ML24086A476

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Application for Technical Specification Change to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line-Item Improvement Process
ML24086A476
Person / Time
Site: Millstone Dominion icon.png
Issue date: 03/22/2024
From: James Holloway
Dominion Energy Nuclear Connecticut
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
24-002
Download: ML24086A476 (1)


Text

Dominion Energy Nuclear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com March 22, 2024 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 Serial No.

NRA/SS:

Docket No.

License No.24-002 RO 50-423 NFP-49 APPLICATION FOR TECHNICAL SPECIFICATION CHANGE TO EXTEND THE INSPECTION INTERVAL FOR REACTOR COOLANT PUMP FLYWHEELS USING THE CONSOLIDATED LINE-ITEM IMPROVEMENT PROCESS Pursuant to 10 CFR 50.90, Dominion Energy Nuclear Connecticut, Inc. (DENC) is submitting a license amendment request (LAR) to the Nuclear Regulatory Commission (NRC) to revise the Technical Specific ations (TS) for Millstone Power Station Unit 3 (MPS3).

The proposed amendment will extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years. The changes are consistent with Industry/Technical Specification Task Force (TSTF) Stan dard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)." The availability of this TS improvement was announced in the Federal Register on October 22, 2003, as part of the consolidated line-item improvement process (CLIIP). to this letter describes the proposed changes and the requested confirmation of applicability. Attachment 2 provides marked-up MPS3 TS pages showing the proposed changes.

The proposed amendment has been reviewed and approved by the station's Facility Safety Review Committee.

DENC requests approval of this LAR by March 22, 2025, with a 60-day impl ementation period.

In accordance with 10 CFR 50.91 (b), a copy of this LAR is being provided to the State of Connecticut.

Serial No.24-002 Docket No. 50-423 Page 2 of 3 If you have any questions or require additional information, please contact Mr. Shayan Sinha at (804) 273-4687.

Sincere

/

Jal Holloway Vice President -Nuclear Engineering and Fleet Support COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by James Holloway, who is Vice President -Nuclear Engineering-and Fleet Support of Dominion Energy Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document on behalf of that company, and that the statements in the dqcument are true to the best of his knowledge and belief.

Acknowledged before me this 22 day of r('(;lv--c\\r)

My Commission Expires: q \\'3of 2-0 2 "1-

,JULIE H HOUGH NOTARY PUBLIC 8066994 COMMONWE/-\\LTH OF VIRGINIA MY COMMISSION EXPIRES 09-30.2027 Attachments: 2024.

1.Description and Assessment of Proposed Change 2.Marked-up Technical Specification Pages Commitments made in this letter: None Notary Pu ic cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Rd., Suite102 King of Prussia, PA 19406-1415 Richard V. Guzman Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 9 E3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environ mental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No.24-002 Docket No. 50-423 Page 3 of 3 Serial No.24-002 Docket Nos. 50-423

Attachment 1

DESCRIPTION AND ASSESSMENT OF PROPOSED CHANGE

Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 Serial No.24-002 Docket No. 50-423 Attachment 1, Page 1 of 3

1.0

SUMMARY

DESCRIPTION

Pursuant to 10 CFR 50.90, Dominion Energy Nuclear Connecticut, Inc. (DENC) is submitting a license amendment request (LAR) to the Nuclear Regulatory Commission (NRC) to revise the Technical Specifications (TS) for Millstone Power Station Unit 3 (MPS3). The proposed LAR changes TS 6.17, Reactor Coolant Pump Flywheel Inspection Program. The revisions are consistent with Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, Revision to RCP Flywheel Inspection Program (WCAP-15666). The availability of this TS improvement was announced in the Federal Register on October 23, 2003, as part of the consolidated line-item improvement process (CLIIP).

2.0 DESCRIPTION

OF PROPOSED AMENDMENT

Consistent with the NRC-approved TSTF-421, the proposed TS change includes the following revision to TS 6.17:

The examination interval for the RCP flywheels is changed from at least once every 10-years coinciding with the Inservice Inspection schedule as required by ASME Section XI, to at least once every 20 years.

