different.

In response to NRC OGCs concern on Recently Irradiated Fuel Assemblies, CEG is supplementing Reference 1 to revise the applicable TSs to be consistent with the changes made to the associated TS bases. The specific changes are provided in Attachment 1 to this supplement.

JAF is entering a Refueling Outage on September 5, 2024, and is scheduled to commence moving fuel on September 7, 2024. Approval of this request is necessary to support fuel moves during this outage. Accordingly, CEG is requesting the proposed change be reviewed under exigent circumstances in accordance with 10 CFR 50.91(a)(6), and requests that the NRC expedite the review of the requested change to support approval by September 5, 2024.

This amendment request contains no new regulatory commitments.

The proposed changes have been reviewed by the JAF Plant Operations Review Committee in accordance with the requirements of the Constellation Quality Assurance Program.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), CEG is transmitting a copy of this application and its attachments to the designated State Officials.

License Amendment Request Fuel Handling Accident Docket No. 50-333 July 29, 2024 Page 3 Should you have any questions concerning this supplement, please contact Dave Gudger David.Gudger@constellation.com.

Approval of the supplement requested by September 5, 2024.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of July 2024.

Respectfully, David T. Gudger Senior Manager - Licensing & Regulatory Affairs Constellation Energy Generation, LLC Attachments:

1. Proposed Technical Specification Changes (Mark-up Pages)

2. Proposed Technical Specification Changes (Clean Pages) cc:

USNRC Region I, Regional Administrator w/attachment USNRC Senior Resident Inspector, JAF w/attachment USNRC Project Manager, JAF w/attachment A. L. Peterson, NYSERDA w/attachment

ATTACHMENT 1 License Amendment Request James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP PAGES)

Facility Operating License (FOL) Page 3

TS Pages 3.3.6.2-4 3.3.7.1-1 3.6.4.1-1 3.6.4.2-1 3.6.4.3-1 3.7.3-1 3.7.4-1 3.8.2-1 3.8.5-1 3.8.8-1 Amendment Renewed License No. DPR-59 (3)

Constellation Energy Generation, LLC, 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)

Constellation Energy Generation, LLC, 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 without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.

(5)

Constellation Energy Generation, LLC, 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, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and 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 subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 355, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

Secondary Containment Isolation Instrumentation 3.3.6.2 JAFNPP 3.3.6.2-4 Amendment Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1.

Reactor Vessel Water Level - Low (Level 3) 1, 2, 3 2

SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6 177 inches

2.

Drywell Pressure - High 1, 2, 3 2

SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6 2.7 psig

3.

Reactor Building Exhaust Radiation - High 1, 2, 3, (a) 1 SR 3.3.6.2.1 SR 3.3.6.2.3 SR 3.3.6.2.6 24,800 cpm

4.

Refueling Floor Exhaust Radiation - High 1, 2, 3, (a) 1 SR 3.3.6.2.1 SR 3.3.6.2.3 SR 3.3.6.2.6 24,800 cpm (a) During movement of recently irradiated fuel assemblies in secondary containment. Recently irradiated is defined for Technical Specification 3.3.6.2 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

CREVAS System Instrumentation 3.3.7.1 JAFNPP 3.3.7.1-1 Amendment 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS) System Instrumentation LCO 3.3.7.1 The Control Room Air Inlet Radiation - High channel shall be OPERABLE.

APPLICABILITY:

MODES 1, 2 and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.3.7.1 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Channel inoperable.

A.1 Place the CREVAS System in the isolate mode of operation.

OR A.2 Declare both CREVAS subsystems inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour

Secondary Containment 3.6.4.1 JAFNPP 3.6.4.1-1 Amendment 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.6.4.1 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Secondary containment inoperable in MODE 1, 2, or 3.

A.1 Restore secondary containment to OPERABLE status.

4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s*

B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours C.

Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment.

C.1

- - - - - - - - - NOTE- - - - - - - - -

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the secondary containment.

Immediately

The Completion Time is extended to 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , in support of the A RHR pump repairs, contingent on implementation of Compensatory Actions stated in Section 3.4 of letter JAFP-21-0053, dated June 14, 2021, as a one-time only change ending upon restoration of the A RHR pump to OPERABLE, or on July 11, 2021 at 20:00 hours. Multiple entries may be necessary to implement compensatory actions, or to address unforeseen circumstances related to the A RHR pump motor replacement.

