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MONTHYEAR05000423/LER-2005-001, Regarding Hydrogen Recombiners Out of Service2005-09-0101 September 2005 Regarding Hydrogen Recombiners Out of Service Project stage: Request ML0603801992006-02-0909 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 ML0722706242007-08-15015 August 2007 MR-I-07-0018: Dominion Promotes David Christian to President/Chief Nuclear Officer Project stage: Request ML0729706052007-10-24024 October 2007 Exigent License Amendment Request Re Alternative Containment Analysis Methodology Supporting Information - Gothic Model Input Files Project stage: Request ML0731905532007-11-15015 November 2007 Request for Extension of Completion Dates for Corrective Actions Regarding NRC Generic Letter 2004-02 Project stage: Request ML0734505942007-12-13013 December 2007 Approval of Extension of Completion Dates for Corrective Actions of Generic Letter 2004-02 Project stage: Other ML0806505622008-02-29029 February 2008 Supplemental Response to NRC GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806503142008-02-29029 February 2008 NRC Generic Letter 2004-02 Supplemental Response, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806505632008-02-29029 February 2008 Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0814905722008-05-29029 May 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0818302472008-07-0101 July 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0832304692008-12-17017 December 2008 Request for Additional Information, GL 2004-02 Project stage: RAI ML1000700682010-02-0404 February 2010 Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI ML1003314992010-03-0101 March 2010 Notice of Conference Call with Dominion Nuclear Connecticut, Inc., to Discuss Millstone Power Station, Unit Nos. 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1008204222010-03-26026 March 2010 Notice of Conference Call with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit Nos 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1009804152010-04-0808 April 2010 Draft Millstone GL2004-02 Supplemental Responses to Support Public Teleconference on 4/08 Project stage: Request ML1011705752010-05-0505 May 2010 Summary of Teleconference with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1012506232010-05-24024 May 2010 Summary of Meeting with Dominion Nuclear Connecticut, Inc. (DNC) to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1013700502010-05-25025 May 2010 Forthcoming Conference Call with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit Nos. 2 and 3 Generic Letter 2004-02 Supplemental Responses Project stage: Other ML1015305562010-06-0202 June 2010 Mps GL-04-002 Draft RAI Responses/Public Telecon Handouts Project stage: Request ML1015906482010-06-30030 June 2010 Summary of Meeting with Dominion Nuclear Connecticut, Inc., (DNC) to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1018005132010-07-0101 July 2010 Notice of Forthcoming Public Meeting with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response Project stage: Meeting ML1020104132010-07-0808 July 2010 Response to Request for Additional Information Re Generic Letter 2004-02 Project stage: Response to RAI ML1019505052010-07-13013 July 2010 MPS3 RAI 6 Project stage: Request ML1019502842010-07-14014 July 2010 Notice of Forthcoming Public Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response Project stage: Meeting ML1020102612010-07-29029 July 2010 Summary of July 13, 2010, Meeting with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1022201102010-09-14014 September 2010 July 28, 2010, Summary of Teleconference with DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML1026402102010-09-16016 September 2010 Response to Request for Additional Information Regarding Generic Letter 2004-02 Project stage: Response to RAI ML1031202422010-11-0808 November 2010 Notice of Teleconference with Dominion Nuclear Connecticut, Inc. to Discuss Millstone Power Station, Unit No. 3 Generic Letter 2004-02 Supplemental Response Project stage: Meeting ML1034706502010-12-13013 December 2010 Draft Response to GL2004-02 RAI No. 6 Project stage: Request ML1034807622011-01-12012 January 2011 November 8, 2010 Summary of Teleconference W/ DNC to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI 2010-03-26
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,o Dominions Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, C7 06385 SEP I 2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
MPS Lic/BAK Docket No.
