ML063110263: Difference between revisions
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{{#Wiki_filter:November 14, | {{#Wiki_filter:November 14, 2006 Mr. Anthony R. Pietrangelo Nuclear Energy Institute 1776 I Street, NW , Suite 400 Washington DC, 20006-3708 | ||
==SUBJECT:== | ==SUBJECT:== | ||
NUCLEAR REGULATORY COMMISSION REQUEST FOR | NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONAL INFORMATION TO PRESSURIZED WATER REACTOR LICENSEES REGARDING RESPONSES TO GENERIC LETTER 2004-02 | ||
==Dear Mr. Pietrangelo:== | ==Dear Mr. Pietrangelo:== | ||
This letter supplements our letter of March 3, 2006, on the same subject. In that letter, | This letter supplements our letter of March 3, 2006, on the same subject. In that letter, the Nuclear Regulatory Commission (NRC) accepted your proposed alternative approach and timetable for licensees to respond to the requests for additional information (RAIs) resulting from the NRCs review of the pressurized water reactor (PWR) licensees responses to Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors. Our March 3, 2006, letter stated the NRCs expectation that units completing their outage to incorporate strainer modifications in 2006 would provide to the NRC the information needed to fully address GL 2004-02 by December 31, 2006. For units installing strainers after 2006, information needed to fully address GL 2004-02 would be provided to the NRC within 90 days of outage completion but not later than December 31, 2007. A similar letter was sent to each PWR licensee. | ||
Since our March 3, 2006, letter it has come to the NRCs attention that some licensees installing modified strainers in 2006 will not have completed all their supporting evaluations in time to support a December 31, 2006, submission date. The delays are the result of ongoing testing and analysis to support resolution of chemical effects issues. Rather than seek a partial response by the end of 2006 for certain licensees, the NRC expects that each PWR licensee will submit a complete supplemental response as soon in 2007 as the information and analysis results are available. The NRC expects that all responses should be provided no later than December 31, 2007. | |||
The NRC has received questions on our expectations for submittal of GL 2004-02 responses by licensees with an approved extension for completion of GL 2004-02 corrective actions past December 31, 2007. Because the extensions have generally been granted to allow installation of certain equipment in spring 2008, the NRC expects that the design of such equipment will have occurred in time to support a complete GL 2004-02 response by December 31, 2007. If any substantive GL corrective action analytical results or technical details change in 2008 (e.g., | |||
during an outage in which GL corrective action modifications are completed), the NRC expects that the facility GL response should be appropriately updated within 90 days of the change or outage completion. | during an outage in which GL corrective action modifications are completed), the NRC expects that the facility GL response should be appropriately updated within 90 days of the change or outage completion. | ||
A. | |||
/RA/John A. Grobe, Associate Director | A. Pietrangelo As licensees are implementing their corrective actions, the staff is looking toward the closure of Generic Safety Issue 191. As part of the closure activities, the staff will have to ascertain that licensees have completed all their corrective actions and updated their licensing bases, as appropriate. Several licensees have committed to providing this information. The NRC expects that all licensees will inform the NRC, either in supplemental GL 2004-02 responses or by separate correspondence as appropriate, when all GSI-191 actions are complete. | ||
/RA/John A. Grobe, Associate Director | The NRC plans to communicate the above information to each PWR licensee by separate correspondence. If you would like to discuss the contents of this letter further, please contact me at (301) 415-1274 or Thomas Martin, Director, Division of Safety Systems, at (301) 415-3283. | ||
Sincerely, | |||
/RA/ | |||
John A. Grobe, Associate Director for Engineering and Safety Systems Office of Nuclear Reactor Regulation | |||
A. Pietrangelo As licensees are implementing their corrective actions, the staff is looking toward the closure of Generic Safety Issue 191. As part of the closure activities, the staff will have to ascertain that licensees have completed all their corrective actions and updated their licensing bases, as appropriate. Several licensees have committed to providing this information. The NRC expects that all licensees will inform the NRC, either in supplemental GL 2004-02 responses or by separate correspondence as appropriate, when all GSI-191 actions are complete. | |||
The NRC plans to communicate the above information to each PWR licensee by separate correspondence. If you would like to discuss the contents of this letter further, please contact me at (301) 415-1274 or Thomas Martin, Director, Division of Safety Systems, at (301 Sincerely, | |||
/RA/ | |||
John A. Grobe, Associate Director for Engineering and Safety Systems Office of Nuclear Reactor Regulation DISTRIBUTION: | |||
