NRC Generic Letter 2004-02
| ML101620040 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/18/2010 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | John Carlin Ginna |
| Pickett D, NRR/DORL, 415-1364 | |
| References | |
| TAC MC4687 | |
| Download: ML101620040 (3) | |
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Mr. John T. Carlin Vice President R E. Ginna Nuclear Power Plant R E. Ginna Nuclear Power Plant, LLC
1503 Lake Road Ontario, NY 14519 SUBJECT: GENERIC LETTER 2004-02 SUPPLEMENTAL RESPONSE - RE. GINNA
NUCLEAR POWER PLANT (TAC NO. MC4687)
Dear Mr. Carlin:
By letters dated February 29, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML080710041), July 25, 2008 (ADAMS Accession No. ML082100452);
June 2, 2009 (ADAMS Accession No. ML091590265); and April 6, 2010 (ADAMS Accession No. ML101020069); RE. Ginna Nuclear Power Plant, LLC, the licensee, submitted supplemental responses to Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," for the RE. Ginna Nuclear Power Plant (Ginna). The last submittal was made in response to a Nuclear Regulatory Commission (NRC) request for additional information dated December 4,
2009 (ADAMS Accession No. ML093290264).
The NRC staff has reviewed your submittals with a process that involved a detailed review by a team of 10 subject matter experts, with focus on the review areas described in the NRC's
"Content Guide for Generic Letter 2004-02 Supplemental Responses" (ADAMS Accession No.
ML073110389). The review process also included a separate review of your submittal consisting of inputs from the subject matter experts that focused on whether you have demonstrated overall that your corrective actions for GL 2004-02 are adequate.
The NRC staff has no further questions for Ginna at this time regarding the licensee's planned methods for completion of actions to fully address GL 2004-02, as described in your response dated April 6, 2010. Because not all the tests and evaluations described in your responses to GL 2004-02 have been completed, we understand that Ginna plans to complete the tests and evaluations by September 30, 2010, and to report the results of these activities to the NRC by October 29, 2010. Should the planned testing and evaluations indicate that any additional actions are needed to address GL 2004-02, the NRC expects that descriptions of planned actions and expected completion dates would be provided by the same date.
As you may be aware, we have not yet issued a final safety evaluation (SE) on WCAP-16793 NP, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous, and Chemical Debris in the Recirculating Fluid." The June 2,2009, submittal for Ginna indicates that the licensee intends to rely on the conclusions reached in WCAP-16793-NP. Assuming disposition of WCAP-16793-NP results in NRC staff issuance of an SE, the NRC intends to send a letter requesting that the licensee confirm whether it still intends to rely on the conclusions reached in WCAP-16793-NP for Ginna. In addition, the letter will likely request a response within 60 days describing, (1) the means the licensee used to determine the amount of debris that bypasses the emergency core cooling system strainer, (2) the fiber loading expected per fuel assembly for
J. Carlin -2 the cold-leg and hot-leg break scenarios based on information available as of the date of the letter, (3) the available head loss margins with bases for the COld-leg and hot-leg break scenarios using the WCAP-16793 acceptance criteria, and (4) the licensee's planned actions for Ginna should it exceed an acceptance criterion. The NRC staff will notify you of the expected timeline for any needed actions at the time the SE is issued, or we will notify you of expectations for additional licensee actions should an SE not be issued. We are not requesting any information from you on this subject at this time.
If you have any further questions on this matter, please contact me at 301-415-1364.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244 cc: Distribution via Listserv
J. Carlin -2 the cold-leg and hot-leg break scenarios based on information available as of the date of the letter, (3) the available head loss margins with bases for the cold-leg and hot-leg break scenarios using the WCAP-16793 acceptance criteria, and (4) the licensee's planned actions for Ginna should it exceed an acceptance criterion. The NRC staff will notify you of the expected timeline for any needed actions at the time the SE is issued, or we will notify you of expectations for additional licensee actions should an SE not be issued. We are not requesting any information from you on this subject at this time.
If you have any further questions on this matter, please contact me at 301-415-1364.
Sincerely, IRA!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244 cc: Distribution via Listserv Distribution:
PUBLIC LPLI-1 r/f RidsNrrDorlLPL 1-1 RidsNrrDssSsib RidsOgcMailCenter RidsAcrsAcnwMailCenter RidsNrrPMREGinna RidsNrrLASLittle GDentel, R1 SSmith, SSIB JLehning, SSIB MYoder, CSGB
Accession Number* ML101620040
OFFICE PM/LPL1-1 LAlLPL1-1 SSIB/BC LPL 1-1/BC
NAME DPickett SLittie EGeiQer for MScott NSalQado DATE 06/17/10 06/16/10 06/17/10 06/18/10
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