Letter Sequence RAI |
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MONTHYEARML0603807082006-02-0909 February 2006
RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0818400612008-06-24024 June 2008
Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ULNRC-05521, Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-24024 June 2008
Request for Extension of Corrective Actions Completion Date for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Request
ML0818503552008-06-27027 June 2008
Attachment, Summary of Telephone Conference Regarding Request for Extension of Completion of Corrective Actions for NRC Generic Letter 2004-02
Project stage: Request
ML0818503312008-06-27027 June 2008
Email Response from Scott Maglio to Mohan Thadani, Jack Donahew, Leon Whitney Generic Letter - 2004 - 02
Project stage: Other
ML0818406062008-07-0303 July 2008
Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Other
ML0920101222008-12-18018 December 2008
Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0920101192008-12-18018 December 2008
Email Re Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ET 08-0053, Corporation Response to Request for Additional Information Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-12-22022 December 2008
Corporation Response to Request for Additional Information Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Response to RAI
ML0919704342009-06-22022 June 2009
Draft Request for Additional Information Generic Letter 2004-02
Project stage: Draft RAI
ML0919704232009-06-22022 June 2009
Email Draft Request for Additional Information Generic Letter 2004-02
Project stage: Draft RAI
ML0920306202009-07-31031 July 2009
Notice of Forthcoming Conference Call with Union Electric Company and Wolf Creek Nuclear Operating Company Re Draft Requests for Additional Information on Generic Letter 2004-02 for Callaway Plant and Wolf Creek Creek Generating Station
Project stage: Draft RAI
ML0920306282009-07-31031 July 2009
Request for Additional Information (RAI) Regarding Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (Tac No. MC4731)
Project stage: RAI
ML0922205722009-08-27027 August 2009
Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage of Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0924607142009-09-28028 September 2009
Summary of Meeting with Union Electric Co., and Wolf Creek, to Discuss Draft Requests for Additional Information on GL 2004-02 for Callaway, Unit 1, and Wolf Creek
Project stage: Draft RAI
ML0928003162009-10-16016 October 2009
Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/0209 and 8/27/2009, Respectively
Project stage: RAI
ML0929300152009-10-20020 October 2009
Revised Notice of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02
Project stage: RAI
ULNRC-05668, Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs2009-11-24024 November 2009
Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs
Project stage: Request
ML0932903202009-11-24024 November 2009
Request for Extension of Response Date to NRC Request for Additional Information Re Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at PWRs
Project stage: Request
ML0933805662009-12-17017 December 2009
Summary of Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss NRC Requests for Additional Information on Generic Letter 2004-02 Sent 7/31/2009 and 8/27/2009, Respectively
Project stage: RAI
ULNRC-05989, Path Forward for Resolution of GSI-1912013-05-16016 May 2013
Path Forward for Resolution of GSI-191
Project stage: Request
ML13263A1682013-09-23023 September 2013
Request for Additional Information, Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191
Project stage: RAI
ULNRC-06045, Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage2013-10-31031 October 2013
Response to Request for Additional Information Closure of Option 2 to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage
Project stage: Response to RAI
2009-11-24
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 23,2013 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RE: CLOSURE OF OPTION 2 TO ADDRESS IN-VESSEL MITIGATIVE MEASURES FOR POTENTIAL IN-VESSEL BLOCKAGE (TAC NO. MC4671)
Dear Mr. Heflin:
In its letter dated May 16, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13136A290), Union Electric Company (dba Ameren Missouri, the licensee), provided the U.S. Nuclear Regulatory Commission (NRC) with its intended path forward for the resolution of Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance," for Callaway Plant, Unit 1 (Callaway). The licensee stated that Callaway would be following the Option 2 risk-informed approach, partially due to high fiber levels in containment.
The DecelTIber 14, 2012, Staff Requirements Memorandum on SECY-12-0093, "Closure Options for [GSI-191]" (ADAMS Accession No. ML12349A378), describes three closure options that licensees can follow to resolve GSI-191. The NRC staff has determined that additional information, as requested in the enclosure, is needed from licensees to complete the review of Option 2 plants, including Callaway, which did not address mitigative measures for potential in-vessel blockage.
A. Heflin
- 2 Please provide a response to the enclosed request for additional information by October 31, 2013. If circumstances result in the need to revise the requested response date, please contact me at 301-415-2296 or via e-mail at Fred.Lyon@nrc.gov.
Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION CLOSURE OF OPTION 2 FOR GENERIC SAFETY ISSUE (GSI}-191 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483 The December 14,2012, Staff Requirements Memorandum on SECY-12-0093, "Closure Options for Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12349A378), describes three closure options that licensees can follow to resolve GSI-191. The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to complete its review of Option 2 plants, including Callaway Plant, which did not address mitigative measures for potential in-vessel blockage.
In its letter dated May 16, 2013 (ADAMS Accession No. ML13136A290), Union Electric Company (dba Ameren Missouri, the licensee), provided the NRC with its intended path forward for the resolution of GSI-191. The licensee stated that Callaway Plant would be following the Option 2 risk-informed approach, partially due to high fiber levels in containment. The licensee also referenced a Nuclear Energy Institute (NEI) letter dated May 4, 2012 (ADAMS Accession No. ML12142A316), as one of the documents providing guidance on the contents of the licensee's submittal as a path forward. The NRC staff noted that the May 4, 2012, NElletter stated that licensees that do not meet very low in-vessel debris limits would provide, as part of the intended path forward, mitigative measures to reduce risk while taking actions to finalize the resolution of Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (ADAMS Accession No. ML042360586). The May 16, 2013, letter did not identify that the licensee had implemented, or identified for future implementation, any mitigative measures to deal with the potential for in-vessel blockage.
The NRC staff has determined that the following request for additional information is needed to complete the review of Option 2 plants, including Callaway Plant, which did not address mitigative measures for potential in-vessel blockage:
Please provide the mitigative measures, in place or planned, to deal with potential in-vessel blockage at Callaway Plant. If all mitigative measures have not been implemented, please provide the schedule for implementing them.
Enclosure
ML13263A168 Sincerely,
/raJ Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- email dated OFFICE NRRlDORLJLPL4IPM NRRlDORUlPl4/LA NRRlDPRlPGCB/BC(A) NRRlDORLJlPl4/BC NRRlDORLJlPl4IPM NAME Flyon JBurkhardt SSluchell*
MMarkley Flyon DATE 9123/13 9/23113 9/19/13 9/23/13 9/23113