3.0 BACKGROUND

The background for this application is adequately addressed by the NRC Notice of Availability published on October 22, 2003, (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421, WCAP-15666, Extension of Reactor Coolant Pump Motor Flywheel Examination, and the related NRC safety evaluation (SE) dated May 5, 2003.

4.0 REGULATORY REQUIREMENTS AND GUIDANCE

The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590),

TSTF-421, WCAP-15666, and the related NRC SE.

Serial No.24-002 Docket No. 50-423 Attachment 1, Page 2 of 3

5.0 TECHNICAL ANALYSIS

DENC has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLIIP. This verification included a review of the NRC staffs model SE, as well as the information provided to support TSTF-421 (including WCAP-15666 and the related SE dated May 5, 2003). DENC has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC staff are applicable to MPS3 and justify this amendment for incorporation into the MPS3 TS.

6.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC notices related to the CLIIP, TSTF-421, topical report WCAP-15666, and the associated SE.

7.0 NO SIGNIFICANT HAZARDS CONSIDERATION

DENC has reviewed the proposed no significant hazards consideration determination published on June 24, 2003 (68 FR 37590) as part of the CLIIP. DENC has concluded that the proposed determination presented in the notice is applicable to MPS3 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).

8.0 ENVIRONMENTAL EVALUATION

DENC has reviewed the environmental evaluation included in the model safety evaluation dated June 24, 2003 (68 FR 37590) as part of the CLIIP. DENC has concluded that the NRC staff's findings presented in that evaluation are applicable to MPS3 and the evaluation is hereby incorporated by reference for this application.

9.0 PRECEDENT

This application is being made in accordance with the CLIIP. DENC is not proposing any substantive variations or deviations from the TS changes described in TSTF-421 or the NRC staffs model SE published on June 24, 2003 (68 FR 37590). Note that MPS3 has not converted to STS; therefore, there are some administrative differences in TS numbering. The NRC approved an Amendment for DC Cook on January 31, 2020 (ADAMS Accession No: ML193478376), which followed a similar approach of only revising the TS section to reflect the new examination interval.

Serial No.24-002 Docket No. 50-423 Attachment 1, Page 3 of 3

10.0 REFERENCES

1. Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line-Item Improvement Process, published October 22, 2003, (68 FR 60422).
2. Federal Register Notice: Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line-Item Improvement Process, published June 24, 2003 (68 FR 37590).
3. Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, Revision to RCP Flywheel Inspection Program (WCAP-15666), Revision 0, November 2001.
4. WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination,"

July 2001.

5. NRC letter dated May 5, 2003, from H. Berkow to R. Bryan (WOG) transmitting Safety Evaluation of WCAP-15666

Serial No.24-002 Docket No. 50-423

Attachment 2

MARKED-UP TECHNICAL SPECIFICATIONS PAGES

Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 Serial No.24-002 Docket No. 50-423 Attachment 2, Page 1 of 1

1eimch 16, 2006 ADMINISTRATIVE CONTROLS

J-Limitations on the annual dose or dose commitment to any member of beyond the SITE BOUNDARY, due to releases of radioactivity and to radiation Y the public,

from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of Specification 4.0.2 and Specification 4.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

6.16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide ( 1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the REMODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

a. Monitoring, sampling, analysis, and reporting ofradiation and radionuclides in the environment in accordance with the methodology and param eters in the REMODCM.
b. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made ifrequired by the results of this census, and
c. Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive mat erials

in environmental sample matrices are perfonned as part of the quality assurance program for environmental monitoring.

6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM

This program shall provide for the inspection of each reactor coolant pump flywheel by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywhee ls at least once every ~

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6.18 TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM

This program provides a means for processing changes to the Bases of these Technical Specifications:

a. Changes to the Bases of the TS shall be made under appropriat e administrative controls and r eviews.
b. Licensees may make changes to Bases without prior N RC approval provided the changes do not require either of the following:
1. A change in the TS incorporated in the license or
2. A chang e to updated FSAR or Bas es that r equires NRC approval pursuant to 10 CFR 50.59.

MILLSTONE - UNIT 3 6-26 Amendment No. -l--88, W4, i-H, ~,

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