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| number = ML16148A179
| number = ML16148A179
| issue date = 06/21/2016
| issue date = 06/21/2016
| title = Prairie Island Nuclear Generating Plant, Units 1 and 2 - Correction Letter for Amendments 185 and 175 to Renewed Facility Operating Licenses (CAC Nos. MD5983 and MD5984)
| title = Correction Letter for Amendments 185 and 175 to Renewed Facility Operating Licenses
| author name = Kuntz R F
| author name = Kuntz R
| author affiliation = NRC/NRR/DORL/LPLIII-1
| author affiliation = NRC/NRR/DORL/LPLIII-1
| addressee name = Northard S D
| addressee name = Northard S
| addressee affiliation = Northern States Power Company, Minnesota
| addressee affiliation = Northern States Power Company, Minnesota
| docket = 05000282, 05000306
| docket = 05000282, 05000306
| license number = DPR-042, DPR-060
| license number = DPR-042, DPR-060
| contact person = Kuntz R F
| contact person = Kuntz R
| case reference number = CAC MD5983, CAC MD5984
| case reference number = CAC MD5983, CAC MD5984
| document type = Letter
| document type = Letter
| page count = 5
| page count = 5
| project = CAC:MD5983, CAC:MD5984
| project = CAC:MD5983, CAC:MD5984
| stage =  
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:Mr. Scott D. Northard Acting Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 21, 2016 Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota 1717 Wakonade Drive East Welch, MN 55089 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -CORRECTION LETTER FOR AMENDMENTS 185 AND 175 TO RENEWED FACILITY OPERATING LICENSES (CAC NOS. MD5983 AND MD5984) Dear Mr. Davison: On June 27, 2008, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 185 to Renewed Facility Operating License No. DPR-42 and Amendment No. 175 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081650272). The amendments consisted of changes to the technical specification (TSs) regarding incorporation of Technical Specification Task Force (TSTF) industry travelers TSTF-479, -485, and -497. The amendments revised the wording for TS 5.5.7, "lnservice Testing Program," on page 5.0-12. The amendments did not revise any wording for the TSs on page 5.0-11; however, in the course of issuing the revised TS pages, the word "year" was inadvertently removed from the last sentence in TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," on page 5.0-11: " ... of exposed surfaces of the removed flywheels may be conducted at 20 year intervals." This letter corrects Amendment Nos. 185 and 175 to restore TS 5.5.6 to the wording as approved in Amendment Nos. 170 and 160 when the inspection interval for TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," was increased from 10 years to 20 years (ADAMS Accession No. ML051510045). The NRC staff concludes that the error was introduced during the preparation of the license amendments and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendments referenced above and does not affect the associated notices to the public. Enclosed, please find the corrected replacement page.
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 21, 2016 Mr. Scott D. Northard Acting Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089
K. Davison -2 -If you have any questions regarding this matter, please call me at (301) 415-3733. Sincerely, Robert F. Kuntz, nior Project Manager Plant Licensin ranch 111-1 Division of erating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 Enclosure: Corrected Page to Amendment No. 185 to DPR-42 and Amendment No. 175 to DPR-60 cc w/encl: Distribution via ListServ ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 CORRECTED PAGE TO LICENSE AMENDMENT NOS. 185 AND 175 RENEWED FACILITY OPERATING LICENSE NO. DPR-42 RENEWED FACILITY OPERATING LICENSE NO. DPR-60 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued) J. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency. 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 4.1.4, cyclic and transient occurrences to ensure that components are maintained within the design limits. 5.5.6 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. In lieu of Position C.4.b(l) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals. 5.5.7 Inservice Testing Program Prairie Island Units 1 and 2 This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following: Unit 1 -Amendment -l-1Q 185 5.0-11 Unit 2 -Amendment No . .f.49-1-e-O 175 Corrected by letter dated June 21, 2016 K. Davison -2 -If you have any questions regarding this matter, please call me at (301) 415-3733. Docket Nos. 50-282 and 50-306 Enclosure: Sincerely, IRA/ Robert F. Kuntz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Corrected Page to Amendment No. 185 to DPR-42 and Amendment No. 175 to DPR-60 cc w/encl: Distribution via ListServ DISTRIBUTION: PUBLIC LPL3-1 r/f RidsNrrDorllpl3-1 Resource RidsNrrPMPrairielsland Resource RidsNrrLASRohrer Resource ADAMS Accession No.: ML16148A179 OFFICE DORULPL3-1 /PM DORULPL3-1 /LA NAME RKuntz SRohrer DATE 5/31/16 5/31/16 RidsOgcRp Resource RidsACRS_MailCTR Resource RidsNrrDssStsb Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource DORULPL3-1 /BC DORULPL3-1 /PM DWrona RKuntz 6/21/16 6/21/16 OFFICIAL RECORD COPY 
 
}}
==SUBJECT:==
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
CORRECTION LETTER FOR AMENDMENTS 185 AND 175 TO RENEWED FACILITY OPERATING LICENSES (CAC NOS. MD5983 AND MD5984)
 
