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| number = ML13119A155
| number = ML13119A155
| issue date = 05/09/2013
| issue date = 05/09/2013
| title = Prairie Island Nuclear Generating Plant, Units 1 and 2 - Request for Additional Information Related to License Amendment Request to Revise Emergency Plan Emergency Action Levels RA1.2 and Fuel Clad Barrier Loss Criteria
| title = Request for Additional Information Related to License Amendment Request to Revise Emergency Plan Emergency Action Levels RA1.2 and Fuel Clad Barrier Loss Criteria
| author name = Wengert T J
| author name = Wengert T
| author affiliation = NRC/NRR/DORL/LPLIII-1
| author affiliation = NRC/NRR/DORL/LPLIII-1
| addressee name = Lynch J E
| addressee name = Lynch J
| 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 = Wengert T J
| contact person = Wengert T
| case reference number = TAC MF0379, TAC MF0380
| case reference number = TAC MF0379, TAC MF0380
| document type = Request for Additional Information (RAI), Letter
| document type = Request for Additional Information (RAI), Letter
| page count = 4
| page count = 4
| project = TAC:MF0379, TAC:MF0380
| stage = RAI
}}
}}
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Hay 9, 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 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE EMERGENCY PLAN EMERGENCY ACTION LEVELS RA1.2 AND FUEL CLAD BARRIER LOSS CRITERIA (TAC NOS. MF0379 AND MF0380)
==Dear Mr. Lynch:==
By letter dated December 13, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12349A362), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, submitted a license amendment request (LAR) for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The LAR requests changes to the PINGP Emergency Plan to revise emergency action level (EAL) RA1.2 and a Fuel Clad Barrier Loss criterion.
The Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. Mr. Dale Vincent of your staff agreed that you would provide a response to this request within 30 days of the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure that sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
J. Lynch                                    -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely,
                                          ~I~~~~
Thomas J. Wengert, Senior    ~ject Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
==Enclosure:==
Request for Additional Information cc w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated December 13,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12349A362), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, submitted a license amendment request (LAR) for the Prairie Island Nuclear Generating Plant, Units 1 and 2. The LAR requests to revise emergency action level (EAL) RA 1.2 to a value that is within the indicating range of radiation monitor R-18 and to remove an EAL for Fuel Clad Barrier Loss based on a Reactor Coolant System letdown line radiation monitor. To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following additional information.
: 1.      A change bar exists to the right of the row for 1(2) R-50 High Range Stack Gas Monitor on Table R-1. Is it intended that the NRC review and approve this entry? It is not described in the license amendment request.
: 2.      Explain the purpose of the OR statement in RA1.1 and why it is needed when Table R-1 includes R-18 with a value of 900,000 counts per minute.
: 3.      Explain the difference between RA 1.1 and RA 1.2. Are there monitors addressed in RA1.1 that do not appear in table R-1.2? Is it possible to meet only one of these EALs without meeting the other?
: 4.      Please add clarification to the basis document for the 900,000 setpoint for the R-18 radiation monitor inconsistency from the Initiating Condition language (60 times vs.
200 times the Offsite Dose Calculation Manual specification).
: 5.      Note 1 on Table R-1 was added in June 2008 with no explanation in the Technical Bases. Explain how this note will not cause excessive delay in EAL classification if the setpoints on Table R-1 are exceeded, or remove this note.
: 6.      Explain how Note 2 on Table R-1 applies to the gaseous monitors, or remove the asterisks.
Enclosure
J. Lynch                                    -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, IRAI 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:==
Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC          LPL3-1 RtF              RidsNrrDorlLpl3-1 Resource RidsNrrPMPrairielsland Resource          RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource            RidsNsirDprDdep Resource RidsRgn3MailCenter Resource              MWasem, NSIR RidsNrrDorlDpr Resource                  DJohnson, NSIR ADAMS Accession Number: ML13119A155 OFFICE      NRRlLPL3-lIPM    NRRlLPL3-1/LA  NSIRlDPRlDDEP/BC  NRRlDORLlLPL3-lIBC  NRRlLPL3-lIPM
~E          TWengert          SRohrer        JAnderson          RCarlson            TWengert ATE        05/01/13          05/01113      05/02/13          05/09/13            05/09/13 OFFICIAL RECORD COpy}}

Latest revision as of 20:10, 4 November 2019

Request for Additional Information Related to License Amendment Request to Revise Emergency Plan Emergency Action Levels RA1.2 and Fuel Clad Barrier Loss Criteria
ML13119A155
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 05/09/2013
From: Thomas Wengert
Plant Licensing Branch III
To: Jeffery Lynch
Northern States Power Co
Wengert T
References
TAC MF0379, TAC MF0380
Download: ML13119A155 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Hay 9, 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 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE EMERGENCY PLAN EMERGENCY ACTION LEVELS RA1.2 AND FUEL CLAD BARRIER LOSS CRITERIA (TAC NOS. MF0379 AND MF0380)

Dear Mr. Lynch:

By letter dated December 13, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12349A362), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, submitted a license amendment request (LAR) for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The LAR requests changes to the PINGP Emergency Plan to revise emergency action level (EAL) RA1.2 and a Fuel Clad Barrier Loss criterion.

The Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. Mr. Dale Vincent of your staff agreed that you would provide a response to this request within 30 days of the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure that sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.

J. Lynch -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.

Sincerely,

~I~~~~

Thomas J. Wengert, Senior ~ject Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated December 13,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12349A362), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, submitted a license amendment request (LAR) for the Prairie Island Nuclear Generating Plant, Units 1 and 2. The LAR requests to revise emergency action level (EAL) RA 1.2 to a value that is within the indicating range of radiation monitor R-18 and to remove an EAL for Fuel Clad Barrier Loss based on a Reactor Coolant System letdown line radiation monitor. To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following additional information.

1. A change bar exists to the right of the row for 1(2) R-50 High Range Stack Gas Monitor on Table R-1. Is it intended that the NRC review and approve this entry? It is not described in the license amendment request.
2. Explain the purpose of the OR statement in RA1.1 and why it is needed when Table R-1 includes R-18 with a value of 900,000 counts per minute.
3. Explain the difference between RA 1.1 and RA 1.2. Are there monitors addressed in RA1.1 that do not appear in table R-1.2? Is it possible to meet only one of these EALs without meeting the other?
4. Please add clarification to the basis document for the 900,000 setpoint for the R-18 radiation monitor inconsistency from the Initiating Condition language (60 times vs.

200 times the Offsite Dose Calculation Manual specification).

5. Note 1 on Table R-1 was added in June 2008 with no explanation in the Technical Bases. Explain how this note will not cause excessive delay in EAL classification if the setpoints on Table R-1 are exceeded, or remove this note.
6. Explain how Note 2 on Table R-1 applies to the gaseous monitors, or remove the asterisks.

Enclosure

J. Lynch -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.

Sincerely, IRAI 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:

Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:

PUBLIC LPL3-1 RtF RidsNrrDorlLpl3-1 Resource RidsNrrPMPrairielsland Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsNsirDprDdep Resource RidsRgn3MailCenter Resource MWasem, NSIR RidsNrrDorlDpr Resource DJohnson, NSIR ADAMS Accession Number: ML13119A155 OFFICE NRRlLPL3-lIPM NRRlLPL3-1/LA NSIRlDPRlDDEP/BC NRRlDORLlLPL3-lIBC NRRlLPL3-lIPM

~E TWengert SRohrer JAnderson RCarlson TWengert ATE 05/01/13 05/01113 05/02/13 05/09/13 05/09/13 OFFICIAL RECORD COpy

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