SCIVs 3.6.4.2 JAFNPP 3.6.4.2-1 Amendment 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.6.4.2 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by inoperable SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more penetration flow paths with one SCIV inoperable.

A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (continued)

SGT System 3.6.4.3 JAFNPP 3.6.4.3-1 Amendment 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.6.4.3 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SGT subsystem inoperable.

A.1 Restore SGT subsystem to OPERABLE status.

7 days B.

Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or

3.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours C.

Required Action and associated Completion Time of Condition A not met in during movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - -

LCO 3.0.3 is not applicable.

C.1 Place OPERABLE SGT subsystem in operation.

OR Immediately (continued)

CREVAS System 3.7.3 JAFNPP 3.7.3-1 Amendment 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS) System LCO 3.7.3 Two CREVAS subsystems shall be OPERABLE.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.7.3 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One CREVAS subsystem inoperable for reasons other than Condition B.

A.1 Restore CREVAS subsystem to OPERABLE status.

7 days B.

One or more CREVAS subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.

B.1 Initiate action to implement mitigating actions.

AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to OPERABLE status.

Immediately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 90 days (continued)

Control Room AC System 3.7.4 JAFNPP 3.7.4-1 Amendment 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.7.4 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One control room AC subsystem inoperable.

A.1 Restore control room AC subsystem to OPERABLE status.

30 days B.

Two control room AC subsystems inoperable.

B.1 Verify control room area temperature < 90°F.

AND B.2 Restore one control room AC subsystem to OPERABLE status.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 72 hours C.

Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours (continued)

AC Sources - Shutdown 3.8.2 JAFNPP 3.8.2-1 Amendment 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, Distribution Systems-Shutdown;

b.

One qualified circuit, which maybe the same circuit required by LCO 3.8.2.a, between the offsite transmission network and the other division of the plant Class 1E AC electrical power distribution subsystem(s), when a second division is required by LCO 3.8.8; and

c.

One emergency diesel generator (EDG) subsystem capable of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.8.2 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

DC Sources - Shutdown 3.8.5 JAFNPP 3.8.5-1 Amendment 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 One 125 VDC electrical power subsystem shall be OPERABLE to support one division of the plant Class IE DC Electrical Power Distribution System required by LCO 3.8.8, Distribution Systems - Shutdown.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.8.5 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable.

A.1 Declare affected required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND Immediately Immediately Immediately (continued)

Distribution Systems - Shutdown 3.8.8 JAFNPP 3.8.8-1 Amendment 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and 125 VDC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.8.8 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC or 125 VDC electrical power distribution subsystems inoperable.

A.1 Declare associated supported required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND Immediately Immediately Immediately (continued)

ATTACHMENT 2 License Amendment Request James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 PROPOSED TECHNICAL SPECIFICATION CHANGES (CLEAN PAGES)

Facility Operating License (FOL) Page 3

TS Pages 3.3.6.2-4 3.3.7.1-1 3.6.4.1-1 3.6.4.2-1 3.6.4.3-1 3.7.3-1 3.7.4-1 3.8.2-1 3.8.5-1 3.8.8-1 Amendment Renewed License No. DPR-59 (3)

Constellation Energy Generation, LLC, 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)

Constellation Energy Generation, LLC, 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 without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.

(5)

Constellation Energy Generation, LLC, 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, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and 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 subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No., are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

Secondary Containment Isolation Instrumentation 3.3.6.2 JAFNPP 3.3.6.2-4 Amendment Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1.

Reactor Vessel Water Level - Low (Level 3) 1, 2, 3 2

SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6 177 inches

2.

Drywell Pressure - High 1, 2, 3 2

SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6 2.7 psig

3.

Reactor Building Exhaust Radiation - High 1, 2, 3, (a) 1 SR 3.3.6.2.1 SR 3.3.6.2.3 SR 3.3.6.2.6 24,800 cpm

4.

Refueling Floor Exhaust Radiation - High 1, 2, 3, (a) 1 SR 3.3.6.2.1 SR 3.3.6.2.3 SR 3.3.6.2.6 24,800 cpm (a) During movement of recently irradiated fuel assemblies in secondary containment. Recently irradiated is defined for Technical Specification 3.3.6.2 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

CREVAS System Instrumentation 3.3.7.1 JAFNPP 3.3.7.1-1 Amendment 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS) System Instrumentation LCO 3.3.7.1 The Control Room Air Inlet Radiation - High channel shall be OPERABLE.

