ML13046A396
| ML13046A396 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/20/2013 |
| From: | Thomas Wengert Plant Licensing Branch III |
| To: | Jeffery Lynch Northern States Power Co |
| Wengert T NRR/DORl/LPL3-1 301-415-4037 | |
| References | |
| TAC ME2609, TAC ME2610 | |
| Download: ML13046A396 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 20, 2013 Mr. James E. Lynch Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 CORRECTION TO LICENSE AND TECHNICAL SPECIFICATION PAGES INCLUDED WITH AMENDMENT NOS. 206 AND 193 REGARDING THE ADOPTION OF THE ALTERNATIVE SOURCE TERM METHODOLOGY (TAC NOS. ME2609 AND ME2610)
Dear Mr. Lynch:
By letter dated January 22, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112521289), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 206 and 193 to Renewed Facility Operating License Nos. DPR-42 and DPR-60 for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, respectively.
Following issuance of these amendments, the NRC staff was informed by a member of your staff that some errors had been inadvertently introduced into certain license pages and a technical specification page during the processing of the amendments. The specific errors are discussed below:
(1)
The last portion of paragraph 2.C.(3) of page 4 of the Unit 2 license was issued as follows (emphasis added):
NSPM shall fully implement and maintain in effect all provisions of the Commission approved Northern States Power Company - Minnesota (NSPM) Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NSPM CSP was approved by License Amendment No. 193.
Amendment No. 190 was the previous amendment affecting Unit 2 License Page 4. This amendment was issued on August 16, 2011 (ADAMS Accession No. ML111990469), and concerned the approval of a changes to the physical security plan. The affected paragraph of License Page 4 did not include the above typographical error. The affected paragraph in License Page 4 was issued as follows (emphasis added):
NSPM shall fully implement and maintain in effect all provisions of the Commission approved Northern States Power Company - Minnesota (NSPM) Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NSPM CSP was approved by License Amendment No. 189.
J. Lynch
-2 Therefore, the page is revised to restore the correct amendment number.
(2)
The last paragraph of Unit 2 Appendix B, page B-3, states the following:
The Alternative Source Term License Amendments 206/193 will be implemented after installation of the Unit 2 Replacement Steam Generators (RSGs).
However, in the preparation of this license page, the amendment numbers appear to be stricken out instead of underlined. This page is revised by removing the underline to avoid possible confusion.
(3)
The APPLICABILITY section of Technical Specifications page 3.9.4-1 states:
During movement of irradiated fuel assemblies within the reactor core.
This statement is correct. However, during processing of the page, the second line of the statement was not indented properly. This page is revised to display the correct indenting.
(4)
REMOVE/INSERT page of the Attachment to License Amendment Nos. 206 and 193:
TS page 3.4.17-3 was inadvertently omitted from the REIVIOVE/INSERT page of the Attachment to License Amendment Nos. 206 and 193. This page is revised to include TS page 3.4.17-3.
The NRC staff concludes that these typographical/editorial errors were inadvertently introduced during the preparation of the license amendments and that the errors are entirely editorial in nature.
Please find enclosed the replacement pages for Amendment Nos. 206 and 193. These corrections do not change any of the NRC staff's conclusions in the safety evaluation associated with the amendments.
If you have any questions regarding this matter, please call me at (301) 415-4037.
Sincerely,
~~
~rA Thomas J. We ert, Senior ~oject Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
As stated cc w/encl: Distribution via ListServ
ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 CORRECTED REMOVEII NSERT ATTACHMENT TO LICENSE AMENDMENT NOS. 206 (UNIT 1) AND 193 (UNIT 2)
CORRECTED UNIT 2 LICENSE PAGE 4 CORRECTED TECHNICAL SPECIFICATIONS PAGE 3.9.4-1 CORRECTED UNIT 2 LICENSE PAGE 8-3
ATTACHMENT TO LICENSE AMENDMENT NOS. 206 AND 193 RENEWED FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 Replace the following pages of the Renewed Facility Operating License Nos. DPR-42 and DPR-60 with the attached revised pages. The changed areas are identified by marginal lines.
REMOVE INSERT DPR-42, License Pages 3 and 4 DPR-42, License Pages 3 and 4 DPR-60, License Pages 3 and 4 DPR-60, License Pages 3 and 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 1.1-2 1.1-2 1.1-3 1.1-3 1.1-4 1.1-4 3.3.7-1 3.3.7-2 3.3.7-3 3.3.7-4 3.4.17-1 3.4.17-1 3.4.17-2 3.4.17-2 3.4.17-3 3.4.17-4 3.7.12-1 3.7.12-1 3.7.12-2 3.7.12-2 3.7.12-3 3.7.13-1 3.7.13-1 3.7.13-2 3.9.4-1 3.9.4-1 3.9.4-2 5.0-23 5.0-23 5.0-28 5.0-28 5.0-30 5.0-30 Replace the following pages of Appendix 8, Additional Conditions, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT DPR-42, License Page 8-3 DPR-42, License Pages 8-3 and 8-4 DPR-60, License Page 8-3 DPR-60, License Pages 8-3 and 8-4
- 4 Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," submitted by letters dated October 18, 2006 and January 10, 2007, and as supplemented by letters dated March 18 and June 2,2011, and approved by NRC Safety Evaluation dated August 16, 2011.
