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| | number = ML071410078 | | | number = ML071410078 |
| | issue date = 05/17/2007 | | | issue date = 05/17/2007 |
| | title = Calvert Cliffs Nuclear Power Plant, Unit 2, Post-Accident Monitoring Report | | | title = Post-Accident Monitoring Report |
| | author name = Pollock J E | | | author name = Pollock J |
| | author affiliation = Constellation Energy Group, Constellation Generation Group | | | author affiliation = Constellation Energy Group, Constellation Generation Group |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Calvert Cliffs Nuclear Power Plant Constellation Generation Group, LLC 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 0 Constellation Energy May 17, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: | | {{#Wiki_filter:Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Constellation Generation Group, LLC Lusby, Maryland 20657 0 Constellation Energy May 17, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Document Control Desk Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Post-Accident Monitoring Report The attached report is submitted in accordance with Calvert Cliffs Nuclear Power Plant Technical Specification 3.3.10.B.
| | Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Post-Accident Monitoring Report The attached report is submitted in accordance with Calvert Cliffs Nuclear Power Plant Technical Specification 3.3.10.B. The report is required due to the Unit 2 Reactor Vessel Water Level Monitoring System having less than the required minimum number of operable channels. |
| The report is required due to the Unit 2 Reactor Vessel Water Level Monitoring System having less than the required minimum number of operable channels.Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.for Joseph E. Pollock Plant General Manager JEP/CAN/bjd | | Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219. |
| | for Joseph E. Pollock Plant General Manager JEP/CAN/bjd |
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| ==Attachment:== | | ==Attachment:== |
| | (1) Unit 2 Reactor Vessel Water Level Monitoring System Report cc: D. V. Pickett, NRC Resident Inspector, NRC S. J. Collins, NRC R. I. McLean, DNR AWo |
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| (1) Unit 2 Reactor Vessel Water Level Monitoring System Report cc: D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC R. I. McLean, DNR AWo ATTACHMENT (1)UNIT 2 REACTOR VESSEL WATER LEVEL MONITORING SYSTEM REPORT Calvert Cliffs Nuclear Power Plant, Inc.May 17, 2007 ATTACHMENT (1)UNIT 2 REACTOR VESSEL WATER LEVEL MONITORING SYSTEM REPORT Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP) submits this Post-Accident Monitoring Report concerning an inoperable Unit 2 Reactor Vessel Water Level Monitoring System channel. This report is required by Technical Specification 3.3.10, Required Action B.1.ACTION TAKEN On April 11, 2007 at approximately 1145 hours, the CCNPP Unit 2 Reactor Vessel Water Level Monitoring System, Channel A experienced the failure of the six of the eight level position sensors. The failure of these sensors resulted in Channel A being declared inoperable.
| | ATTACHMENT (1) |
| Calvert Cliffs Technical Specification Bases Section B3.3.10, "Post-Accident Monitoring (PAMS) Instrumentation," requires one of the upper three (vessel head region) and three of the lower five (plenum region) sensors for operability of each Reactor Vessel Water Level Monitor Channel. As a result of the subject failures, CCNPP immediately entered Technical Specification 3.3.10, Condition A. When the Completion Time of Condition A expired, CCNPP entered Technical Specification 3.3.10, Condition B, which requires submission of this report in accordance with Technical Specification 5.6.7.EFFECT ON OPERATION The Reactor Vessel Water Level Monitoring System instrumentation is designated for post-accident monitoring use. It provides the plant operator with information to assess void formation in the reactor vessel head region and the trend of liquid level in the reactor vessel plenum. The Reactor Vessel Water Level Monitoring System consists of two redundant channels. | | UNIT 2 REACTOR VESSEL WATER LEVEL MONITORING SYSTEM REPORT Calvert Cliffs Nuclear Power Plant, Inc. |
| Reactor Vessel Water Level Monitoring Channel B remains operable with all eight of its sensors functioning normally. | | May 17, 2007 |
| The removal of Channel A from operable status eliminates a means of redundant indication. | | |
| However, alternate methods of monitoring for core and Reactor Coolant System voiding, using pressurizer level, Reactor Coolant System subcooling, hot and cold leg temperature, and core exit thermocouple instrumentation, have been initiated as required by plant procedures. | | ATTACHMENT (1) |
