ML21026A347: Difference between revisions

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==Dear Mr. Scarpello,==
==Dear Mr. Scarpello,==


By letter dated October 5, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20290A500), Indiana Michigan Power Company (I&M, the licensee) requested that, pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), the Nuclear Regulatory Commission (NRC) authorize relief request REL-PP2 for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). Specifically, the licensee requested authorization of a proposed alternative to certain requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), associated with the vibration acceptance criteria for smooth running pumps at CNP.
By {{letter dated|date=October 5, 2020|text=letter dated October 5, 2020}} (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20290A500), Indiana Michigan Power Company (I&M, the licensee) requested that, pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), the Nuclear Regulatory Commission (NRC) authorize relief request REL-PP2 for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). Specifically, the licensee requested authorization of a proposed alternative to certain requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), associated with the vibration acceptance criteria for smooth running pumps at CNP.
The NRC staff has reviewed the submittals and determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on January 26, 2021, the I&M staff indicated that a response to the RAIs would be provided by February 26, 2021.
The NRC staff has reviewed the submittals and determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on January 26, 2021, the I&M staff indicated that a response to the RAIs would be provided by February 26, 2021.
If you have questions, please contact me at 301-415-2855 or via e-mail at Scott.Wall@nrc.gov.
If you have questions, please contact me at 301-415-2855 or via e-mail at Scott.Wall@nrc.gov.
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REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE TO AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE RELIEF REQUEST REL-PP2
REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE TO AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE RELIEF REQUEST REL-PP2


INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-315 AND 50-316 INTRODUCTION By letter dated October 5, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20290A500), Indiana Michigan Power Company (I&M, the licensee) requested that, pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), the Nuclear Regulatory Commission (NRC) authorize relief request REL-PP2 for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). Specifically, the licensee requested authorization of a proposed alternative to certain requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), associated with the vibration acceptance criteria for smooth running pumps at CNP.
INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-315 AND 50-316 INTRODUCTION By {{letter dated|date=October 5, 2020|text=letter dated October 5, 2020}} (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20290A500), Indiana Michigan Power Company (I&M, the licensee) requested that, pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), the Nuclear Regulatory Commission (NRC) authorize relief request REL-PP2 for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). Specifically, the licensee requested authorization of a proposed alternative to certain requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), associated with the vibration acceptance criteria for smooth running pumps at CNP.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the application and has determined that the following additional information is required in order to complete the review.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the application and has determined that the following additional information is required in order to complete the review.
APPLICABLE REGULATION AND GUIDANCE The NRC regulations in 10 CFR 50.55a(z)(1) require that a licensee must demonstrate that its proposed alternative would provide an acceptable level of quality and safety.
APPLICABLE REGULATION AND GUIDANCE The NRC regulations in 10 CFR 50.55a(z)(1) require that a licensee must demonstrate that its proposed alternative would provide an acceptable level of quality and safety.
The NRC regulations in 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, states, in part, that valves that are within the scope of the ASME OM Code must meet the inservice testing (IST) requirements set forth in the ASME OM Code; and that valves that are within the scope of the ASME OM Code, but are not classified as ASME BPV Code Class 1, 2, or 3, may be satisfied as part of an augmented IST program.
The NRC regulations in 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, states, in part, that valves that are within the scope of the ASME OM Code must meet the inservice testing (IST) requirements set forth in the ASME OM Code; and that valves that are within the scope of the ASME OM Code, but are not classified as ASME BPV Code Class 1, 2, or 3, may be satisfied as part of an augmented IST program.
RAI-EMIB-01 The NRC staff compared the October 5, 2020, submittal to the version of the CNP IST Program Plan outlined in letter dated June 30, 2016 (ADAMS Accession No. ML16197A057) and noted apparent differences. Please confirm the information for the components within scope of the IST Program with respect to the differences noted in the table below:
RAI-EMIB-01 The NRC staff compared the October 5, 2020, submittal to the version of the CNP IST Program Plan outlined in {{letter dated|date=June 30, 2016|text=letter dated June 30, 2016}} (ADAMS Accession No. ML16197A057) and noted apparent differences. Please confirm the information for the components within scope of the IST Program with respect to the differences noted in the table below:
Pump                      Submittal Information            IST Plan Information 1-PP-3E                        Code Class 2                      Code Class 3 1-PP-3W 1-PP-7E                          Centrifugal              Vertical Line Shaft (VLS) 1-PP-7W 1-PP-9E                  Code Class 3, OM Group A          Code Class 2, OM Group B 1-PP-9W 1-QT-106-AB1                  Non Class, OM Group B,            Not in IST Plan Table 1-QT-106-AB2              Positive Displacement Pump 1-QT-106-CD1 1-QT-106-CD2
Pump                      Submittal Information            IST Plan Information 1-PP-3E                        Code Class 2                      Code Class 3 1-PP-3W 1-PP-7E                          Centrifugal              Vertical Line Shaft (VLS) 1-PP-7W 1-PP-9E                  Code Class 3, OM Group A          Code Class 2, OM Group B 1-PP-9W 1-QT-106-AB1                  Non Class, OM Group B,            Not in IST Plan Table 1-QT-106-AB2              Positive Displacement Pump 1-QT-106-CD1 1-QT-106-CD2


