ML13044A665: Difference between revisions

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| issue date = 02/13/2013
| issue date = 02/13/2013
| title = Electronic Transmission, Draft Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval
| title = Electronic Transmission, Draft Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval
| author name = Bamford P J
| author name = Bamford P
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Khanna M K
| addressee name = Khanna M
| addressee affiliation = NRC/NRR/DORL/LPLI-2
| addressee affiliation = NRC/NRR/DORL/LPLI-2
| docket = 05000289
| docket = 05000289
| license number =  
| license number =  
| contact person = Bamford P J
| contact person = Bamford P
| case reference number = TAC ME9819
| case reference number = TAC ME9819
| document type = Memoranda, Request for Additional Information (RAI)
| document type = Memoranda, Request for Additional Information (RAI)
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:February 13, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2   Division of Operating Reactor Licensing     Office of Nuclear Reactor Regulation  
{{#Wiki_filter:February 13, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:                   Peter Bamford, Project Manager /ra/
 
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
FROM:   Peter Bamford, Project Manager /ra/   Plant Licensing Branch I-2 Division of Operating Reactor Licensing     Office of Nuclear Reactor Regulation  


==SUBJECT:==
==SUBJECT:==
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL (TAC NO. ME9819)  
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL (TAC NO. ME9819)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 13, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees request proposing alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, for the Pressurizer Pilot Operated Relief Valve. The draft RAI is related to the licensees submittal dated October 18, 2012. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-289


The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 13, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review
==Enclosure:==
 
As stated
being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensee's request proposing alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, for the Pressurizer Pilot Operated Relief Valve. The draft RAI is related to the licensee's submittal dated October 18, 2012. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-289


==Enclosure:==
February 13, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:                   Peter Bamford, Project Manager /ra/
As stated February 13, 2013 MEMORANDUM TO: Meena Khanna, Chief   Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:   Peter Bamford, Project Manager /ra/   Plant Licensing Branch I-2   Division of Operating Reactor Licensing     Office of Nuclear Reactor Regulation  
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation


==SUBJECT:==
==SUBJECT:==
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE  
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL (TAC NO. ME9819)
 
The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 13, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees request proposing alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, for the Pressurizer Pilot Operated Relief Valve. The draft RAI is related to the licensees submittal dated October 18, 2012. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
TESTING INTERVAL (TAC NO. ME9819)
Docket No. 50-289
The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 13, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review  
 
being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensee's request proposing alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, for the Pressurizer Pilot Operated Relief Valve. The draft RAI is related to the licensee's submittal dated October 18, 2012. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-289  


==Enclosure:==
==Enclosure:==
As stated DISTRIBUTION
As stated DISTRIBUTION:
: Public   RidsNrrPMThreeMileIsland Resource LPL1-2 R/F Accession No.: ML13044A665
Public                 RidsNrrPMThreeMileIsland Resource                     LPL1-2 R/F Accession No.: ML13044A665
* via email OFFICE LPL1-2/PM EPTB/BC NAME PBamfordAMcMurtray*
* via email OFFICE       LPL1-2/PM           EPTB/BC NAME         PBamford            AMcMurtray*
DATE 02/13/13 02/12/13 OFFICIAL RECORD COPY Enclosure REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL DOCKET NO. 50-289
DATE         02/13/13             02/12/13 OFFICIAL RECORD COPY
 
By letter dated October 18, 2012 (Agencywide Documents Access and Management System Accession No. ML12292A585), Exelon Generation Company, LLC (Exelon, the licensee) submitted a relief request, VR-01, associated with the fifth Inservice Testing (IST) interval at Three Mile Island Nuclear Station, Unit 1 (TMI-1). The request proposes alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the Pressurizer Pilot Operated Relief Valve (POR V). The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed
 
to complete its review. 