DSS r/f M. Evans, NRR M. Cunningham, RES T. Martin, NRR M. Scott, NRR ADAMS Accession# ML063110263 NRR-088 OFFICE NRR/SSIB NRR/DCI NRR/DSS NRR/ADES NAME MScott MEvans TMartin JGrobe DATE 11/ 07 /06 11/ 07 /06 11/ 09 /06 11/ 14 /06 OFFICIAL RECORD COPY}} |
Latest revision as of 13:18, 23 November 2019
ML063110263 | |
Person / Time | |
---|---|
Issue date: | 11/14/2006 |
From: | Grobe J NRC/NRR/ADES/DSS/SSIB |
To: | Pietrangelo A Nuclear Energy Institute |
Scott M L, NRR/DSS/SSIB, 415-0565 | |
References | |
GL-04-002 | |
Download: ML063110263 (3) | |
Text
November 14, 2006 Mr. Anthony R. Pietrangelo Nuclear Energy Institute 1776 I Street, NW , Suite 400 Washington DC, 20006-3708
SUBJECT:
NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONAL INFORMATION TO PRESSURIZED WATER REACTOR LICENSEES REGARDING RESPONSES TO GENERIC LETTER 2004-02
Dear Mr. Pietrangelo:
This letter supplements our letter of March 3, 2006, on the same subject. In that letter, the Nuclear Regulatory Commission (NRC) accepted your proposed alternative approach and timetable for licensees to respond to the requests for additional information (RAIs) resulting from the NRCs review of the pressurized water reactor (PWR) licensees responses to Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors. Our March 3, 2006, letter stated the NRCs expectation that units completing their outage to incorporate strainer modifications in 2006 would provide to the NRC the information needed to fully address GL 2004-02 by December 31, 2006. For units installing strainers after 2006, information needed to fully address GL 2004-02 would be provided to the NRC within 90 days of outage completion but not later than December 31, 2007. A similar letter was sent to each PWR licensee.
Since our March 3, 2006, letter it has come to the NRCs attention that some licensees installing modified strainers in 2006 will not have completed all their supporting evaluations in time to support a December 31, 2006, submission date. The delays are the result of ongoing testing and analysis to support resolution of chemical effects issues. Rather than seek a partial response by the end of 2006 for certain licensees, the NRC expects that each PWR licensee will submit a complete supplemental response as soon in 2007 as the information and analysis results are available. The NRC expects that all responses should be provided no later than December 31, 2007.
The NRC has received questions on our expectations for submittal of GL 2004-02 responses by licensees with an approved extension for completion of GL 2004-02 corrective actions past December 31, 2007. Because the extensions have generally been granted to allow installation of certain equipment in spring 2008, the NRC expects that the design of such equipment will have occurred in time to support a complete GL 2004-02 response by December 31, 2007. If any substantive GL corrective action analytical results or technical details change in 2008 (e.g.,
during an outage in which GL corrective action modifications are completed), the NRC expects that the facility GL response should be appropriately updated within 90 days of the change or outage completion.
A. Pietrangelo As licensees are implementing their corrective actions, the staff is looking toward the closure of Generic Safety Issue 191. As part of the closure activities, the staff will have to ascertain that licensees have completed all their corrective actions and updated their licensing bases, as appropriate. Several licensees have committed to providing this information. The NRC expects that all licensees will inform the NRC, either in supplemental GL 2004-02 responses or by separate correspondence as appropriate, when all GSI-191 actions are complete.
The NRC plans to communicate the above information to each PWR licensee by separate correspondence. If you would like to discuss the contents of this letter further, please contact me at (301) 415-1274 or Thomas Martin, Director, Division of Safety Systems, at (301) 415-3283.
Sincerely,
/RA/
John A. Grobe, Associate Director for Engineering and Safety Systems Office of Nuclear Reactor Regulation
A. Pietrangelo As licensees are implementing their corrective actions, the staff is looking toward the closure of Generic Safety Issue 191. As part of the closure activities, the staff will have to ascertain that licensees have completed all their corrective actions and updated their licensing bases, as appropriate. Several licensees have committed to providing this information. The NRC expects that all licensees will inform the NRC, either in supplemental GL 2004-02 responses or by separate correspondence as appropriate, when all GSI-191 actions are complete.
The NRC plans to communicate the above information to each PWR licensee by separate correspondence. If you would like to discuss the contents of this letter further, please contact me at (301) 415-1274 or Thomas Martin, Director, Division of Safety Systems, at (301 Sincerely,
/RA/
John A. Grobe, Associate Director for Engineering and Safety Systems Office of Nuclear Reactor Regulation DISTRIBUTION:
DSS r/f M. Evans, NRR M. Cunningham, RES T. Martin, NRR M. Scott, NRR ADAMS Accession# ML063110263 NRR-088 OFFICE NRR/SSIB NRR/DCI NRR/DSS NRR/ADES NAME MScott MEvans TMartin JGrobe DATE 11/ 07 /06 11/ 07 /06 11/ 09 /06 11/ 14 /06 OFFICIAL RECORD COPY