License No.05-350 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 LICENSEE EVENT REPORT 2005-001-00, HYDROGEN RECOMBINERS OUT OF SERVICE This letter forwards Licensee Event Report (LER) 2005-001-00, documenting an event that occurred at Millstone Power Station Unit 3, on February 24, 2005. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B), as any event or condition prohibited by the plant's Technical Specifications and 10 CFR 50.73(a)(2)(v)(D), related to a condition that could have prevented the fulfillment of the safety function of a system.
If you have any questions or require additional Mr. David W. Dodson at (860) 447-1791, extension 2346.
information, please contact Very truly yours, J Al n Price S t ice President - Millstone
a I
Serial No.05-350 LER 2005-001 -00 Page 2 of 2 Attachments:
1 Commitments made in this letter: None.
cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. G. F. Wunder Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B-1A Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station
Serial No.05-350 LER 2005-001-00 HYDROGEN RECOMBINERS OUT OF SERVICE Millstone Power Station Unit 3 Dominion Nuclear Connecticut, Inc. (DNC)
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 (7i1 COMMIS, the NRC may not conduct or (See reverse for required number of digits/characters for each block) sponsor, and a person Is not required to respond to. the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Millstone Power Station - Unit 3 05000423 1 OF 3 TITLE (4)
Hydrogen Recombiners Out Of Service EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR SEQUENTIAL REV MO DAY YEAR NUMBER NO.
DY YA FACILITY NAME DOCKET NUMBER 02 24 2005 2005-001-00 08 25 2005 OPERATING 1
THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR§: (Check all that apply) (11)
MODE (9) 1 20.2201(b)
I 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201(d)
_ 20.2203(a)(4)
_ 50.73(a)(2)(iii)
_ 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)
OTHER 20.2203(a)(2)(iii)
_ 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
Specify In Abstract below or 20.2203(a)(2)(iv) 50.73(a)(2)Ci)(A)
X 50.73(a)(2)(v)(D) in (If more space is required, use additional copies of NRC Fonn 366A) (17)
- 4.
Corrective Action
The compression joint was repaired (on February 28, 2005) via AWO M3-05-04144 and a post maintenance acceptance test was satisfactorily performed.
The maintenance department communicated compression fitting fit-up requirements and work practices to minimize the potential for a repeat event of this type. Additional corrective actions were included in the station's corrective action program.
- 5.
Previous Occurrences
Internal operating experience was reviewed and did not provide any additional information.
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
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| 05000423/LER-2005-001, Regarding Hydrogen Recombiners Out of Service | Regarding Hydrogen Recombiners Out of Service | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) | | 05000336/LER-2005-001, Regarding Nonconformance with Surveillance Requirements | Regarding Nonconformance with Surveillance Requirements | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) | | 05000423/LER-2005-002, Regarding Inadvertent Reactor Trip and Safety Injection | Regarding Inadvertent Reactor Trip and Safety Injection | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | | 05000336/LER-2005-002, Re Reactor Coolant System Pressure Boundary Leakage from PWSCC in a Pressurizer Heater Sleeve | Re Reactor Coolant System Pressure Boundary Leakage from PWSCC in a Pressurizer Heater Sleeve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000423/LER-2005-003, For Millstone Power Station, Unit 3 Manual Reactor Trip Due to Loss of Two Circulating Water Pumps in Same Condenser Section | For Millstone Power Station, Unit 3 Manual Reactor Trip Due to Loss of Two Circulating Water Pumps in Same Condenser Section | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) | | 05000336/LER-2005-003, Re Non-Compliance with Technical Specifications Due to Installation of Unqualified Test Equipment | Re Non-Compliance with Technical Specifications Due to Installation of Unqualified Test Equipment | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | | 05000423/LER-2005-004, Pressurizer Spray Nozzle Weld Indications | Pressurizer Spray Nozzle Weld Indications | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(b)(2)(ii)(A) | | 05000423/LER-2005-005, Automatic Reactor Trip of Millstone Unit 3 Due to Low-Low Steam Generator Level | Automatic Reactor Trip of Millstone Unit 3 Due to Low-Low Steam Generator Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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