ML18038A785

Summary Report for NRC Audit for Point Beach Nuclear Plant, Units 1 and 2, License Amendment Request to Resolve Nonconformance Relating to Containment Dome Truss

ML18038A785
Person / Time
Site:	Point Beach
Issue date:	03/06/2018
From:	Mahesh Chawla Plant Licensing Branch III
To:	Craven R Point Beach
Chawla M, NRR/DORL/LPLIII
References
EPID L-2017-LLA-0209
Download: ML18038A785 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 6, 2018 Mr. Robert Craven Plant General Manager NextEra Energy Point Beach, LLC 661 O Nuclear Road Two Rivers, WI 54241

SUMMARY

REPORT FOR NRC AUDIT FOR POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE AMENDMENT REQUEST TO RESOLVE NONCONFORMANCE RELATING TO CONTAINMENT DOME TRUSS (EPID L-2017-LLA-0209)

Dear Mr. Coffey:

By letter dated March 31, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17090A511), NextEra Energy Point Beach, LLC (NextEra, the licensee) submitted a license amendment request (LAR) for the Point Beach Nuclear Plant PBNP), Units 1 and 2. The proposed amendment uses a risk-informed resolution strategy to resolve legacy design code non-conformances associated with construction trusses in the containment buildings of PBNP, Units 1 and 2.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the subject license amendment request review process. The NRC staff developed a request for information needed to conduct the audit. The initial request for technical information was provided to the licensee via email sent on October 30, 2017 (ADAMS Accession No. ML17307A040). A follow up public teleconference was held on November 14, 2017 (ADAMS Accession No. ML17311A084), to discuss the requested technical information.

The NRC staff conducted the audit on November 29 and 30, 2017, at the NextEra office in Jupiter, Florida. The staff noted that upon completion of the audit, the draft requests for additional information (RAls) would be revised, as necessary, and issued as final, and the licensee would be expected to provide the needed information on the docket. The results of the audit were used by the NRC staff to finalize and transmit RAls on January 31, 2018 (ADAMS Accession No. ML18025C043).

The audit summary report is provided as an enclosure to this letter.

R. Craven If you have any questions, please contact me at (301) 415-8371 or Mahesh.Chawla@nrc.gov.

Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosure:

Audit Summary Report cc: ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0.C. 20555-0001 AUDIT

SUMMARY

REPORT FOR POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE AMENDMENT REQUEST TO RESOLVE NONCONFORMANCES RELATING TO CONTAINMENT DOME TRUSS DOCKET NOS. 50-266 AND 50-301 EPID L-2017-LLA-0209

1.0 INTRODUCTION

By letter dated March 31, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17090A511), NextEra Energy Point Beach, LLC (NextEra, the licensee) submitted a license amendment request (LAR) for the Point Beach Nuclear Plant PBNP), Units 1 and 2. The proposed amendment uses a risk-informed resolution strategy to resolve legacy design code nonconformances associated with construction trusses in the containment buildings of PBNP, Units 1 and 2.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittal and determined that a regulatory audit would assist in the timely completion of the subject LAR review process. The NRC staff developed a request for information needed to conduct the audit. The initial request for technical information was provided to the licensee via email sent on October 30, 2017 (ADAMS Accession No. ML17307A040). A follow up public teleconference was held on November 14, 2017 (ADAMS Accession No. ML17311A084), to discuss the requested technical information.

The NRC staff conducted the audit on November 29 and 30, 2017, at the NextEra office in Jupiter, Florida.

The audit was performed consistent with NRC Office of Nuclear Reactor Regulation (NRR)

Office Instruction LIC-111, "Regulatory Audits," (ADAMS Accession No. ML082900195). The audit supported the staff's review of the licensee's submittal.

2.0 AUDIT ACTIVITIES AND OBSERVATIONS During the audit the NRC staff and the licensee discussed each of the information needs provided to the licensee. Technical discussions were focused on the scope of the proposed change, structural design consideration, and the structural and risk analysis performed to support the proposed change. In response to the staff's information needs, the licensee provided details, using drawings and calculations listed in the following table. These documents were uploaded to an electronic portal set up by the licensee in response to NRC letter dated July 25, 2017 (ADAMS Accession No. ML17202G591 ).

Enclosure

LIST OF SHAREPOINT PORTAL REQUESTED DOCUMENTS FOR THE LICENSE AMENDMENT REQUEST (LAR)

