L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements

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Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
ML24270A102
Person / Time
Site: Monticello 
Issue date: 09/26/2024
From: Hafen S
Northern States Power Company, Minnesota, Xcel Energy
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
L-MT-24-025
Download: ML24270A102 (1)
v • d • e


Text

2807 West County Road 75 Monticello, MN 55362 L-MT-24-025 10 CFR 50.90 September , 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Application to Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements" Pursuant to 10 CFR 50.90, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), is submitting a request for an amendment to the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP).

NSPM requests adoption of TSTF-554, "Revise Reactor Coolant Leakage Requirements,"

which is an approved change to the Standard Technical Specifications (STS), into the MNGP TS. The proposed amendment revises the TS definition of "Leakage," clarifies the requirements when pressure boundary leakage is detected and adds a Required Action when pressure boundary leakage is identified. This change is requested as part of the Consolidated Line Item Improvement Process (CLIIP).

The enclosure provides a description and assessment of the proposed changes. Attachment 1 provides the existing TS pages marked up to show the proposed changes. Attachment 2 provides revised (clean) TS pages. Attachment 3 provides existing TS Bases pages marked to show the proposed changes for information only.

Approval of the proposed amendment is requested within six months of completion of the NRC's acceptance review. Once approved, the amendment shall be implemented within 120 days.

In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Minnesota State Official.

This letter makes no new commitments and no revisions to existing commitments.

If you should have any questions regarding this submittal, please contact Ron Jacobson at (612) 330-6542 or ronald.g.jacobson@xcelenergy.com.

fl Xcel Energy

Document Control Desk L-MT-24-025 Page2 I declare under penalty of perjury, that the foregoing is true and correct.

Executed on September l.k, 2024, ShaL Site Vice

  • resident, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:

Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC State of Minnesota

ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT EVALUATION OF PROPOSED CHANGE License Amendment Request Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements"

1.0 DESCRIPTION

..................................................................................................... 2

2.0 ASSESSMENT

..................................................................................................... 2 2.1 Applicability of Safety Evaluation............................................................... 2 2.2 Variations................................................................................................... 2

3.0 REGULATORY ANALYSIS

.................................................................................. 4 3.1 No Significant Hazards Consideration Analysis......................................... 4 3.2 Conclusion................................................................................................. 5

4.0 ENVIRONMENTAL CONSIDERATION

................................................................ 6 ATTACHMENTS:

1. Technical Specification Pages (Marked Up)
2. Technical Specification Pages (Retyped)
3. Technical Specification Bases Pages (Marked Up, For Information Only)

L-MT-24-025 NSPM Enclosure Page 2 of 5 License Amendment Request Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements"

1.0 DESCRIPTION

In accordance with the provisions of 10 CFR 50.90, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby requests adoption of TSTF-554, Revision 1, "Revise Reactor Coolant Leakage Requirements," which is an approved change to the Standard Technical Specifications (STS), into the Monticello Nuclear Generating Plant (MNGP) Technical Specifications (TS). The proposed amendment revises the TS definition of "Leakage" and the Reactor Coolant System (RCS) Operational Leakage TS to clarify the requirements.

2.0 ASSESSMENT

2.1 Applicability of Safety Evaluation NSPM has reviewed the safety evaluation for TSTF-554, Revision 1 provided to the Technical Specifications Task Force (TSTF) in a letter dated December 18, 2020 (ADAMS Accession Nos. ML20168A361 and ML20322A024). This review included a review of the NRC staff's evaluation, as well as the information provided in TSTF-554, Revision

1. As described herein, NSPM has concluded that the justifications presented in TSTF-554, Revision 1 and the safety evaluation prepared by the NRC staff are applicable to the MNGP and justify this amendment for the incorporation of the changes into the MNGP TS.

2.2 Variations NSPM is proposing the following editorial variations from the TS changes described in TSTF-554, Revision 1:

x MNGP TS 1.1 Definition for Identified LEAKAGE, Item a.1., already ends with a

or so the markups in this license amendment request differ editorially from TSTF-554 which shows the punctuation changing from a, to a ;.

x MNGP TS 1.1 Definition for Identified LEAKAGE, Item a.2., already ends with a

so the markups in this license amendment request differ editorially from TSTF-554 which shows the punctuation changing from a, to a ;.

x MNGP TS 1.1 Definition for Unidentified LEAKAGE, Item b., ends with a ; so the markups in this license amendment request differ editorially from TSTF-554

L-MT-24-025 NSPM Enclosure Page 3 of 5 by not deleting a comma and retaining the existing semi-colon for consistency with a. and c.

x MNGP TS 1.1 Definition for Identified LEAKAGE, Item c., already ends with a

so the markups in this license amendment request differ editorially from TSTF-554 which shows the punctuation changing from a, to a ;.

TSTF-554, Revision 1 and its corresponding Safety Evaluation discuss the applicable regulatory requirements and guidance, including the applicability of 10 CFR 50, Appendix A, General Design Criteria (GDC) 14 and 30. MNGP was not licensed to the 10 CFR 50, Appendix A, GDC. MNGP was licensed to the applicable Atomic Energy Commission (AEC) preliminary general design criteria, published July 11, 1967. The applicable AEC proposed criteria are addressed as documented in the MNGP Updated Safety Analysis Report (USAR), Appendix E, "Plant Comparative Evaluation with the Proposed AEC 70 Design Criteria". Following implementation of the proposed change, MNGP will remain in compliance with the applicable AEC design criteria as described in the MNGP USAR. Therefore, this difference does not alter the conclusion that the proposed change is applicable to MNGP.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Analysis NSPM requests adoption of TSTF-554, "Revise Reactor Coolant Leakage Requirements," Revision 1 that is an approved change to the Standard Technical Specifications (STS) into the MNGP Technical Specifications (TS). The proposed amendment revises the TS definition of "Leakage," clarifies the requirements when pressure boundary leakage is detected, and adds a Required Action when pressure boundary leakage is identified.

