Letter Sequence Draft RAI |
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MONTHYEARML0515305472005-05-27027 May 2005
RAI Related to GL 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at pressurized-water Reactors
Project stage: RAI
ML0516605012005-06-0202 June 2005
Waterford - RAI Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
Project stage: RAI
ML0603903862006-02-0909 February 2006
Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accident at Pressurized-Water Reactors.
Project stage: RAI
W3F1-2007-0051, Request for Extension of Completion Date for Corrective Actions Required by Generic Letter 2004-022007-11-14014 November 2007
Request for Extension of Completion Date for Corrective Actions Required by Generic Letter 2004-02
Project stage: Request
ML0733900652007-12-10010 December 2007
Approval of Extension Request, Corrective Actions Due Date, GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors
Project stage: Other
ML0801400072008-01-28028 January 2008
Report on Results of Staff Audit of Corrective Actions to Address GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at PWRs
Project stage: Other
ML0801403182008-01-28028 January 2008
Staff Audit Report on Results of Corrective Actions to Address GSI-191 GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at PWRs
Project stage: Other
ML0917302852009-06-11011 June 2009
Draft 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: Draft RAI
ML0917302832009-06-11011 June 2009
Email, Draft 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: Draft RAI
ML0920901072009-08-0606 August 2009
Notice of Conference Call with Entergy Operations, Inc. to Discuss Draft Request for Additional Information on Generic Letter 2004-02 for Waterford, Unit 3
Project stage: Draft RAI
ML0925101242009-09-22022 September 2009
RAI, Regarding Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents.
Project stage: RAI
ML0927200322009-10-0101 October 2009
Notice of Forthcoming Conference Call with Entergy Operations, Inc. to Discuss Waterford Steam Electric Station, Unit 3, Planned Response to Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML1005400832010-02-24024 February 2010
Forthcoming Conference Call with Entergy Operations, Inc. to Licensee'S Responses to NRC Generic Letter 2004-02 for Waterford Steam Electric Station, Unit 3
Project stage: Request
ML1006903722010-03-0808 March 2010
Licensee Slides from 3/8/2010 Meeting Generic Letter 2004-02 Response to RAIs
Project stage: Response to RAI
ML1007003012010-04-0707 April 2010
Summary Follow-Up Conference Call with Entergy Operations, Inc. to Discuss Draft Response for Waterford, Unit 3, to the Request for Additional Information for Generic Letter 2004-02
Project stage: Draft RAI
ML1013400612010-05-18018 May 2010
Notice of Forthcoming Conference Call with Entergy Operations, Inc. to Discuss Draft Response on GL-2004-02 for Waterford Steam Electric Station, Unit 3
Project stage: Draft Other
ML1015204762010-06-0101 June 2010
Email, Request for Additional Information Regarding Supplemental 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
ML1015302322010-06-0909 June 2010
Summary of Conference Call Meeting with Entergy Operations, Inc. to Discuss Draft Response on GL-2004-02 for Waterford Steam Electric Station, Unit 3
ML1017301902010-06-17017 June 2010
Revised Responses to the Request for Additional Information Related to GL-2004-02
Project stage: Request
ML1017301952010-06-17017 June 2010
Revised Responses to the Nrc'S Request for Additional Information Related to GL-2004-02
Project stage: Request
ML1017302002010-06-17017 June 2010
Chemical Effects Summary Related to RAI Response to GL-2004-02
Project stage: Other
W3F1-2010-0032, Response to Request for Additional Information Regarding Final Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2010-11-23023 November 2010
Response to Request for Additional Information Regarding Final Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Supplement
2009-08-06
[Table View] |
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2023-03-21
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 7, 2010 LICENSEE: ENTERGY OPERATIONS, INC.
FACILITY: WATERFORD STEAM ELECTRIC STATION, UNIT 3
SUBJECT:
SUMMARY
OF MARCH 8, 2010, FOLLOW-UP CONFERENCE CALL WITH ENTERGY OPERATIONS, INC. ON DRAFT RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION FOR GENERIC LETTER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED WATER REACTORS" (TAC NO. MC4729)
On March 8, 2010, a Category 1 Public Meeting via conference call was held between the U.S.
Nuclear Regulatory Commission (NRC) and representatives of Entergy Operations, Inc.
(Entergy, the licensee). This was a follow-up call to the conference call on October 15, 2009, to discuss the open items for Waterford Steam Electric Station, Unit 3 (Waterford 3), from the request for additional information (RAI) on NRC Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized Water Reactors." The licensee submitted a document entitled, "Waterford 3 Generic Letter 2004-02 Response to RAls, March 8, 2010" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100690372), which contained the RAls and draft responses.
The March 8, 2010, Category 1 Public Meeting via conference call was noticed through Meeting Notice, ADAMS Accession No. ML100540083.
It was also decided that Entergy will give the complete response (to all 44 questions) and provide a detailed schedule for the response by March 15, 2010. The licensee committed to providing the complete response by April 15, 2010.
Members of the public were not in attendance. A list of participants is enclosed in Enclosure 1. covers the status of the responses to the 44 questions in the licensee presentation.
-2 Please direct any inquiries to me at 301-415-1480 or kaly.kalyanam@nrc.gov.
N. Kaly Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosures:
- 1. List of Participants
- 2. Status of Responses cc w/encls: Distribution via Listserv
LIST OF PARTICIPANTS MARCH 8, 2010, PUBLIC MEETING VIA CONFERENCE CALL WITH ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 Entergy Operations. Inc.
Robert Murillo Brian Lanka Greg Ferguson Nick Petit Mike Mason Megan Stachowiak Jim Furman Gil Zigler Nuclear Regulatory Commission Michael Scott, NRRlDSS/SSIB Steven Smith, NRRlDSS/SSIB Roberto Torres, NRRlDSS/SSIB Paul Klein, NRRlDCI/CSGB Matt Yoder, NRRlDCI/CSGB Emma Wong, NRRlDCI/CSGB N. Kalyanam, NRRlDORLlLPL4 Enclosure 1
STATUS OF RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 RAI Question No. (*) Comment 1 thru 10 Licensee stated it will use 17D for Nukon. This response is acceptable to the NRC staff.
11 (**) Staff suggested that the licensee reach a decision for the path forward and include it in the RAI response.
12 and 13 The responses provided in the previous discussions on October 15, 2009, appear acceptable to the NRC staff, subject to review of the draft RAI response.
14 The NRC staff does not need to review the CFD plots, since licensee does not plan to credit debris settling.
15 thru 17 The responses provided in the previous discussions on October 15, 2009, appear acceptable to the NRC staff, subject to review of the draft RAI response.
18(**) The licensee to re-evaluate whether settling will be credited for downstream effects.
19 The responses provided in the previous discussions on October 15, 2009, appear acceptable to the NRC staff, subject to review of the draft RAI response.
20 While the draft response appears acceptable and it is not necessary to credit the holdup (Le., assume a 100 percent transport), the licensee response should clearly state that methodology used to determine this percentage of debris lifting over the plenum applies to one break (Break S7).
21 The responses provided in the previous discussions on October 15, 2009, appear acceptable to the NRC staff, subject to review of the draft RAI response.
(*) For the description of the Request for Additional Information (RAI) questions, please refer to the presentation entitled, "Waterford 3 Generic Letter 2004-02 Response to RAls, March 8,2010" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100690372).
(**) Represents the items considered unresolved. These items will likely be the focus for a future discussion, unless the RAI responses contain details not discussed or unexpected information.
Enclosure 2
-2 RAI Question No. (*) Comment 22(**) The licensee is finalizing the assumptions and will commit to procedural items similar to the Dominion Energy, Millstone response to deal with low pressure safety injection pump to stop. The licensee will also include this scenario in the testing. The NRC staff also stated that it would like to see a draft response on this item, since the licensee's decision will affect the transport evaluation.
23 The licensee can provide a high-level description of the test facility and state if it is similar to that observed by the staff.
24 and 25 The responses provided in the previous discussions on October 15, 2009, appear acceptable to the NRC staff, subject to review of the draft RAI response.
26 The licensee should state that it is using the same procedure used at other plants and found acceptable by the NRC staff.
27 thru 34 The responses provided in the previous discussions on October 15, 2009, appear acceptable to the NRC staff, subject to review of the draft RAI response.
35 The response appears acceptable to the NRC staff, subject to review of the draft RAI response.
36(**) Licensee stated that there is no net holdup in the refueling canal, since the 6 inch straight pipe drains with the other obstacles in the region prevent clogging of the drains. While the NRC staff considered the response as probably acceptable, the formal RAI response should provide a clear and cogent argument.
37 The responses provided in the previous discussions on October 15, 2009, appear acceptable to the NRC staff, subject to review of the draft RAI response. Regarding the inorganic zinc, the licensee stated that the 102 in the zone of influence is top-coated.
38 This item (in-vessel downstream effects) is to be resolved generically.
39 thru 44 Licensee stated it will retest with WCAP precipitate Base model. Any contingent refinement will be discussed in detail in the RAI response. The licensee should include the equilibrium pH range and aluminum concentration. NRC staff will provide a sample of a successful licensee submittal.
(*) For the description of the Request for Additional Information (RAI) questions, please refer to the presentation entitled, "Waterford 3 Generic Letter 2004-02 Response to RAls, March 8, 2010" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100690372).
(**) Represents the items considered unresolved. These items will likely be the focus for a future discussion, unless the RAI responses contain details not discussed or unexpected information.
Meetina Notice . S ummarv ML100700301, Licensee Slides ML100690372 OFFICE DORULPL4/PM DORULPL4/LA NRRlDSS/SSIB DORULPL4/BC DORULPL4/PM NAME NKalyanam JBurkhardt MScott MMarkley BSingal for NKalyanam DATE 3/31/10 3/15/10 3/15/10 4/6110 4/7/10
