ML20184A005

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Request for Additional Information (E-mail Dated 7/2/2020) Relief Request IR-3-33 for Limited Coverage Examiniations
ML20184A005
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/02/2020
From: Sinha S
Dominion Energy Nuclear Connecticut
To: Richard Guzman
NRC/NRR/DORL/LPL1
Guzman R
References
EPID L-2020-LLR-0029
Download: ML20184A005 (3)


Text

Guzman, Richard From: Guzman, Richard Sent: Thursday, July 02, 2020 6:31 AM To: Shayan.Sinha@dominionenergy.com

Subject:

Millstone Unit 3 - REQUEST FOR ADDITIONAL INFORMATION - REQUEST FOR RELIEF IR-3-33 (EPID: L-2020-LLR-0029)

Shayan, On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) staff sent Dominion Energy Nuclear Connecticut, Inc. (DENC, the licensee) the subject Request for Additional Information (RAI) as a draft (via e-mail shown below). This RAI relates to Relief Request IR-3-33 submitted by DENC dated February 17, 2020 (ADAMS Accession No. ML20049A088) for Millstone Power Station, Unit 3. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(g)(5)(iii), the licensee requested relief from certain ASME Code inspection requirements on the basis that these requirements were impractical. The licensees relief request applies to ASME Code inspections that were attempted during the 2 nd period of the third ISI interval.

You indicated on June 30th that a clarification call was not necessary to respond to the information request. I understand DENC will provide a response to this RAI by August 3, 2020 (approximately 30 days from the issuance of the RAI). Updated below is the official (final) RAI. A publicly available version of this e-mail and RAI will be placed in the NRCs ADAMS system. Please contact me should you have any questions in regard to this request.

Thanks, Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov From: Guzman, Richard <Richard.Guzman@nrc.gov>

Sent: Monday, June 29, 2020 12:23 PM To: Shayan Sinha (Services - 6) <Shayan.Sinha@dominionenergy.com>

Subject:

[EXTERNAL] Millstone Unit 3 - DRAFT Request for Additional Information - REQUEST FOR RELIEF IR-3-33 (EPID: L-2020-LLR-0029)

Shayan, By letter dated February 17, 2020, (ADAMS Accession No. ML20049A088), Dominion Energy Nuclear Connecticut, Inc., (the licensee), requested relief from the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code (Code),Section XI, requirements for certain inservice inspections (ISI) of component welds at Millstone Power Station, Unit 3. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(g)(5)(iii), the licensee requested relief from certain ASME Code inspection requirements and submitted Relief Request IR-3-33 on the basis that these requirements were impractical. The licensees relief request applies to ASME Code inspections that were attempted during the 2 nd period of the third ISI interval.

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The Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to complete its review, as described in the request for additional information (RAI) shown below. This RAI is identified as draft at this time to confirm your understanding of the information needed by the NRC staff to complete its evaluation. If youd like to have a clarification call, please let me know and I will coordinate availabilities w/the NRC technical staff. I intend to send out the questions below as official by the end of next week, if possible.

Thanks,

~~~~~~~~~~~

Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov

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REQUEST FOR ADDITIONAL INFORMATION ON THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF IR-3-33 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNIT 3 DOCKET NO. 50-423 (EPID NO. L-2020-LLR-0029)

By letter dated February 17, 2020, (Agencywide Documents Access and Management System (ADAMS),

Accession No. ML20049A088), Dominion Energy Nuclear Connecticut, Inc., (the licensee), requested relief from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, requirements for certain inservice inspections (ISI) of component welds at Millstone Power Station, Unit

3. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(g)(5)(iii),

the licensee requested relief from certain ASME Code inspection requirements and submitted Relief Request IR-3-33 on the basis that these requirements were impractical. The licensees relief request applies to ASME Code inspections that were attempted during the 2nd period of the third ISI interval.

The NRC staff has reviewed the information provided in the submittal and has determined that additional information as requested below is needed to complete its review.

RAI 1

ASME Code,Section XI, Article I-2210 states that ultrasonic examination of vessels not greater than 2 inches in thickness shall be conducted in accordance with Appendix III, as supplemented by Table I-2000-1. Relief Request IR-3-33 states that Weld 03-074-004, an Examination Category C-A Pressure Retaining Weld in Pressure Vessels, was examined using equipment and procedures written in accordance with ASME Section XI, Appendix I and Section V, Article 4. The staff notes that the thickness of Weld 03-074-004 is less than 2 2

inches; therefore, it appears that this weld should be examined in accordance with Appendix III of the ASME Code,Section XI as well.

Please discuss whether Weld 03-074-004 was examined in accordance with ASME Code,Section XI, Appendix III as supplemented by Table I-2000-1, as required by Section XI, Article I-2210. If not, please provide justification.

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