Revision as of 19:38, 7 March 2021

NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval
ML21026A347
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 01/26/2021
From: Scott Wall
NRC/NRR/DORL/LPL3
To: Scarpello M
Indiana Michigan Power Co
Wall S
References
L-2020-LLR-0138
Download: ML21026A347 (4)
v • d • e


Text

From: Wall, Scott Sent: Tuesday, January 26, 2021 3:48 PM To: Michael K. Scarpello Cc: Helen L Levendosky; Joe Tanko

Subject:

Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year interval (EPID No. L-2020-LLR-0138)

Dear Mr. Scarpello,

By letter dated October 5, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20290A500), Indiana Michigan Power Company (I&M, the licensee) requested that, pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), the Nuclear Regulatory Commission (NRC) authorize relief request REL-PP2 for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). Specifically, the licensee requested authorization of a proposed alternative to certain requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), associated with the vibration acceptance criteria for smooth running pumps at CNP.

The NRC staff has reviewed the submittals and determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on January 26, 2021, the I&M staff indicated that a response to the RAIs would be provided by February 26, 2021.

If you have questions, please contact me at 301-415-2855 or via e-mail at Scott.Wall@nrc.gov.

Scott P. Wall, LSS BB, BSP Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301.415.2855 Scott.Wall@nrc.gov Docket Nos. 50-315 and 50-316

Enclosure:

Request for Additional Information cc: Listserv RAI-EMIB (REL-PP2)

REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE TO AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE RELIEF REQUEST REL-PP2

INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-315 AND 50-316 INTRODUCTION By letter dated October 5, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20290A500), Indiana Michigan Power Company (I&M, the licensee) requested that, pursuant to Section 50.55a(z)(1) of Title 10 of the Code of Federal Regulations (10 CFR), the Nuclear Regulatory Commission (NRC) authorize relief request REL-PP2 for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). Specifically, the licensee requested authorization of a proposed alternative to certain requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), associated with the vibration acceptance criteria for smooth running pumps at CNP.

The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the application and has determined that the following additional information is required in order to complete the review.

APPLICABLE REGULATION AND GUIDANCE The NRC regulations in 10 CFR 50.55a(z)(1) require that a licensee must demonstrate that its proposed alternative would provide an acceptable level of quality and safety.

The NRC regulations in 10 CFR 50.55a(f)(4), Inservice testing standards requirement for operating plants, states, in part, that valves that are within the scope of the ASME OM Code must meet the inservice testing (IST) requirements set forth in the ASME OM Code; and that valves that are within the scope of the ASME OM Code, but are not classified as ASME BPV Code Class 1, 2, or 3, may be satisfied as part of an augmented IST program.

RAI-EMIB-01 The NRC staff compared the October 5, 2020, submittal to the version of the CNP IST Program Plan outlined in letter dated June 30, 2016 (ADAMS Accession No. ML16197A057) and noted apparent differences. Please confirm the information for the components within scope of the IST Program with respect to the differences noted in the table below:

Pump Submittal Information IST Plan Information 1-PP-3E Code Class 2 Code Class 3 1-PP-3W 1-PP-7E Centrifugal Vertical Line Shaft (VLS) 1-PP-7W 1-PP-9E Code Class 3, OM Group A Code Class 2, OM Group B 1-PP-9W 1-QT-106-AB1 Non Class, OM Group B, Not in IST Plan Table 1-QT-106-AB2 Positive Displacement Pump 1-QT-106-CD1 1-QT-106-CD2

1-QT-130-AB1 Non Class, OM Group A, Augmented Group B 1-QT-130-AB2 Centrifugal 1-QT-130-CD1 1-QT-130-CD2 2-PP-3E Code Class 2 Code Class 3 2-PP-3W 2-PP-7E Centrifugal VLS 2-PP-7W 2-PP-9E Code Class 3, OM Group A Code Class 2, OM Group B 2-PP-9W 2-QT-106-AB1 Non Class, OM Group B, Not in IST Plan Table 2-QT-106-AB2 Positive Displacement Pump 2-QT-106-CD1 2-QT-106-CD2 2-QT-130-AB1 Non Class, OM Group A, Not in IST Plan Table 2-QT-130-AB2 Centrifugal 2-QT-130-CD1 2-QT-130-CD2 EMIB REVIEW NOTE ASME prepares Code Cases to provide alternative methods to satisfy certain requirements of the ASME OM Code. Recently, ASME issued Code Case OMN-22, Smooth Running Pumps, to provide its recommended method for an alternative to the ASME OM Code pump testing requirements for smooth running pumps. The wording in the licensees alternative request looks similar to OMN-22, but this Code Case is not directly referenced in the alternative request. Does the similarity in wording reflect the licensees intention to follow OMN-22?

Hearing Identifier: NRR_DRMA Email Number: 984 Mail Envelope Properties (MN2PR09MB50193E85A903FB164406DA8C92BC9)

Subject:

Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year interval (EPID No. L-2020-LLR-0138)

Sent Date: 1/26/2021 3:47:55 PM Received Date: 1/26/2021 3:47:56 PM From: Wall, Scott Created By: Scott.Wall@nrc.gov Recipients:

"Helen L Levendosky" <hllevendosky@aep.com>

Tracking Status: None "Joe Tanko" <jmtanko@aep.com>

Tracking Status: None "Michael K. Scarpello" <mkscarpello@aep.com>

Tracking Status: None Post Office: MN2PR09MB5019.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 5464 1/26/2021 3:47:56 PM Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

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