NSPM shall fully implement and maintain in effect all provisions of the Commission-approved Northern States Power Company - Minnesota (NSPM)
Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The NSPM CSP was approved by License Amendment No. 189.
(4)
Fire Protection NSPM shall implement and maintain in effect all provisions of the approved fire protection program as described and referenced in the Updated Safety Analysis Report for the Prairie Island Nuclear Generating Plant, Units 1 and 2, and as approved in Safety Evaluation Reports dated February 14, 1978, September 6, 1979, April 21, 1980, December 29, 1980, July 28, 1981, October 27, 1989, and October 6, 1995, subject to the following provision:
NSPM may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(5)
Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 193, are hereby incorporated into this license. NSPM shall operate the facility in accordance with the Additional Conditions.
(6)
Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a)
Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2. Assessment of mutual aid fire fighting assets
- 3. Designated staging areas for equipment and materials
- 4. Command and control
- 5. Training of response personnel (b)
Operations to mitigate fuel damage considering the following:
- 1. Protection and use of personnel assets
- 2. Communications
- 3. Minimizing fire spread
- 4. Procedures for implementing integrated fire response strategy
- 5. Identification of readily-available pre-staged equipment
- 6. Training on integrated fire response strategy
- 7. Spent fuel pool mitigation measures Renewed Operating License No. DPR-60 Amendment No. 193 Corrected by "L-PI-13-017, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS ([[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid.) - Shutdown|letter dated February 20, 2013]]
Amendment Number 149 149 193 APPENDIX 8 ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Additional Conditions The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 149 shall be as follows:
For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.
The licensee is authorized to relocate certain Technical Specification requirements previously included in Appendix A to licensee-controlled documents, as described in Table LR, "Less Restrictive Changes - Relocated Details," and Table R, "Relocated Specifications," attached to the NRC staff's safety evaluation dated July 26,2002.
Those requirements shall be relocated to the appropriate documents no later than October 31, 2002.
The Alternative Source Term license Amendments 206/193 will be implemented after installation of the Unit 2 Replacement Steam Generators (RSGs).
Implementation Date October 31.
2002 October 31, 2002 Within 90 days after completion of the outage in which the Unit 2 RSGs are installed 8-3 Amendment No. 193 Corrected by "L-PI-13-017, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS ([[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid.) - Shutdown|letter dated February 20, 2013]]
Decay Time 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Decay Time LCO 3.9.4 The reactor shall be subcritical for at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
APPUCABIUIY:
During movement of irradiated fuel assemblies within the reactor core.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor subcritical for less than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
A.l Suspend movement of irradiated fuel assemblies within the reactor core.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.9.4.1 Verify the reactor has been subcritical for at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />.
FREQUENCY Once prior to movement of irradiated fuel in the reactor core following reactor shutdown Prairie Island Unit 1 - Amendment No. -B +66 206 Units 1 and 2 3.9.4-1 Unit 2 - Amendment No. -l-49 +§6 193 Corrected by "L-PI-13-017, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS ([[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid.) - Shutdown|letter dated February 20, 2013]]
J. Lynch
- 2 Therefore, the page is revised to the restore correct amendment number.
(2)
The last paragraph of Unit 2 Appendix B, page B-3, states the following:
The Alternative Source Term License Amendments 206/193 will be implemented after installation of the Unit 2 Replacement Steam Generators (RSGs).
However, in the preparation of this license page, the amendment numbers appear to be stricken out instead of underlined. This page is revised by removing the underline to avoid possible confusion.
(3)
The APPLICABILITY section of Technical Specifications page 3.9.4-1 states:
During movement of irradiated fuel assemblies within the reactor core.
This statement is correct. However, during processing of the page, the second line of the statement was not indented properly. This page is revised to display the correct indenting.
(4)
REMOVE/INSERT page of the Attachment to License Amendment Nos. 206 and 193:
TS page 3.4.17-3 was inadvertently omitted from the REMOVEIINSERT page of the Attachment to License Amendment Nos. 206 and 193. This page is revised to include TS page 3.4.17-3.
The NRC staff concludes that these typographical/editorial errors were inadvertently introduced during the preparation of the license amendments and that the errors are entirely editorial in nature.
Please find enclosed the replacement pages for Amendment Nos. 206 and 193. These corrections do not change any of the NRC staff's conclusions in the safety evaluation associated with the amendments.
If you have any questions regarding this matter, please call me at (301) 415-4037.
Sincerely, IRA!
Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
As stated cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 r/f RidsOgcRp Resource RidsNrrDorlLpl3-1 Resource RidsNrrDorlLpl3-1 Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrPMPrairielsland Resource RecordsAmend Resource RidsNrrLASRohrer Resource ADAMS Accession Number' ML13046A396 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC NRR/LPL3-1/PM NAME TWengert SRohrer MChawla for RCarlson TWengert DATE 02/20/13 02119/13 02/20/13 02120/13 OFFICIAL RECORD COPY