ML112550357: Difference between revisions

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| document type = Request for Additional Information (RAI)
| document type = Request for Additional Information (RAI)
| page count = 1
| page count = 1
| project = TAC:ME2610, TAC:ME2609
| project = TAC:ME2609, TAC:ME2610
| stage = Draft RAI
| stage = Draft RAI
}}
}}


=Text=
=Text=
{{#Wiki_filter: REQUEST FOR ADDITIONAL INFORMATION FOR CHANGES RELATED TO ADOPTION OF ALTERNATIVE SOURCE TERM PRAIRIE ISLAND NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306  By letter dated October 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093160583), supplemented by letters including those dated June 22, 2011, and August 9, 2011, (ADAMS Accession Nos. ML111740145 and ML112220098, respectively), Northern States Power Company, a Minnesota corporation (the licensee) requested Technical Specifications changes related to adoption of an Alternative Source Term Methodology for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. In response to the Nuclear Regulatory Commission (NRC) staff requests for additional information (RAIs), the licensee, by letters dated June 22, 2011 and August 9, 2011, provided a list of instrumentation required to cope with a Steam Generator Tube Rupture (SGTR) event. The NRC staff has reviewed these responses and requests further clarification regarding the classification of these instrument loops as they relate to the criteria in Regulatory Guide (RG) 1.97, Revision 2. The PINGP Updated Safety Analysis Report (USAR) Tables 7.10-1 and 7.10-2 identifies the RG 1.97, Rev. 2 variables applicable to Units 1 and 2 respectively, which have been previously reviewed and approved by the NRC in various safety evaluations. Please revise the previously docketed list of instrumentation (i.e., instrument loops) credited for coping with a SGTR and indicate which instrument loops are contained within these USAR tables. Also, if any instrument loops credited for a SGTR are not contained within the USAR Tables 7.10-1 and 7.10-2, please indicate the specific Plant Variable Type and Design and Qualification Category applicable to these instrument loops, as specified in RG 1.97, Rev. 2. This instrumentation is relied upon by the operators during accident situations, therefore the NRC staff expects these instruments to be incorporated into PINGP's RG 1.97 Post Accident Monitoring Instrumentation commitments, and documented in the USAR as appropriate. Please include a marked-up copy of the USAR documenting these new instrument loops as RG 1.97, Rev. 2 instrumentation.  
{{#Wiki_filter:REQUEST FOR ADDITIONAL INFORMATION FOR CHANGES RELATED TO ADOPTION OF ALTERNATIVE SOURCE TERM PRAIRIE ISLAND NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50
}}
-282 AND 50
-306  By letter dated October 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No.
ML093160583), supplemented by letters including those dated June 22, 2011, and August 9, 2011, (ADAMS Accession Nos. ML111740145 and ML112220098 , respectively), Northern States Power Company, a Minnesota corporation (t he licensee) requested Technical Specifications changes related to adoption of an Alternative Source Term Methodology for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2.
In response to the Nuclear Regulatory Commission (NRC) staff requests for additional information (RAIs), the licensee, by letters dated June 22, 2011 and August 9, 2011, provided a list of instrumentation required to cope with a Steam Generator Tube Rupture (SGTR) event. The NRC staff has reviewed these responses and requests further clarification regarding the classification of these instrument loops as they relate to the criteria in Regulatory Guide (RG) 1.97, Revision 2.
The PINGP Updated Safety Analysis Report (USAR)
Tables 7.10
-1 and 7.10
-2 identifies the RG 1.97, Rev. 2 variables applicable to Units 1 and 2 respectively, which have been previously reviewed and approved by the NRC in various safety evaluations. Please revise the previously docketed list of instrumentation (i.e., instrument loops) credited for coping with a SGTR and indicate which instrument loops are contained within these USAR tables. Also, if any instrument loops credited for a SGTR are not contained within the USAR Tables 7.10-1 and 7.10
-2, please indicate the specific Plant Variable Type and Design and Qualification Category applicable to these instrument loops, as specified in RG 1.97, Rev.
: 2. This instrumentation is relied upon by the operators during accident situations, therefore the NRC staff expects these instruments to be incorporated into PINGP's RG 1.97 Post Accident Monitoring Instrumentation commitments, and documented in the USAR as appropriate.
Please include a marked
-up copy of the USAR documenting these new instrument loops as RG 1.97, Rev. 2 instrumentation.}}

Revision as of 06:25, 3 August 2018

PINGP Draft RAI - AST Instrumentation
ML112550357
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 09/01/2011
From: Wengert T J
Plant Licensing Branch III
To: Myers G R
Northern States Power Co
Wengert T J
Shared Package
ML112550367 List:
References
TAC ME2609, TAC ME2610
Download: ML112550357 (1)
v • d • e


Text

REQUEST FOR ADDITIONAL INFORMATION FOR CHANGES RELATED TO ADOPTION OF ALTERNATIVE SOURCE TERM PRAIRIE ISLAND NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50

-282 AND 50

-306 By letter dated October 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No.

ML093160583), supplemented by letters including those dated June 22, 2011, and August 9, 2011, (ADAMS Accession Nos. ML111740145 and ML112220098 , respectively), Northern States Power Company, a Minnesota corporation (t he licensee) requested Technical Specifications changes related to adoption of an Alternative Source Term Methodology for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2.

In response to the Nuclear Regulatory Commission (NRC) staff requests for additional information (RAIs), the licensee, by letters dated June 22, 2011 and August 9, 2011, provided a list of instrumentation required to cope with a Steam Generator Tube Rupture (SGTR) event. The NRC staff has reviewed these responses and requests further clarification regarding the classification of these instrument loops as they relate to the criteria in Regulatory Guide (RG) 1.97, Revision 2.

The PINGP Updated Safety Analysis Report (USAR)

Tables 7.10

-1 and 7.10

-2 identifies the RG 1.97, Rev. 2 variables applicable to Units 1 and 2 respectively, which have been previously reviewed and approved by the NRC in various safety evaluations. Please revise the previously docketed list of instrumentation (i.e., instrument loops) credited for coping with a SGTR and indicate which instrument loops are contained within these USAR tables. Also, if any instrument loops credited for a SGTR are not contained within the USAR Tables 7.10-1 and 7.10

-2, please indicate the specific Plant Variable Type and Design and Qualification Category applicable to these instrument loops, as specified in RG 1.97, Rev.

2. This instrumentation is relied upon by the operators during accident situations, therefore the NRC staff expects these instruments to be incorporated into PINGP's RG 1.97 Post Accident Monitoring Instrumentation commitments, and documented in the USAR as appropriate.

Please include a marked

-up copy of the USAR documenting these new instrument loops as RG 1.97, Rev. 2 instrumentation.

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