AEP-NRC-2019-33, Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-421

Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-421

ML19241A242
Person / Time
Site:	Cook
Issue date:	08/27/2019
From:	Lies Q American Electric Power, Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2019-33
Download: ML19241A242 (10)

Text

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.m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER One Cook Place Bridgman, Ml 49106 .

A unit ofAmerican Electric Power Indiana Michigan Power.com August 27, 2019 AEP-NRC-2019-33 10 CFR 50.90 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant, Units 1 and 2 APPLICATION TO REVISE TECHNICAL SPECIFICATION 5.5.5, "REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM," IN ACCORDANCE WITH TSTF-421.

Pursuant to 10 CFR 50.90, Indiana Michigan Power Company (l&M), the licensee for Donald C. Cook Nuclear Plant (CNP), hereby requests an amendment to the Technical Specifications (TS) for CNP Units 1 and 2.

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 lndustry!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 22, 2003, as part of the consolidated line item improvement process.

Enclosure 1 provides an affirmation statement pertaining to the information contained herein.

Enclosure 2 provides a description and the requested confirmation of applicability. Enclosures 3 and 4 provide Unit 1 and Unit 2 TS pages, respectively, marked to show the proposed changes. New clean Unit 1 and Unit 2 TS pages with proposed changes incorporated will be provided to the Nuclear Regulatory Commission (NRC) Licensing Project Manager when requested.

l&M requests NRC review and approval of the proposed changes commensurate with the NRC's normal review schedule. Once approved, the amendment shall be *implemented within 60 days.

In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated Michigan state officials.

,Ii l

U. S. Nuclear Regulatory Commission AEP-NRC-2019-33 Page 2 There are no new regulatory commitments made in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.

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Sincerely, Q. Shane Lies Site Vice President Indiana Michigan Power Company JMT/mll

Enclosures:

1. Affirmation

2. Description and Assessment of the Technical Specification Changes

3. Donald C. Cook Nuclear Plant Unit 1 Technical Specification Pages Marked To Show Proposed Changes

4. Donald C. Cook Nuclear Plant Unit 2 Technical Specification Pages Marked To Show Proposed Changes c: R. J. Ancona - MPSC R. F. Kuntz- NRG, Washington, D.C.

EGLE - RMD/RPS NRG Resident Inspector D. J. Roberts - NRG Region Ill A. J. Williamson -AEP Ft. Wayne, w/o enclosures

Enclosure 1 to AEP-NRC-2019-33 AFFIRMATION I, Q. Shane Lies, being duly sworn, state that I am the Site Vice President of Indiana Michigan Power Company (l&M), that I am authorized to sign and file this request with the U. S. Nuclear Regulatory Commission on behalf of l&M, and that the statements made and the matters set forth herein pertaining to l&M are true and correct to the best of my knowledge, information, and belief.

Indiana Michigan Power Company 1~A-~

ls:ne Lies Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS di DAY OF /\ugLrs+ 2019

~L>.r&@ Notary Publ~

My Commission Expires <:J\,d-\/ ~~5

Enclosure 2 to AEP-NRC-2019-33 Description and Assessment of Technical Specification Changes

1.0 DESCRIPTION

Indiana Michigan Power Company (l&M), the licensee for Donald C. Cook Nuclear Plant (CNP)

Units 1 and 2, requests adoption of Technical Specifications Task Force (TSTF)-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)," into the Technical Specifications (TS) for CNP Units 1 and 2. TSTF-421 changes TS 5.5.5, "Reactor Coolant Pump Flywheel Inspection Program." 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).

2.0 DESCRIPTION

OF PROPOSED AMENDMENT Consistent with the Nuclear Regulatory Commission (NRC) -approved TSTF-421, the proposed TS change includes the following revision to TS 5.5.5:

The examination interval for the RCP flywheels is changed from approximately 10 year intervals coinciding with the lnservice Inspection schedule as required by ASME Section XI to 20 year intervals.

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.

5.0 TECHNICAL ANALYSIS

l&M 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 staff's model SE, as well as the information provided to support TSTF-421 (including WCAP-15666 andthe related SE dated May 5, 2003). l&M has concluded that the justifications presented in the TSTF proposal to AEP-NRC-2019-33 Page 2 and the model SE prepared by the NRG staff are applicable to CNP Units 1 and 2 and justify this amendment for the incorporation of the changes to the CNP Unit 1 and Unit 2 TS.

6.0 REGULATORY ANALYSIS

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

7.0 NO SIGNIFICANT HAZARDS CONSIDERATION l&M has reviewed the proposed no significant hazards consideration determination published on June 24, 2003, (68 FR 37590) as part of the CLIIP. l&M has concluded that the proposed determination presented in the notice is applicable to CNP Units 1 and 2 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

8.0 ENVIRONMENTAL EVALUATION l&M has reviewed the environmental evaluation included in the model SE published on June 24, 2003, (68 FR 37590) as part of the CLIIP. l&M has concluded that the staff's findings presented in that evaluation are applicable to CNP Units 1 and 2 and the evaluation is hereby incorporated by reference for this application.

9.0 PRECEDENT This application is being made in accordance with the CLIIP. l&M is not proposing variations or deviations from the TS changes described in TSTF-421 or the NRG staff's model SE published on June 24, 2003, (68 FR 37590).

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.

to AEP-NRC-2019-33 Page 3

5. NRC letter dated May 5, 2003, from H. Berkow to R. Bryan 0f\JOG) transmitting Safety Evaluation of WCAP-15666.

Enclosure 3 to AEP-NRC-2019-33 Donald C. Cook Nuclear Plant Unit 1 Technical Specification Pages Marked to Show Proposed Changes

at an interval not to exceed 20 years. Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Reactor Coolant Pum This program shall provide for the inspection of ch reactor coolant pump flywheel.

A qualified in-place UT examination over the volume fro the inner bore of the flywheel to the circle one-half of the outer radius or a surfa examination (magnetic particle testing or penetrant testing, or combinatio f the two tests) of exposed surfaces of the removed flywheels shall be conducte 10 years.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program Surveillance Frequency.

5.5.6 DELETED Cook Nuclear Plant Unit 1 5.5-4 Amendment No. ~ . 335

Enclosure 4 to AEP-NRC-2019-33 Donald C. Cook Nuclear Plant Unit 2 Technical Specification Pages Marked to Show Proposed Changes

at an interval not to exceed 20 years. Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Reactor Coolant Pum This program shall provide for the inspection of ch reactor coolant pump flywheel.

A qualified in-place UT examination over the volume fr the inner bore of the flywheel to the circle one-half of the outer radius or a surf e examination (magnetic particle testing or penetrant testing, or combinatio of the two tests) of exposed surfaces of the removed flywheels shall be conducte once every 10 years.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program Surveillance Frequency.

5.5.6 DELETED .

Cook Nuclear Plant Unit 2 5.5-4 Amendment No.~. 317