1.) The PORV, 1-RC-RV-2, is categorized as a B/C valve in the referenced request. In addition to the requirements of the OM Code, ISTC-3310 and ISTC-3510 (for which relief is being requested), are any other ASME OM Code ISTC or Mandatory Appendix I test requirements applicable to this valve? Please provide any specific ASME OM Code test requirements for this valve type, but don't provide general test requirements from the OM Code. 2.) Is the Pressurizer PORV block valve included in the TMI-1 IST program? If not, please provide the basis for not including this valve in the program.}}
REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL DOCKET NO. 50-289 By letter dated October 18, 2012 (Agencywide Documents Access and Management System Accession No. ML12292A585), Exelon Generation Company, LLC (Exelon, the licensee) submitted a relief request, VR-01, associated with the fifth Inservice Testing (IST) interval at Three Mile Island Nuclear Station, Unit 1 (TMI-1). The request proposes alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the Pressurizer Pilot Operated Relief Valve (PORV). The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
1.)     The PORV, 1-RC-RV-2, is categorized as a B/C valve in the referenced request. In addition to the requirements of the OM Code, ISTC-3310 and ISTC-3510 (for which relief is being requested), are any other ASME OM Code ISTC or Mandatory Appendix I test requirements applicable to this valve? Please provide any specific ASME OM Code test requirements for this valve type, but dont provide general test requirements from the OM Code.
2.)     Is the Pressurizer PORV block valve included in the TMI-1 IST program? If not, please provide the basis for not including this valve in the program.
Enclosure}}

Latest revision as of 23:10, 4 November 2019

Electronic Transmission, Draft Request for Additional Information Regarding Relief Request VR-01, Associated with the Fifth Inservice Testing Interval
ML13044A665
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 02/13/2013
From: Peter Bamford
Plant Licensing Branch 1
To: Meena Khanna
Plant Licensing Branch 1
Bamford P
References
TAC ME9819
Download: ML13044A665 (3)


Text

February 13, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL (TAC NO. ME9819)

The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 13, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees request proposing alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, for the Pressurizer Pilot Operated Relief Valve. The draft RAI is related to the licensees submittal dated October 18, 2012. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.

Docket No. 50-289

Enclosure:

As stated

February 13, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Peter Bamford, Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL (TAC NO. ME9819)

The attached draft request for additional information (RAI) was transmitted by electronic transmission on February 13, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees request proposing alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, for the Pressurizer Pilot Operated Relief Valve. The draft RAI is related to the licensees submittal dated October 18, 2012. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.

Docket No. 50-289

Enclosure:

As stated DISTRIBUTION:

Public RidsNrrPMThreeMileIsland Resource LPL1-2 R/F Accession No.: ML13044A665

  • via email OFFICE LPL1-2/PM EPTB/BC NAME PBamford AMcMurtray*

DATE 02/13/13 02/12/13 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 RELIEF REQUEST VR-01, ASSOCIATED WITH THE FIFTH INSERVICE TESTING INTERVAL DOCKET NO. 50-289 By letter dated October 18, 2012 (Agencywide Documents Access and Management System Accession No. ML12292A585), Exelon Generation Company, LLC (Exelon, the licensee) submitted a relief request, VR-01, associated with the fifth Inservice Testing (IST) interval at Three Mile Island Nuclear Station, Unit 1 (TMI-1). The request proposes alternative testing, as compared to the requirements of the applicable American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), for the Pressurizer Pilot Operated Relief Valve (PORV). The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review.

1.) The PORV, 1-RC-RV-2, is categorized as a B/C valve in the referenced request. In addition to the requirements of the OM Code, ISTC-3310 and ISTC-3510 (for which relief is being requested), are any other ASME OM Code ISTC or Mandatory Appendix I test requirements applicable to this valve? Please provide any specific ASME OM Code test requirements for this valve type, but dont provide general test requirements from the OM Code.

2.) Is the Pressurizer PORV block valve included in the TMI-1 IST program? If not, please provide the basis for not including this valve in the program.

Enclosure