ML053480216

Safety Evaluation Report Regarding the License Renewal Application for Monticello Nuclear Generating Plant

ML053480216
Person / Time
Site:	Monticello
Issue date:	12/12/2005
From:	Dennig R NRC/NRR/ADRA/DRA/ACVB
To:	Lund A NRC/NRR/ADRO/DLR/REBA
Goel R, NRR/DRA, 415-2806
References
TAC MC6440
Download: ML053480216 (4)

Text

December 12, 2005 MEMORANDUM TO: A. Louise Lund, Chief License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation FROM:

Robert L. Dennig, Chief

/RA/

Containment and Ventilation Branch Division of Risk Assessment Office of Nuclear Reactor Regulation

SUBJECT:

SAFETY EVALUATION REPORT REGARDING THE LICENSE RENEWAL APPLICATION FOR MONTICELLO NUCLEAR GENERATING PLANT (TAC NO. MC6440)

The Containment and Ventilation Branch reviewed the license renewal application (LRA) submitted by Nuclear Management Company, LLC, Licensee of Monticello Nuclear Generating Plant. The review included the following sections of the application and associated systems that are within the scope of license renewal in accordance with Title 10 of the Code of Federal Regulations, Part 54.4(a) (10 CFR 54.4(a)), and subject to an aging management review in accordance with 10 CFR 54.21(a)(1). As a result of our review, attached is a safety evaluation report (SER).

LRA Section 2.3.2.2, Combustible Gas Control System LRA Section 2.3.2.5, Primary Containment Mechanical System Our effort on TAC No. MC6440 is being continued due to additional technical support needed for resolving the Office of the General Counsels comments and Advisory Committee on Reactor Safeguards briefings. If you have any questions regarding this SER please contact us.

Docket No.: 50-263

Enclosure:

As stated

Contact:

Raj Goel, DRA/NRR (301) 415-2806

December 12, 2005 MEMORANDUM TO: A. Louise Lund, Chief License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation FROM:

Robert L. Dennig, Chief

/RA/

Containment and Ventilation Branch Division of Risk Assessment Office of Nuclear Reactor Regulation

SUBJECT:

SAFETY EVALUATION REPORT REGARDING THE LICENSE RENEWAL APPLICATION FOR MONTICELLO NUCLEAR GENERATING PLANT (TAC NO. MC6440)

The Containment and Ventilation Branch reviewed the license renewal application (LRA) submitted by Nuclear Management Company, LLC, Licensee of Monticello Nuclear Generating Plant. The review included the following sections of the application and associated systems that are within the scope of license renewal in accordance with Title 10 of the Code of Federal Regulations, Part 54.4(a) (10 CFR 54.4(a)), and subject to an aging management review in accordance with 10 CFR 54.21(a)(1). As a result of our review, attached is a safety evaluation report (SER).

LRA Section 2.3.2.2, Combustible Gas Control System LRA Section 2.3.2.5, Primary Containment Mechanical System Our effort on TAC No. MC6440 is being continued due to additional technical support needed for resolving the Office of the General Counsels comments and Advisory Committee on Reactor Safeguards briefings. If you have any questions regarding this SER please contact us.

Docket No.: 50-263

Enclosure:

As stated DISTRIBUTION: DRA r/f D. Merzke ADAMS Accession #: ML053480216 G:\\ACVB\\GOEL\\Monticello LRA_CNTM SE.wpd NRR-096 OFFICE NRR/DRA/ACVB NRR/DRA/ACVB NRR/DRA/ACVB NAME RGoel HWalker RDennig DATE 12/12/05 12/12/05 12/12/05 OFFICIAL RECORD COPY

ENCLOSURE SAFETY EVALUATION REPORT BY THE CONTAINMENT AND VENTILATION BRANCH, OFFICE OF NUCLEAR REACTOR REGULATION LICENSE RENEWAL APPLICATION FOR MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 TAC NO. MC6440 2.3.2.2 Combustible Gas Control System 2.3.2.2.1 Summary of Technical Information in the Application (to be provided by RLEP) 2.3.2.2.2 Staff Evaluation The staff reviewed license renewal application (LRA) Section 2.3.2.2 and Monticello Nuclear Generating Plant Updated Safety Analysis Report (USAR), Sections 5.2.1.5, and 5.2.2.9 using the evaluation methodology described in Section 2.1 of this safety evaluation report (SER). The staff conducted its review in accordance with the guidance described in Standard Review PlanLicense Renewal (SRP-LR) Section 2.3, Scoping and Screening Results - Mechanical Systems.

