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# | {{Adams | ||
| number = ML20118D177 | |||
| issue date = 04/27/2020 | |||
| title = Updated Safety Analysis Report (USAR) Revision 36 | |||
| author name = Sharp S | |||
| author affiliation = Xcel Energy, Northern States Power Co | |||
| addressee name = | |||
| addressee affiliation = NRC/Document Control Desk, NRC/NRR | |||
| docket = 05000282, 05000306 | |||
| license number = DPR-042, DPR-060 | |||
| contact person = | |||
| case reference number = L-PI-20-016 | |||
| package number = MML20118D173 | |||
| document type = Letter, Updated Final Safety Analysis Report (UFSAR) | |||
| page count = 2 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:'{},, x~;;E~o;;;gyi~ Enclosure 3 Contains SUNSI Disclosure in Accordance with 10CFR 2.390. | |||
R ES P O N S I B LE B V NAT U R E 1717 Wakonade Drive Welch, MN 55089 April 27, 2020 L-Pl-20-016 10 CFR 50.71(e) | |||
U S Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos . DPR-42 and DPR-60 Updated Safety Analysis Report (USAR) Revision 36 | |||
==References:== | |||
: 1) NSPM letter, S. Sharp to NRC Document Control Desk, "Changes to Technical Specification Bases, " L-Pl-18-030, dated May 18, 2018 (ADAMS Accession No. ML18155A431) | |||
: 2) NSPM letter, S. Sharp to NRC Document Control Desk, "50.59 Evaluation Summary Report," L-Pl-17-051, dated December 28, 2017 (ADAMS Accession No ML17362A148) | |||
: 3) NRC letter, from R. Kuntz to S. Northard, "Issuance of Amendments - | |||
Transition to NFPA-805 "Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, dated August 8, 2017 (ADAMS Accession No. ML17163A027) | |||
Pursuant to 10CFR 50 .71(e) and Nuclear Regulatory Commission (NRC) specific exemption granted May 22, 2006 (ADAMS Accession Number ML061110032), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM") , by this letter submits USAR, Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. | |||
Enclosure 1, Information Regarding Changes to the USAR, identifies those changes made based on approved license amendments , changes made under the provisions of 10 CFR 50 .59, 10 CFR 50.46, and editorial changes including deletion of particular information and the basis for that deletion. | |||
Enclosure 2 (Non- Proprietary) and Enclosure 3 (Proprietary), Contains the Updated Safety Analysis Report (USAR) Revision 36 in its entirety. This revision was made pursuant to 10 CFR 50.71 (e), using the guidance of NEI 98-03 , Rev. 1, "Guidelines for Updating Final Safety Analysis Reports Enclosure 4, In accordance with TS 5.5.12, "Technical Specifications (TS) Bases Control Program ," contains the TS Bases for the Prai rie Island Nuclear Generating Plant, Units 1 and 2, that includes the changes to the bases from Revisions 242 through 246 that have been implemented since the previous submittal (Reference 1). | |||
Document Control Desk Page 2 Enclosure 5, Contains a brief description and a summary of the safety evaluation for each of those changes , tests , and experiments made under the provisions of 10 CFR 50.59 during the period of January 2018 to present (Reference 2) . | |||
NRC Safety Evaluation Report (SER) dated August 8, 2017, approved the NFPA 805 License Amendment Request (LAR) which made changes to the PINGP USAR in accordance with 10 CFR 50. 71 (e) and the exemption from 10 CFR 50.71 (e)(4) which allows periodic updates of the PINGP USAR to be submitted within C of each Unit2 refueling outage, not to exceed 24 months from the previous submittal. (Reference 3) | |||
Consistent with the guidance in Regulatory Issue Summary {RIS) 2007-16, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses", a review of eng ineering changes, equipment list changes, USAR changes, changes to SSCs credited to 10 CFR 54.4(a)(3) regulated events, and changes to time limited aging analyses (TLAAs) was conducted for the review period from November 20, 2017 to October 28, 2019. These changes were reviewed to identify components installed before June 27, 2011 that had not previously been screened or screened incorrectly for being in scope of License Renewal Aging Management. From the review, no newly identified SSCs were found . | |||
If there are any questions or if additional information is needed, please contact Ms. Pamela Johnson at 651-267-6829. | |||
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments . | |||
I certify that the information presented herein accurately presents changes made since the last updating submittal up through February 27, 2020. | |||
Scott Sharp Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (5) cc: Administrator, Region Ill , USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC}} |
Latest revision as of 23:40, 22 September 2022
ML20118D177 | |
Person / Time | |
---|---|
Site: | Prairie Island ![]() |
Issue date: | 04/27/2020 |
From: | Sharp S Xcel Energy, Northern States Power Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
Shared Package | |
MML20118D173 | List: |
References | |
L-PI-20-016 | |
Download: ML20118D177 (2) | |
Text
'{},, x~;;E~o;;;gyi~ Enclosure 3 Contains SUNSI Disclosure in Accordance with 10CFR 2.390.