Document# Cross-reference to the LAR Report title and number Point Beach CT Target Assessment, PBN-1 Reference 3 in Enclosure 4 BFJR-17-020 Photographs and videos from walkdown performed to support containment truss target assessment (it would be most beneficial if the 2 Not Applicable photographs and videos showed the components of interest for the assessment in relation to the containment trusses and any barriers) 1100060-C-005, Rev. 1, "SSI Analysis of 3 Reference 5.5 in Enclosure 5 Containment Building for Response Spectra at Supports of Dome Truss" 1100060-C-022, Rev. 0, "Thermal Evaluation 4 Reference 5.8 in Enclosure 5 of Unit 1 Containment Dome Truss in Support of Risk Informed LAR" 1100060-C-023, Rev. 0, "Thermal Evaluation 5 Reference 5.9 in Enclosure 5 of Unit 2 Containment Dome Truss in Support of Risk Informed LAR" 11 Q0060-C-024, Rev. 0, "Seismic Evaluation Reference 5.1 O in Enclosure 6 of Unit 1 Containment Dome Truss in Support 5

of Risk Informed LAR" 1100060-C-025, Rev. 0, "Seismic Evaluation Reference 5.11 in Enclosure 7 of Unit 2 Containment Dome Truss in Support 5

of Risk Informed LAR" Reference 5.14 in Enclosure 1100060-C-028, Rev. 0, "Seismic Fragility 8

5 Analysis of Containment Dome Trusses" 11 Q0060-C-030, Rev. 0, "Probability of Failure Reference 5.16 in Enclosure 9 vs Temperature for Unit 1 Containment Dome 5

Truss in Support of Risk Informed LAR" 1100060-C-031, Rev. 0, "Probability of Failure Reference 5.17 in Enclosure 10 vs Temperature for Unit 1 Containment Dome 5

Truss in Support of Risk Informed LAR" 1100060-C-032, Rev. 0, "Evaluation of Unit 1 Reference 5.18 in Enclosure Containment Spray Piping under Seismic 11 5 Loading Using GMRS Input in Support of Risk Informed LAR" 1100060-C-033, Rev. 0, "Evaluation of Unit 1 Reference 5.19 in Enclosure Containment Spray Piping under Seismic 12 5 Loading Using GMRS Input in Support of Risk Informed LAR" 1100060-C-034, Rev. 0, "Analysis of Reference 5.20 in Enclosure 13 Containment Liner to Determine Elastic Limit 5

under Contact Load from CDT" Reference 5.24 in Enclosure 1100060-C-038, Rev. 0, "Seismic Strength 14 5 Capacity of Units 1 and 2 Containment Dome

Document# Cross-reference to the LAR Report title and number Trusses with Modifications to Meet AISC N690 Acceptance Criteria" The licensee indicated that a peer review was conducted for the PRA analysis as well as the seismic and thermal fragility analyses.

Provide peer review procedures, guidance, or 15 Not applicable acceptance standards; applicable self-assessment report which was provided to the peer review team; and peer review team report.

16 Ref. 4.1 in Enclosure 5 Drawing C-125, Rev.10 Dome Truss shop drawings (from 4.2.1 -

17 Ref. 4.2 in Enclosure 5 4.2.17)

Westinghouse letter WEP-97-541, dated 18 Ref. 3.10 in Enclosure 5 December 8, 1997 Bechtel Job 6118-Vol 8 - Book 44 "Seismic 19 Ref. 5.1 in Enclosure 5 Analysis - Containment" 6904-15-TR, Rev. 0, "calc. for Adequacy of 20 Ref. 5.2 in Enclosure 5 Containment Dome Truss" 11 Q0060-C-001, Rev.O, Including CCN-001 21 Ref. 5.4 in Enclosure 5 and CCN-002 1100060-RPT-002, Revision 1, Methodology and Criteria to Determine the Strength Capacity of the Point Beach Nuclear Plant 22 Ref. 6.9 in Enclosure 5 Containment Dome Trusses and Attached/Adjacent Components in Support of a Risk-Informed License Amendment Request

3.0 CONCLUSION

S During this audit, the NRC staff did not make any regulatory decisions regarding the proposed license amendment. The NRC staff noted that upon completion of the audit, the draft requests for additional information (RAls) would be revised, as necessary, and issued as final, and the licensee would be expected to provide the needed information on the docket. Subsequent to the audit, the staff finalized and transmitted the RAls (ADAMS Accession No. ML18025C043).

4.0 AUDIT PARTICIPANTS NRC

Participants:

• Mahesh Chawla, Project Manager, NRC

• Shilp Vasavada, Technical Reviewer, Probabilistic Risk Assessment (PRA), NRC

• Sara Lyons, Technical Reviewer, PRA, NRC

• Ching Ng, Technical Reviewer, PRA, NRC

• Dan Hoang, Technical Reviewer, Structural Engineering, NRC

NextEra

Participants:

• Steve Cattron

• Lori Christensen

• Rich LaPlante

• Nabil Juraydini

• Anil Julka

• Ted Kulczycky

• Stan Guokas Principal Contributor: Shilp Vasavada, NRR/DRA/APLB/RILIT

ML18038A785 OFFICE NRR/DORULPL3/PM NRR/DORULPL3/LA NRR/DRA/APLB/RILI (A)

NAME MChawla SRohrer CFong DATE 02/07/2018 02/07/2018 02/08/2018 OFFICE NRR/DE/ESEB/BC NRR/DORULPL3/BC NRR/D0RULPL3/PM NAME BWittick DWrona MChawla DATE 02/07/2018 02/21/2018 03/06/2018