In conducting its review, the staff evaluated the system functions described in the LRA and USAR in accordance with the requirements of Title 10 of the Code of Federal Regulations, Part 54.4(a) (10 CFR 54.4(a)) to verify that the applicant did not inadvertently omit from the scope of license renewal any components with intended functions delineated under 10 CFR 54.4(a). The staff then reviewed those components that the applicant identified as being within the scope of license renewal to verify that the applicant did not omit any passive and long-lived components that should be subject to an aging management review (AMR) in accordance with the requirements of 10 CFR 54.21(a)(1).

On the basis of its review, the staff found that the applicant has identified those portions of the combustible gas control (CGC) system that meet the scoping requirements of 10 CFR 54.4 and has included them within the scope of license renewal in LRA Section 2.3.2.8. The applicant has also included CGC system components that are subject to an AMR in accordance with 10 CFR 54.4(a), and 10 CFR 54.21(a)(1) in LRA Table 2.3.2-2, Combustible Gas Control System. The staff did not identify any omissions.

2.3.2.2.3 Conclusions During its review of information provided in the LRA, license renewal drawings, and licensing-basis information, the staff did not identify any omissions or discrepancies in the applicants scoping and screening results for the components of the CGC system. Therefore, the staff concludes that the applicant has adequately identified the CGC system components that are within the scope of license renewal, as required by 10 CFR 54.4(a), and that the applicant has adequately identified the CGC system components that are subject to an AMR, as required by 10 CFR 54.21(a)(1).

2.3.2.5 Primary Containment Mechanical System 2.3.2.5.1 Summary of Technical Information in the Application (to be provided by RLEP) 2.3.2.5.2 Staff Evaluation The staff reviewed LRA Section 2.3.2.5 and Monticello Nuclear Generating Plant USAR Sections 5.2.1.3, 5.2.2.3, 5.2.2.7, 5.2.2.10, 5.2.3.11, and 10.3.10.1 using the evaluation methodology described in Section 2.1 of this SER. The staff conducted its review in accordance with the guidance described in SRP-LR Section 2.3, Scoping and Screening Results - Mechanical Systems.

In conducting its review, the staff evaluated the system functions described in the LRA and USAR in accordance with the requirements of 10 CFR 54.4(a) to verify that the applicant did not inadvertently omit from the scope of license renewal any components with intended functions delineated under 10 CFR 54.4(a). The staff then reviewed those components that the applicant identified as being within the scope of license renewal to verify that the applicant did not omit any passive and long-lived components that should be subject to an AMR in accordance with the requirements of 10 CFR 54.21(a)(1).

On the basis of its review, the staff found that the applicant has identified those portions of the primary containment mechanical (PCM) system that meet the scoping requirements of 10 CFR 54.4 and has included them within the scope of license renewal in LRA Section 2.3.2.5.

The applicant has also included PCM system components that are subject to an AMR in accordance with 10 CFR 54.4(a), and 10 CFR 54.21(a)(1) in LRA Table 2.3.2-5, Primary Containment Mechanical System. The staff did not identify any omissions.

2.3.3.5.3 Conclusions During its review of information provided in the LRA, license renewal drawings, and licensing-basis information, the staff did not identify any omissions or discrepancies in the applicants scoping and screening results for the components of the PCM system. Therefore, the staff concludes that the applicant has adequately identified the PCM system components that are within the scope of license renewal, as required by 10 CFR 54.4(a), and that the applicant has adequately identified the PCM System components that are subject to an AMR, as required by 10 CFR 54.21(a)(1).