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| author name = Kuntz R | | author name = Kuntz R | ||
| author affiliation = NRC/NRR/DORL/LPLIII | | author affiliation = NRC/NRR/DORL/LPLIII | ||
| addressee name = Northard S | | addressee name = Northard S | ||
| addressee affiliation = Northern States Power Co | | addressee affiliation = Northern States Power Co | ||
| docket = 05000282, 05000306 | | docket = 05000282, 05000306 | ||
| license number = DPR-042, DPR-060 | | license number = DPR-042, DPR-060 | ||
| contact person = Kuntz R | | contact person = Kuntz R 415-3733 | ||
| case reference number = CAC ME9735 | | case reference number = CAC ME9735 | ||
| document type = Letter | | document type = Letter | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 Ma. y 1 4 , | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ma. y 1 4 , 2019 Mr. Scott D. Northard Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089 | ||
==SUBJECT:== | ==SUBJECT:== | ||
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -CORRECTION LETTER FOR AMENDMENT 207 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-60 (CAC NO. ME9735) | PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - | ||
CORRECTION LETTER FOR AMENDMENT 207 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-60 (CAC NO. ME9735) | |||
==Dear Mr. Northard:== | ==Dear Mr. Northard:== | ||
On August 8, 2017, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 220 to Renewed Facility Operating License No. DPR-42 and Amendment No. 207 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. | On August 8, 2017, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 220 to Renewed Facility Operating License No. DPR-42 and Amendment No. | ||
The amendments revised the licenses, including the technical specifications, for Prairie Island Nuclear Generating Plant Units, 1 and 2, to establish and maintain fire protection program in accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.48(c). | 207 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17163A027). The amendments revised the licenses, including the technical specifications, for Prairie Island Nuclear Generating Plant Units, 1 and 2, to establish and maintain fire protection program in accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.48(c). | ||
This letter corrects Amendment No. 207 to license No. DPR-60 to issue page 3 of the amendment (Enclosure 2 to the August 8, 2017 letter) which had been inadvertently omitted. If you have any questions regarding this matter, please call me at (301) 415-3733. | This letter corrects Amendment No. 207 to license No. DPR-60 to issue page 3 of the amendment (Enclosure 2 to the August 8, 2017 letter) which had been inadvertently omitted. | ||
Docket No. 50-306 | If you have any questions regarding this matter, please call me at (301) 415-3733. | ||
Robert F. Kun Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-306 | |||
==Enclosures:== | ==Enclosures:== | ||
: 2. Page 3 of Amendment No. 207 to DPR-60 cc: Listserv | : 2. Page 3 of Amendment No. 207 to DPR-60 cc: Listserv | ||
ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 2 FACILITY OPERATING LICENSE DPR-60 DOCKET NO. 50-306 AMENDMENT NO. 207 AMENDMENT PAGE 3 | |||
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, | |||
must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation. | |||
(b) Other Changes that May be Made Without Prior NRC Approval | |||
: 1. Changes to NFPA 805, Chapter 3, Fundamental Fire Protection Program Prior NRC review and approval are not required for changes to the NFPA 805, Chapter 3, fundamental fire protection program elements and design requirements for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is functionally equivalent or adequate for the hazard. The licensee may use an engineering evaluation to demonstrate that a change to an NFPA 805, Chapter 3, element is functionally equivalent to the corresponding technical requirement. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard. | |||
The licensee may use an engineering evaluation to demonstrate that changes to certain NFPA 805, Chapter 3, elements are acceptable because the alternative is "adequate for the hazard." | |||
Prior NRC review and approval would not be required for alternatives to four specific sections of NFPA 805, Chapter 3, for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is adequate for the hazard . A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard. The four specific sections of NFPA 805, Chapter 3, are as follows: | |||
* "Fire Alarm and Detection Systems" (Section 3.8); | |||
* "Automatic and Manual Water-Based Fire Suppression Systems" (Section 3.9); | |||
* "Gaseous Fire Suppression Systems" (Section 3.1 O); and | |||
* "Passive Fire Protection Features" (Section 3.11 ). | |||
This License Condition does not apply to any demonstration of equivalency under Section 1.7 of NFPA 805. | |||
: 2. Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRC review and approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process as approved in the NRC safety evaluation | |||
ML19126A292 OFFICE NRR/D0RL/LPL3/PM NRR/D0RL/LPL3/LA NRR/D0RL/LPL3/BC NRR/D0RL/LPL3/PM NAME RKuntz SRohrer DWrona RKuntz DATE 05/07/19 05/07/19 05/14/19 05/14/19}} | |||
Latest revision as of 19:24, 19 October 2019
| ML19126A292 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/14/2019 |
| From: | Robert Kuntz Plant Licensing Branch III |
| To: | Northard S Northern States Power Co |
| Kuntz R 415-3733 | |
| References | |
| CAC ME9735 | |
| Download: ML19126A292 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ma. y 1 4 , 2019 Mr. Scott D. Northard 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 AMENDMENT 207 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-60 (CAC NO. ME9735)
Dear Mr. Northard:
On August 8, 2017, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 220 to Renewed Facility Operating License No. DPR-42 and Amendment No.
207 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17163A027). The amendments revised the licenses, including the technical specifications, for Prairie Island Nuclear Generating Plant Units, 1 and 2, to establish and maintain fire protection program in accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.48(c).
This letter corrects Amendment No. 207 to license No. DPR-60 to issue page 3 of the amendment (Enclosure 2 to the August 8, 2017 letter) which had been inadvertently omitted.
If you have any questions regarding this matter, please call me at (301) 415-3733.
Robert F. Kun Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-306
Enclosures:
- 2. Page 3 of Amendment No. 207 to DPR-60 cc: Listserv
ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 2 FACILITY OPERATING LICENSE DPR-60 DOCKET NO. 50-306 AMENDMENT NO. 207 AMENDMENT PAGE 3
must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.
(b) Other Changes that May be Made Without Prior NRC Approval
- 1. Changes to NFPA 805, Chapter 3, Fundamental Fire Protection Program Prior NRC review and approval are not required for changes to the NFPA 805, Chapter 3, fundamental fire protection program elements and design requirements for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is functionally equivalent or adequate for the hazard. The licensee may use an engineering evaluation to demonstrate that a change to an NFPA 805, Chapter 3, element is functionally equivalent to the corresponding technical requirement. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard.
The licensee may use an engineering evaluation to demonstrate that changes to certain NFPA 805, Chapter 3, elements are acceptable because the alternative is "adequate for the hazard."
Prior NRC review and approval would not be required for alternatives to four specific sections of NFPA 805, Chapter 3, for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is adequate for the hazard . A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard. The four specific sections of NFPA 805, Chapter 3, are as follows:
- "Fire Alarm and Detection Systems" (Section 3.8);
- "Automatic and Manual Water-Based Fire Suppression Systems" (Section 3.9);
- "Gaseous Fire Suppression Systems" (Section 3.1 O); and
- "Passive Fire Protection Features" (Section 3.11 ).
This License Condition does not apply to any demonstration of equivalency under Section 1.7 of NFPA 805.
- 2. Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRC review and approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process as approved in the NRC safety evaluation
ML19126A292 OFFICE NRR/D0RL/LPL3/PM NRR/D0RL/LPL3/LA NRR/D0RL/LPL3/BC NRR/D0RL/LPL3/PM NAME RKuntz SRohrer DWrona RKuntz DATE 05/07/19 05/07/19 05/14/19 05/14/19