==Dear Mr. Davison:==
 
On June 27, 2008, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 185 to Renewed Facility Operating License No. DPR-42 and Amendment No. 175 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081650272). The amendments consisted of changes to the technical specification (TSs) regarding incorporation of Technical Specification Task Force (TSTF) industry travelers TSTF-479, -485, and -497.
The amendments revised the wording for TS 5.5.7, "lnservice Testing Program," on page 5.0-12. The amendments did not revise any wording for the TSs on page 5.0-11; however, in the course of issuing the revised TS pages, the word "year" was inadvertently removed from the last sentence in TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," on page 5.0-11: " ... of exposed surfaces of the removed flywheels may be conducted at 20 year intervals."
This letter corrects Amendment Nos. 185 and 175 to restore TS 5.5.6 to the wording as approved in Amendment Nos. 170 and 160 when the inspection interval for TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," was increased from 10 years to 20 years (ADAMS Accession No. ML051510045).
The NRC staff concludes that the error was introduced during the preparation of the license amendments and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendments referenced above and does not affect the associated notices to the public. Enclosed, please find the corrected replacement page.
 
K. Davison                               If you have any questions regarding this matter, please call me at (301) 415-3733.
Sincerely, Robert F. Kuntz,     nior Project Manager Plant Licensin   ranch 111-1 Division of   erating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
 
==Enclosure:==
 
Corrected Page to Amendment No. 185 to DPR-42 and Amendment No. 175 to DPR-60 cc w/encl: Distribution via ListServ
 
ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 CORRECTED PAGE TO LICENSE AMENDMENT NOS. 185 AND 175 RENEWED FACILITY OPERATING LICENSE NO. DPR-42 RENEWED FACILITY OPERATING LICENSE NO. DPR-60
 
Programs and Manuals 5.5 5.5     Programs and Manuals 5.5.4         Radioactive Effluent Controls Program (continued)
J. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
5.5.5         Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 4.1.4, cyclic and transient occurrences to ensure that components are maintained within the design limits.
5.5.6         Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. In lieu of Position C.4.b(l) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.
5.5.7         Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:
Prairie Island                                        Unit 1 - Amendment No.~ -l-1Q 185 Units 1 and 2                            5.0-11     Unit 2 - Amendment No . .f.49-1-e-O 175 Corrected by letter dated June 21, 2016
 
ML16148A179 OFFICE      DORULPL3-1 /PM      DORULPL3-1 /LA      DORULPL3-1 /BC      DORULPL3-1 /PM NAME       RKuntz               SRohrer             DWrona              RKuntz DATE         5/31/16             5/31/16             6/21/16               6/21/16}}

Latest revision as of 02:12, 19 March 2020

Correction Letter for Amendments 185 and 175 to Renewed Facility Operating Licenses
ML16148A179
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/21/2016
From: Robert Kuntz
Plant Licensing Branch III
To: Northard S
Northern States Power Company, Minnesota
Kuntz R
References
CAC MD5983, CAC MD5984
Download: ML16148A179 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 21, 2016 Mr. Scott D. Northard Acting Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

CORRECTION LETTER FOR AMENDMENTS 185 AND 175 TO RENEWED FACILITY OPERATING LICENSES (CAC NOS. MD5983 AND MD5984)

Dear Mr. Davison:

On June 27, 2008, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 185 to Renewed Facility Operating License No. DPR-42 and Amendment No. 175 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081650272). The amendments consisted of changes to the technical specification (TSs) regarding incorporation of Technical Specification Task Force (TSTF) industry travelers TSTF-479, -485, and -497.

The amendments revised the wording for TS 5.5.7, "lnservice Testing Program," on page 5.0-12. The amendments did not revise any wording for the TSs on page 5.0-11; however, in the course of issuing the revised TS pages, the word "year" was inadvertently removed from the last sentence in TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," on page 5.0-11: " ... of exposed surfaces of the removed flywheels may be conducted at 20 year intervals."

This letter corrects Amendment Nos. 185 and 175 to restore TS 5.5.6 to the wording as approved in Amendment Nos. 170 and 160 when the inspection interval for TS 5.5.6, "Reactor Coolant Pump Flywheel Inspection Program," was increased from 10 years to 20 years (ADAMS Accession No. ML051510045).

The NRC staff concludes that the error was introduced during the preparation of the license amendments and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendments referenced above and does not affect the associated notices to the public. Enclosed, please find the corrected replacement page.

K. Davison If you have any questions regarding this matter, please call me at (301) 415-3733.

Sincerely, Robert F. Kuntz, nior Project Manager Plant Licensin ranch 111-1 Division of erating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Corrected Page to Amendment No. 185 to DPR-42 and Amendment No. 175 to DPR-60 cc w/encl: Distribution via ListServ

ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 CORRECTED PAGE TO LICENSE AMENDMENT NOS. 185 AND 175 RENEWED FACILITY OPERATING LICENSE NO. DPR-42 RENEWED FACILITY OPERATING LICENSE NO. DPR-60

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

J. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 4.1.4, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. In lieu of Position C.4.b(l) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.

5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

Prairie Island Unit 1 - Amendment No.~ -l-1Q 185 Units 1 and 2 5.0-11 Unit 2 - Amendment No . .f.49-1-e-O 175 Corrected by letter dated June 21, 2016

ML16148A179 OFFICE DORULPL3-1 /PM DORULPL3-1 /LA DORULPL3-1 /BC DORULPL3-1 /PM NAME RKuntz SRohrer DWrona RKuntz DATE 5/31/16 5/31/16 6/21/16 6/21/16

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