ML19177A012

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NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031)
ML19177A012
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 06/25/2019
From: Dennis Galvin
Plant Licensing Branch II
To: Zaremba A
Duke Energy Carolinas
References
L 2019-LLA-0031
Download: ML19177A012 (4)


Text

1 NRR-DRMAPEm Resource From:

Galvin, Dennis Sent:

Tuesday, June 25, 2019 5:52 PM To:

Arthur.Zaremba@duke-energy.com Cc:

Mark Turkal (Mark.Turkal@duke-energy.com)

Subject:

Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031)

Attachments:

Brunswick - TS 5.5.12 for Permanent Extension of Type A to 15 years - Draft RAI 2019-06-25.pdf Mr. Zaremba, By letter dated dated February 27, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19058A768), Duke Energy Progress, LLC (the licensee) submitted a license amendment request (LAR) for Brunswick Steam Electric Plant Units 1 and 2 (BSEP). The proposed amendments would modify the BSEP Technical Specification (TS) 5.5.12, Primary Containment Leakage Rate Testing Program, to allow for permanent extension of Appendix J containment leakage testing maximum intervals.

To complete its review, the NRC staff has prepared the attached request for additional information (RAI) in DRAFT form.

To arrange a clarification call for the attached draft RAI and to discuss the due date for the RAI response, please contact me at (301) 415-6256.

Respectfully, Dennis Galvin Project Manager U.S Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Licensing Project Branch 2-2 301-415-6256 Docket No. 50-325, 50-324

Hearing Identifier:

NRR_DRMA Email Number:

68 Mail Envelope Properties (CH2PR09MB39575BEA1811A1B0F7486C5CFBE30)

Subject:

Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031)

Sent Date:

6/25/2019 5:51:52 PM Received Date:

6/25/2019 5:51:00 PM From:

Galvin, Dennis Created By:

Dennis.Galvin@nrc.gov Recipients:

"Mark Turkal (Mark.Turkal@duke-energy.com)" <Mark.Turkal@duke-energy.com>

Tracking Status: None "Arthur.Zaremba@duke-energy.com" <Arthur.Zaremba@duke-energy.com>

Tracking Status: None Post Office:

CH2PR09MB3957.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1035 6/25/2019 5:51:00 PM Brunswick - TS 5.5.12 for Permanent Extension of Type A to 15 years - Draft RAI 2019-06-25.pdf 91285 Options Priority:

Standard Return Notification:

No Reply Requested:

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Normal Expiration Date:

Recipients Received:

OFFICE OF NUCLEAR REACTOR REGULATION DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION TS 5.5.12, PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM FOR PERMANENT EXTENSION OF MAXIMUM APPENDIX J TEST INTERVALS DUKE ENERGY PROGRESS, LLC BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS. 50-325, 50-324 By license amendment request (LAR) dated February 27, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19058A768), Duke Energy Progress, LLC (Duke Energy) proposed a change to the Brunswick Steam Electric Plant (BSEP), Units 1 and 2 Technical Specification (TS) 5.5.12, Primary Containment Leakage Rate Testing Program, to allow for permanent extension of Appendix J containment leakage testing maximum intervals.

Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors, Option B, Performance-Based Requirements, Item V.B.3 states that the regulatory guide or other implementation document used by a licensee to develop a performance-based leakage-testing program must be included, by general reference in the TSs. The current BSEP TS 5.5.12 states that the plants program shall be in accordance with the guidelines contained in Regulatory Guide (RG) 1.163, Performance Based Containment Leak Test Program, dated September 1995 (ADAMS Accession No. ML003740058). RG 1.163 endorsed the Nuclear Electric Institute (NEI) Topical Report NEI 94-01, Revision 0, Industry Guideline for Implementing Performance Based Option of 10 CFR Part 50, Appendix J, dated July 26, 1995 (ADAMS Accession No. ML11327A025).

The LAR proposes to replace this with a reference to NEI 94-01, Revision 3-A, dated July 31, 2012 (ADAMS Accession No. ML12221A202), with the conditions of NEI 94-01, Revision 2-A, dated November 19, 2008 (ADAMS Accession No. ML100620847). All revisions of NEI 94-01 require, as a prerequisite for extending the integrated leak rate test (ILRT) interval beyond three times in 10 years, that the results of the previous two tests are less than or equal to the performance criterion leakage rate specified in the TS.

LAR Enclosure page 25 has Tables 3.4.4-3 and 3.4.4-4 titled Verification of Current Extended ILRT Interval for BSEP Unit (1 and 2 respectively). The data entered in Table 3.4.4-4 for the 03/30/2005 Unit 2 ILRT performance is the same as that for Table 3.4.4-3 for the 03/25/2004 Unit 1 ILRT performance. This suggests a possible cut and paste transcription error.

LAR Tables 3.4.4-3 and 3.4.4-4 include columns labeled, Measured Leakage Rate at 95% UCL

(%wt./day), Water Level Corrections (%wt./day), and Corrections for valves not in Accident Positions during Test (%wt./day). The data in these three columns when summed give the values in a fourth column labeled Performance Leakage Rate LAR Enclosure pages 20 and 21 show Tables 3.4.4-1 and 3.4.4-2 titled BSEP Unit 1(2) Type A Testing History, respectively.

Tables 3.4.4-1 and 3.4.4-2 include columns labeled 95% Upper Confidence Limit (wt.%/day),

As-Found Leakage (wt.%/day), As-Left Leakage (wt.%/day), and Performance Leakage Rate (wt.%/day). It is not clear how the how the as-found leakage rate values were determined and why they differ from the as-left values and performance leakage rate values.

RAI SCPB-1: Provide the correct values for Tables 3.4.4-3 and 3.4.4-4 or confirm the values originally provided are correct. Provide a description of how the As-Found ILRT values shown in LAR Enclosure Tables 3.4.4-1 and 3.4.4-2 were derived relative to the Performance Leakage Rate values shown in Tables 3.4.4-3 and 3.4.4-4.