| CAUSES OF INOPERABILITY The cause of inoperability is the failure of six sensors (one is located in the upper region and five are located in the lower region of the reactor vessel). The cause of these failures is unknown at this time.An apparent cause evaluation is in progress to determine the cause of these failures.PLANS AND SCHEDULES FOR RESTORING THE SYSTEM TO OPERABLE STATUS Calvert Cliffs Nuclear Power Plant will repair or replace as necessary the Channel A Reactor Vessel Water Level cable and associated connectors during the next forced outage of sufficient duration. | | UNIT 2 REACTOR VESSEL WATER LEVEL MONITORING SYSTEM REPORT Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP) submits this Post-Accident Monitoring Report concerning an inoperable Unit 2 Reactor Vessel Water Level Monitoring System channel. This report is required by Technical Specification 3.3.10, Required Action B.1. |
| If these activities do not resolve the problem, the Channel A Reactor Vessel Water Level sensors will be replaced during the scheduled Unit 2 2009 Refueling Outage. Following these maintenance activities, it is expected that the Reactor Vessel Water Level Monitor Channel A will be returned to operable status.1}} | | ACTION TAKEN On April 11, 2007 at approximately 1145 hours, the CCNPP Unit 2 Reactor Vessel Water Level Monitoring System, Channel A experienced the failure of the six of the eight level position sensors. The failure of these sensors resulted in Channel A being declared inoperable. Calvert Cliffs Technical Specification Bases Section B3.3.10, "Post-Accident Monitoring (PAMS) Instrumentation," requires one of the upper three (vessel head region) and three of the lower five (plenum region) sensors for operability of each Reactor Vessel Water Level Monitor Channel. As a result of the subject failures, CCNPP immediately entered Technical Specification 3.3.10, Condition A. When the Completion Time of Condition A expired, CCNPP entered Technical Specification 3.3.10, Condition B, which requires submission of this report in accordance with Technical Specification 5.6.7. |
| | EFFECT ON OPERATION The Reactor Vessel Water Level Monitoring System instrumentation is designated for post-accident monitoring use. It provides the plant operator with information to assess void formation in the reactor vessel head region and the trend of liquid level in the reactor vessel plenum. The Reactor Vessel Water Level Monitoring System consists of two redundant channels. Reactor Vessel Water Level Monitoring Channel B remains operable with all eight of its sensors functioning normally. The removal of Channel A from operable status eliminates a means of redundant indication. However, alternate methods of monitoring for core and Reactor Coolant System voiding, using pressurizer level, Reactor Coolant System subcooling, hot and cold leg temperature, and core exit thermocouple instrumentation, have been initiated as required by plant procedures. |
| | CAUSES OF INOPERABILITY The cause of inoperability is the failure of six sensors (one is located in the upper region and five are located in the lower region of the reactor vessel). The cause of these failures is unknown at this time. |
| | An apparent cause evaluation is in progress to determine the cause of these failures. |
| | PLANS AND SCHEDULES FOR RESTORING THE SYSTEM TO OPERABLE STATUS Calvert Cliffs Nuclear Power Plant will repair or replace as necessary the Channel A Reactor Vessel Water Level cable and associated connectors during the next forced outage of sufficient duration. If these activities do not resolve the problem, the Channel A Reactor Vessel Water Level sensors will be replaced during the scheduled Unit 2 2009 Refueling Outage. Following these maintenance activities, it is expected that the Reactor Vessel Water Level Monitor Channel A will be returned to operable status. |
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Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:Status Report