R ES P O N S I B LE B V NAT U R E 1717 Wakonade Drive Welch, MN 55089 April 27, 2020 L-Pl-20-016 10 CFR 50.71(e)
U S Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos . DPR-42 and DPR-60 Updated Safety Analysis Report (USAR) Revision 36
References:
- 1) NSPM letter, S. Sharp to NRC Document Control Desk, "Changes to Technical Specification Bases, " L-Pl-18-030, dated May 18, 2018 (ADAMS Accession No. ML18155A431)
- 2) NSPM letter, S. Sharp to NRC Document Control Desk, "50.59 Evaluation Summary Report," L-Pl-17-051, dated December 28, 2017 (ADAMS Accession No ML17362A148)
- 3) NRC letter, from R. Kuntz to S. Northard, "Issuance of Amendments -
Transition to NFPA-805 "Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, dated August 8, 2017 (ADAMS Accession No. ML17163A027)
Pursuant to 10CFR 50 .71(e) and Nuclear Regulatory Commission (NRC) specific exemption granted May 22, 2006 (ADAMS Accession Number ML061110032), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM") , by this letter submits USAR, Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2.
Enclosure 1, Information Regarding Changes to the USAR, identifies those changes made based on approved license amendments , changes made under the provisions of 10 CFR 50 .59, 10 CFR 50.46, and editorial changes including deletion of particular information and the basis for that deletion.
Enclosure 2 (Non- Proprietary) and Enclosure 3 (Proprietary), Contains the Updated Safety Analysis Report (USAR) Revision 36 in its entirety. This revision was made pursuant to 10 CFR 50.71 (e), using the guidance of NEI 98-03 , Rev. 1, "Guidelines for Updating Final Safety Analysis Reports Enclosure 4, In accordance with TS 5.5.12, "Technical Specifications (TS) Bases Control Program ," contains the TS Bases for the Prai rie Island Nuclear Generating Plant, Units 1 and 2, that includes the changes to the bases from Revisions 242 through 246 that have been implemented since the previous submittal (Reference 1).
Document Control Desk Page 2 Enclosure 5, Contains a brief description and a summary of the safety evaluation for each of those changes , tests , and experiments made under the provisions of 10 CFR 50.59 during the period of January 2018 to present (Reference 2) .
NRC Safety Evaluation Report (SER) dated August 8, 2017, approved the NFPA 805 License Amendment Request (LAR) which made changes to the PINGP USAR in accordance with 10 CFR 50. 71 (e) and the exemption from 10 CFR 50.71 (e)(4) which allows periodic updates of the PINGP USAR to be submitted within C of each Unit2 refueling outage, not to exceed 24 months from the previous submittal. (Reference 3)
Consistent with the guidance in Regulatory Issue Summary {RIS) 2007-16, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses", a review of eng ineering changes, equipment list changes, USAR changes, changes to SSCs credited to 10 CFR 54.4(a)(3) regulated events, and changes to time limited aging analyses (TLAAs) was conducted for the review period from November 20, 2017 to October 28, 2019. These changes were reviewed to identify components installed before June 27, 2011 that had not previously been screened or screened incorrectly for being in scope of License Renewal Aging Management. From the review, no newly identified SSCs were found .
If there are any questions or if additional information is needed, please contact Ms. Pamela Johnson at 651-267-6829.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments .
I certify that the information presented herein accurately presents changes made since the last updating submittal up through February 27, 2020.
Scott Sharp Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (5) cc: Administrator, Region Ill , USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC