Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
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MONTHYEARML0506900352005-03-0303 March 2005
Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Request
ML0515100172005-05-31031 May 2005
Draft RAI on Response to Generic Letter 2004-02
Project stage: Draft RAI
ML0515303042005-06-0303 June 2005
6/3/05, Calvert Cliffs - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0520200572005-07-15015 July 2005
Response to NRC Request for Additional Information Re NRC 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
ML0603803582006-02-0909 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
ML0609500512006-04-12012 April 2006
Approval of Extension Request for Completion of Corrective Actions in Response to Generic Letter 2004-02
Project stage: Other
ML0618702222006-06-30030 June 2006
Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Basis Accidents at Pressurized Water Reactors
Project stage: Other
ML0626405472006-09-20020 September 2006
Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Other
ML0633407022006-12-18018 December 2006
Unit No.1 - Approval of Extension Request for Completion of Corrective Action in Response to Generic Letter 2004-02
Project stage: Other
ML0712703722007-05-0202 May 2007
Revision to Generic Letter 2004-02 Response
Project stage: Other
ML0734504992007-12-10010 December 2007
Attachment (1) Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02
Project stage: Request
ML0734504982007-12-10010 December 2007
Request for Extension for Completion of Activities Related to Generic Letter 2004-02
Project stage: Request
ML0811307392008-04-22022 April 2008
Revision to Generic Letter 2004-02 Response
Project stage: Other
ML0817101052008-06-18018 June 2008
Attachment 1, Request for Extension of the Completion Date for Corrective Actions Related to Generic Letter 2004-02
Project stage: Request
ML0827404892008-09-30030 September 2008
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
ML0827404972008-09-30030 September 2008
Attachment 2, ECCS and CS System Figures
Project stage: Other
ML0833003202008-12-0404 December 2008
Request for Additional Information Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors-Calvert Cliffs Unit 1 & 2
Project stage: RAI
ML0906807672009-03-0404 March 2009
Request for Additional Information: 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
ML1009500782010-04-12012 April 2010
Request for Additional Information Generic Letter 2004-02 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2-
Project stage: RAI
ML1011903842010-05-0606 May 2010
Notice of Forthcoming Conference Call with Calvert Cliffs to Discuss Supplemental Responses to Generic Ltr. 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Request
ML1014708982010-06-0707 June 2010
Summary of Meeting with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss Supplement to Responses to Generic Letter 2004-02
Project stage: Meeting
ML1028701002010-09-30030 September 2010
Draft Responses to NRC Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents on Pressurized-Water..
Project stage: Draft Response to RAI
ML1029306502010-10-20020 October 2010
Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2,
Project stage: Other
ML1030810242010-11-10010 November 2010
Summary of November 1, 2010, Meeting with Duke to Discuss Responses to Generic Letter (GL) 2004-02 (Tac Nos. MC4673, MC4674, MC4692, and MC4693)
Project stage: Meeting
ML1031903612010-11-10010 November 2010
Response to Request for Additional Information Regarding Generic Letter 2004-02
Project stage: Response to RAI
ML12356A0852012-12-27027 December 2012
January 8, 2013 - Notice of Teleconference with Calvert Cliffs Nuclear Power Plant, LLC
Project stage: Meeting
ML13038A5432013-01-24024 January 2013
Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant (CCNPP-CHLE-002, Revision 0d)
Project stage: Request
ML13038A6042013-01-24024 January 2013
PIRT Item Summary
Project stage: Request
ML13038A4872013-01-24024 January 2013
CCNPP-CHLE-001, Revision 0c, Chemical Effects Head Loss Experiment (Chle) Test Plan for Calvert Cliffs Nuclear Power Plant
Project stage: Request
ML13038A5782013-01-24024 January 2013
Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant (CCNPP-CHLE-003, Revision 0b)
Project stage: Request
ML13086A5512013-01-24024 January 2013
MC4672 & MC4673 - CCNPP-CHLE-003, Rev 0c Chemical Effects PIRT Considerations Excerpts with Respect to GL2004-02, GSI-191
Project stage: Other
ML13030A3482013-02-0707 February 2013
Summary of Teleconference with Calvert Cliffs Nuclear Power Plant, Units 1 and 2 to Discuss Proposed Risk-Informed Approach to the Resolution of Generic LTR 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Des
Project stage: Meeting
ML13045A1822013-02-19019 February 2013
March 20, 2013, Notice of Forthcoming Teleconference with Calvert Cliffs and Nrc/Nrr Staff to Have Additional Discussions of Licenseess Proposed Path for Resolution of Generic Letter 2004-02
Project stage: Meeting
ML13050A5112013-02-19019 February 2013
MC4672-3 Corrected Notice -Public Meeting on March 20, 2013 Re-GL2004-02
Project stage: Request
ML13086A5502013-03-0101 March 2013
MC4672 & MC4673, CCNPP-CHLE-002, Rev 0e Chemical Effects Experimental Protocol with Respect to GL2004-02, GSI-191
Project stage: Request
ML13088A2202013-03-18018 March 2013
MC4672 & MC4673 - CCNPP-CHLE-005, Rev 1 Chemical Effects Autoclave Experimental Plan with Respect to GL2004-02, GSI-1 91
Project stage: Request
ML13086A5492013-03-20020 March 2013
MC4672 & MC4673 - Licensee Presentation-Category 1, Public Meeting on March 20, 2013 with Respect to GL2004-02, GSI-191
Project stage: Meeting
ML13091A0552013-04-10010 April 2013
Summary of Meeting on March 20, 2013, with Calvert Cliffs Nuclear Power Plant, LLC, to Discuss the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation D
Project stage: Meeting
ML13149A3942013-05-20020 May 2013
Chemical Effects Head Loss Experiment (Chle) Test Protocol for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-002, Revision 0 May 20, 2013
Project stage: Request
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Chemical Effects Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant CCNPP-CHLE-005, Revision 2, May 20, 2013
Project stage: Request
ML13149A4052013-05-23023 May 2013
Metals BENCH-TOP Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-006, Revision 0, May 23, 2013
Project stage: Request
ML13148A3962013-05-29029 May 2013
Forthcoming Meeting with Calvert Cliffs Nuclear Power Plant, LLC to Discuss Licensees Proposed Plan for Resolution of GL 2004-02
Project stage: Meeting
ML13179A3132013-07-11011 July 2013
June 12, 2013 Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculati
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ML13224A0942013-08-0606 August 2013
Chemical Effects PIRT Considerations for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-003, Revision 0c
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ML13224A1032013-08-0808 August 2013
CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant
Project stage: Request
ML13226A0902013-08-14014 August 2013
Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC
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ML13304B4032013-11-0101 November 2013
Notice of Forthcoming Meeting with Constellation Energy Nuclear Group, LLC,
Project stage: Meeting
ML13319A9392013-11-13013 November 2013
Ri GSI-191 November 2013 Meeting with NRC Rev 0
Project stage: Request
ML13310B9292013-12-0606 December 2013
Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During .
Project stage: Meeting
ML14014A0392014-01-29029 January 2014
Summary of Meeting with Constellation Energy Group, Inc., to Continue Discussions on the Proposed Risk-Informed Approach to the Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During
Project stage: Meeting
2010-06-07
[Table View] |
Text
James A. Spina Vice President nstellati n En~i"fi1"'*
uclear eneration Group April 22, 2008 U. S. Nuclear Regulatory Commission Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Inc.
1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.5200 410.495-3500 Fax ATTENTION:
SUBJECT:
REFERENCES:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 Revision to Generic Letter 2004-02 Response (a)
Letter from Mr. 1. E. Pollock to Document Control Desk (NRC), dated November 29,
- 2005, Supplemental
Response
to NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized Water Reactors" (b)
Letter from Mr. P. D. Milano to Mr. J. A. Spina (CCNPP), dated December 18, 2006, Approval of Extension Request for Completion of Corrective Actions in Respon se to Generic Letter 2004-02 (TAC No.
MC4672)
(c)
NEI 04-07, dated May 28, 2004, Pressurized Water Reactor (PWR) Sump Performance Methodology The purpose of Reference (a) was to supplement our response to Generic Letter 2004-02 to address issues raised by the Nuclear Regulatory Commission (NRC) at a public meeting on September 30, 2005.
As part of the efforts to resolve Generic Safety Issue-191, the NRC has conducted tests at Argonne National Labs to determine the magnitude of the impact of chemical precipitation which might occur in the containment sump pool during post-loss-of-coolant accident (LOCA) recirculation.
One of the tests examined the interaction of calcium-silicate insulation with a Trisodium Phosphate (TSP) sump pool buffer agent. The results showed that a chemical precipitant did form and the impact on strainer headloss was significant.
Those plants containing both calcium-silicate insulation and TSP buffering agent were identified by the NRC/Nuclear Energy Institute (NEI) as needing to address the impact of this result on plant operability including the need to implement additional compensatory measures.
Calvert Cliffs Units I and 2 were among the plants identified as having calcium-silicate insulation and TSP buffering agent. In Reference (a) we stated that, "... Calvert Cliffs has no calcium-silicate insulation in the zone of influence of the LOCA break; therefore, per NEI 04-07... no calcium-silicate insulation
Document Control Desk April 22, 2008 Page 2 will be destroyed during the LOCA, and thus none will transport to the containment sump pool. Since there is no calcium-silicate insulation in our containment sump pool the results of the Argonne National Labs chemical effects testing has no impact on plant operability."
This information was based on a walkdown of Unit 1 during the 2004 refueling outage. That walkdown did not identify any calcium-silicate insulation in the zone of influence ofa Reactor Coolant System (RCS) pipe break.
However, insulation inspections performed during the Unit 1 2008 refueling outage showed some Unit 1 piping did have calcium-silicate insulation in the zone of influence for an RCS pipe break.
These additional inspections were performed based on information obtained during the Unit 2 inspections performed in the 2007 refueling outage. Therefore, in accordance with 10 CFR 50.9(a) we are providing this updated information.
Reference (a) was used to support the approval of our extension request for the completion of corrective actions in response to Generic Letter 2004-02 for Unit 1 (Reference b).
The information originally supplied is not correct for Unit 1, based on the 2008 walkdown of the Unit 1 Containment. All actions that were the subject of the extension request have been completed and all of the identified calcium silicate insulation was mitigated as described below. Therefore, we believe that the updated information provided below has no impact on the previously granted extension.
Updated information for Unit 1 In accordance with Section 3.4.2.2 of NEI 04-07 (Reference c), we identified the zone of influence (17 LID) for the insulation in Containment having the minimum destruction pressure (unjacketed insulation) and applied this to all insulation types. As stated in NEI 04-07, "this approach provides a conservatively large value for debris generation." Walkdowns in Unit 1 during the 2008 refueling outage inspected areas again within this large zone of influence for insulation and specifically calcium-silicate insulation.
The walkdowns identified calcium-silicate insulation on the pressurizer relief valve lines in the pressurizer compartment, on two steam generator blowdown lines near the lower level of Containment, and on four component cooling water relief valve lines ncar the lower level of Containment.
The calcium-silicate insulation was jacketed and the insulation jacket was held on with rivets. Other lines were identified which had calcium-silicate insulation but they are in areas that would not be impacted by an RCS pipe break.
It has also been determined from NEI 04-07 that insulation with banded jacketing has a zone of influence of only 5.45 LID. We contacted the source of this information and were told that the published data was for bands spaced 8 Y4" apart. In addition, WCAP-16720-P documents that with the bands spaced 3" apart a zone of influence of 3 LID was obtained. During the 2008 Unit 1 refueling outage, bands spaced at 6" were placed on the calcium-silicate insulation greater than 10 pipe diameters from an RCS pipe break, and bands spaced at 2 %" were placed on calcium-silicate insulation between a distance of 4 and 10 pipe diameters. In addition, all identified calcium-silicate insulation less than 4 LID from the RCS piping was replaced with either fiberglass or Temp Mat insulation. Therefore, the calcium-silicate insulation within the zone of influence of RCS piping has either been eliminated or armored such that there is no longer any identified calcium-silicate insulation that could get damaged and washed to the containment sump during a LOCA. The banding and removal of calcium-silicate insulation which occurred during the 2008 refueling outage results in an operable containment sump.
An operability evaluation was performed to assess the past operability of the containment sump with calcium-silicate insulation with riveted jacketing (pre Unit 1 refueling outage).
The evaluation determined that the location and inherent strength of the insulation with riveted jacketing would limit the
Document Control Desk April 22, 2008 Page 3 amount of insulation impacted by an RCS break.
Therefore, the evaluation concluded that past operability of Unit I was not significantly affected by the discovered calcium-silicate insulation.
We understand that calcium-silicate insulation and its interaction with trisodium phosphate, as well as other chemical effects, are the subject of continued study by the NRC and the industry. We continue to evaluate the information provided by these efforts to determine the best course of action to ensure the continued operability of our containment sumps.
Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.
STATE OF MARYLAND TO WIT:
COUNTY OF CALVERT I, James A. Spina, being duly sworn, state that I am Vice President - Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP), and that I am duly authorized to execute and file this response on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other CCNPP employees and/or consultants.
Such information has been reviewed in accordance with company practice and I believe it to be reliable.
Subscribed and sworn before me~ Notary Pu lie il\\ and for the State of Maryland and County of
.j~. tl!a.t'e( ~
,this ~ day of
'/;I
,2008.
I
'iilTNESS Illy Hand and Notarial Seal:
My Commission Expires:
JAS/PSF/bjd cc:
D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC S. Gray,DNR