APPLICABILITY:

MODES 1, 2 and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.3.7.1 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Channel inoperable.

A.1 Place the CREVAS System in the isolate mode of operation.

OR A.2 Declare both CREVAS subsystems inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour

Secondary Containment 3.6.4.1 JAFNPP 3.6.4.1-1 Amendment 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.6.4.1 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Secondary containment inoperable in MODE 1, 2, or 3.

A.1 Restore secondary containment to OPERABLE status.

4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s*

B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours C.

Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment.

C.1

- - - - - - - - - NOTE- - - - - - - - -

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the secondary containment.

Immediately

The Completion Time is extended to 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , in support of the A RHR pump repairs, contingent on implementation of Compensatory Actions stated in Section 3.4 of letter JAFP-21-0053, dated June 14, 2021, as a one-time only change ending upon restoration of the A RHR pump to OPERABLE, or on July 11, 2021 at 20:00 hours. Multiple entries may be necessary to implement compensatory actions, or to address unforeseen circumstances related to the A RHR pump motor replacement.

SCIVs 3.6.4.2 JAFNPP 3.6.4.2-1 Amendment 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.6.4.2 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by inoperable SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more penetration flow paths with one SCIV inoperable.

A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (continued)

SGT System 3.6.4.3 JAFNPP 3.6.4.3-1 Amendment 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.6.4.3 as fuel assemblies which have occupied part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SGT subsystem inoperable.

A.1 Restore SGT subsystem to OPERABLE status.

7 days B.

Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or

3.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours C.

Required Action and associated Completion Time of Condition A not met in during movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - -

LCO 3.0.3 is not applicable.

C.1 Place OPERABLE SGT subsystem in operation.

OR Immediately (continued)

CREVAS System 3.7.3 JAFNPP 3.7.3-1 Amendment 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS) System LCO 3.7.3 Two CREVAS subsystems shall be OPERABLE.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.7.3 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One CREVAS subsystem inoperable for reasons other than Condition B.

A.1 Restore CREVAS subsystem to OPERABLE status.

7 days B.

One or more CREVAS subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.

B.1 Initiate action to implement mitigating actions.

AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to OPERABLE status.

Immediately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 90 days (continued)

Control Room AC System 3.7.4 JAFNPP 3.7.4-1 Amendment 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.7.4 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One control room AC subsystem inoperable.

A.1 Restore control room AC subsystem to OPERABLE status.

30 days B.

Two control room AC subsystems inoperable.

B.1 Verify control room area temperature < 90°F.

AND B.2 Restore one control room AC subsystem to OPERABLE status.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 72 hours C.

Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours (continued)

AC Sources - Shutdown 3.8.2 JAFNPP 3.8.2-1 Amendment 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, Distribution Systems-Shutdown;

b.

One qualified circuit, which maybe the same circuit required by LCO 3.8.2.a, between the offsite transmission network and the other division of the plant Class 1E AC electrical power distribution subsystem(s), when a second division is required by LCO 3.8.8; and

c.

One emergency diesel generator (EDG) subsystem capable of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.8.2 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

DC Sources - Shutdown 3.8.5 JAFNPP 3.8.5-1 Amendment 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 One 125 VDC electrical power subsystem shall be OPERABLE to support one division of the plant Class IE DC Electrical Power Distribution System required by LCO 3.8.8, Distribution Systems - Shutdown.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.8.5 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable.

A.1 Declare affected required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND Immediately Immediately Immediately (continued)

Distribution Systems - Shutdown 3.8.8 JAFNPP 3.8.8-1 Amendment 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and 125 VDC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Recently irradiated is defined for Technical Specification 3.8.8 as fuel assemblies which have occupied part of a critical reactor core within the previous 104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months .

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC or 125 VDC electrical power distribution subsystems inoperable.

A.1 Declare associated supported required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND Immediately Immediately Immediately (continued)

v t e Letter Sequence Supplement
EPID:L-2023-LLA-0109, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis (Approved, Closed)
Initiation Request, Request Acceptance Supplement Administration Questions 1 February 2024 28 February 2024 15 April 2024 Answers 28 February 2024 25 March 2024 Results Approval Other: ML24208A049
MONTHYEAR2024-03-25 [Table View]

JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis

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JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis

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