NSPM has evaluated whether a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed amendment revises the TS definition of "Leakage," clarifies the requirements when pressure boundary leakage is detected, and adds a Required Action when pressure boundary leakage is identified.

The proposed change revises the definition of pressure boundary leakage. Pressure boundary leakage is a precursor to some accidents previously evaluated. The proposed

L-MT-24-025 NSPM Enclosure Page 4 of 5 change expands the definition of pressure boundary leakage by eliminating the qualification that pressure boundary leakage must be from a "nonisolable" flaw. A new TS Action is created which requires isolation of the pressure boundary flaw from the Reactor Coolant System. This new action provides assurance that the flaw will not result in any accident previously evaluated.

Pressure boundary leakage and the actions taken when pressure boundary leakage is detected are not assumed in the mitigation of any accident previously evaluated. As a result, the consequences of any accident previously evaluated are unaffected.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed amendment revises the TS definition of "Leakage," clarifies the requirements when pressure boundary leakage is detected and adds a Required Action when pressure boundary leakage is identified. The proposed change does not alter the design function or operation of the RCS. The proposed change does not alter the ability of the RCS to perform its design function. Since pressure boundary leakage is an evaluated accident, the proposed change does not create any new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No The proposed amendment revises the TS definition of "Leakage," clarifies the requirements when pressure boundary leakage is detected and adds a Required Action when pressure boundary leakage is identified. The proposed change does not affect the initial assumptions, margins, or controlling values used in any accident analysis. The amount of leakage allowed from the RCS is not increased. The proposed change does not affect any design basis or safety limit or any Limiting Condition for Operation.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, NSPM concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

L-MT-24-025 NSPM Enclosure Page 5 of 5 3.2 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4.0 ENVIRONMENTAL EVALUATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

ENCLOSURE ATTACHMENT 1 MONTICELLO NUCLEAR GENERATING PLANT, UNIT 1 License Amendment Request Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements" TECHNICAL SPECIFICATIONS PAGES (MARKUP)

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ENCLOSURE 1, ATTACHMENT 2 MONTICELLO NUCLEAR GENERATING PLANT, UNIT 1 License Amendment Request Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements" TECHNICAL SPECIFICATIONS PAGES (RE-TYPED)

(3 Pages Follow)

Definitions 1.1 Monticello 1.1-4 Amendment No. TBD 1.1 Definitions LEAKAGE LEAKAGE shall be:

a.

Identified LEAKAGE 1.

LEAKAGE into the drywell, such as that from pump seals or valve packing that is captured and conducted to a sump or collecting tank; or 2.

LEAKAGE into the drywell atmosphere from sources that are both specifically located and known to not interfere with the operation of leakage detection systems;

b.

Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c.

Total LEAKAGE Sum of the identified and unidentified LEAKAGE; and d.

Pressure Boundary LEAKAGE LEAKAGE through a fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LEAKAGE past seals, packing, and gaskets is not pressure boundary leakage.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per unit length of RATE (LHGR) fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all FUNCTIONAL TEST logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio (CPR) that RATIO (MCPR) exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

RCS Operational LEAKAGE 3.4.4 Monticello 3.4.4-1 Amendment No. TBD 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to:

a.

No pressure boundary LEAKAGE;

b.

d 5 gpm unidentified LEAKAGE;

c.

d 25 gpm total LEAKAGE averaged over the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period; and

d.

d 2 gpm increase in unidentified LEAKAGE within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period in MODE 1.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressure boundary LEAKAGE exists.

A.1 Isolate affected component, pipe, or vessel from the RCS by use of a closed manual valve, closed and de-activated automatic valve, blind flange, or check valve.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Unidentified LEAKAGE not within limit.

OR Total LEAKAGE not within limit.

B.1 Reduce LEAKAGE to within limits.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

RCS Operational LEAKAGE 3.4.4 Monticello 3.4.4-2 Amendment No. TBD ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Unidentified LEAKAGE increase not within limit.

C.1 Reduce LEAKAGE to within limits.

OR C.2 Verify source of unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours D. Required Action and associated Completion Time not met.

D.1 Be in MODE 3.

AND D.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE and unidentified LEAKAGE increases are within limits.

In accordance with the Surveillance Frequency Control Program

ENCLOSURE 1, ATTACHMENT 3 MONTICELLO NUCLEAR GENERATING PLANT, UNIT 1 License Amendment Request Revise Technical Specifications to Adopt TSTF-554, "Revise Reactor Coolant Leakage Requirements" TECHNICAL SPECIFICATIONS BASES PAGES (MARKUP)

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IfpressureboundaryLEAKAGEexists,theaffectedcomponent,pipe,orvesselmustbeisolatedfromthe

RCSbyaclosedmanualvalve,closedanddeactivatedautomaticvalve,blindflange,orcheckvalve

within4hours.Whileinthiscondition,structuralintegrityofthesystemshouldbeconsideredbecause

thestructuralintegrityofthepartofthesystemwithintheisolationboundarymustbemaintained

underalllicensingbasisconditions,includingconsiderationofthepotentialforfurtherdegradationof

theisolatedlocation.NormalLEAKAGEpasttheisolationdeviceisacceptableasitwilllimitRCS

LEAKAGEandisincludedinidentifiedorunidentifiedLEAKAGE.Thisactionisnecessarytoprevent

furtherdeteriorationoftheRCPB.

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