MONTHYEARRS-17-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2017-03-30030 March 2017 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-16-046, Annual Property Insurance Status Report2017-03-29029 March 2017 Annual Property Insurance Status Report RS-16-094, Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isl2016-04-25025 April 2016 Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isla RS-16-028, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design- Basis External Events (Order Number EA-12-049)2016-02-26026 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design- Basis External Events (Order Number EA-12-049) RS-15-054, February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-20020 February 2015 February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-15-055, February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051)2015-02-20020 February 2015 February 2015 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) L-14-030, August 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-26026 August 2014 August 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14069A3182014-02-27027 February 2014 February 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML14069A1802014-02-24024 February 2014 February 2014 Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML13098A0842013-03-27027 March 2013 Decommissioning Funding Status Report ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML12024A3762011-12-28028 December 2011 State-of-the-Art Reactor Consequence Analyses, Current Status and Next Steps ML0908504002009-03-26026 March 2009 Units, 1 & 2, Nine Mile Point, Units, 1 & 2, and R.E. Ginna, 2009 Decommissioning Funding Status Report: Year End 2008 ML0723203822007-08-23023 August 2007 Status of the Acceptance Review Part One of the Combined License Application for Calvert Cliffs Nuclear Power Plant, Unit 3 ML0714100782007-05-17017 May 2007 Post-Accident Monitoring Report ML0710802622007-03-30030 March 2007 Biennial Report: Status of Decommissioning Funding Per 10 CFR 50.75(f)(1) ML0509400242005-03-29029 March 2005 Plants 2005 Report on Status of Decommissioning Funding ML0224007982002-02-0101 February 2002 E-mail from Beth Wetzel Bulletin 2001-01 Status Report ML0224007812002-01-18018 January 2002 E-mail from Jacob Zimmerman, Bulletin 2001-01 Status Report 2017-03-30
[Table view] |
Text
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Constellation Generation Group, LLC Lusby, Maryland 20657 0 Constellation Energy May 17, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Post-Accident Monitoring Report The attached report is submitted in accordance with Calvert Cliffs Nuclear Power Plant Technical Specification 3.3.10.B. The report is required due to the Unit 2 Reactor Vessel Water Level Monitoring System having less than the required minimum number of operable channels.
Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.
for Joseph E. Pollock Plant General Manager JEP/CAN/bjd
Attachment:
(1) Unit 2 Reactor Vessel Water Level Monitoring System Report cc: D. V. Pickett, NRC Resident Inspector, NRC S. J. Collins, NRC R. I. McLean, DNR AWo
ATTACHMENT (1)
UNIT 2 REACTOR VESSEL WATER LEVEL MONITORING SYSTEM REPORT Calvert Cliffs Nuclear Power Plant, Inc.
May 17, 2007
ATTACHMENT (1)
UNIT 2 REACTOR VESSEL WATER LEVEL MONITORING SYSTEM REPORT Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP) submits this Post-Accident Monitoring Report concerning an inoperable Unit 2 Reactor Vessel Water Level Monitoring System channel. This report is required by Technical Specification 3.3.10, Required Action B.1.
ACTION TAKEN On April 11, 2007 at approximately 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, the CCNPP Unit 2 Reactor Vessel Water Level Monitoring System, Channel A experienced the failure of the six of the eight level position sensors. The failure of these sensors resulted in Channel A being declared inoperable. Calvert Cliffs Technical Specification Bases Section B3.3.10, "Post-Accident Monitoring (PAMS) Instrumentation," requires one of the upper three (vessel head region) and three of the lower five (plenum region) sensors for operability of each Reactor Vessel Water Level Monitor Channel. As a result of the subject failures, CCNPP immediately entered Technical Specification 3.3.10, Condition A. When the Completion Time of Condition A expired, CCNPP entered Technical Specification 3.3.10, Condition B, which requires submission of this report in accordance with Technical Specification 5.6.7.
EFFECT ON OPERATION The Reactor Vessel Water Level Monitoring System instrumentation is designated for post-accident monitoring use. It provides the plant operator with information to assess void formation in the reactor vessel head region and the trend of liquid level in the reactor vessel plenum. The Reactor Vessel Water Level Monitoring System consists of two redundant channels. Reactor Vessel Water Level Monitoring Channel B remains operable with all eight of its sensors functioning normally. The removal of Channel A from operable status eliminates a means of redundant indication. However, alternate methods of monitoring for core and Reactor Coolant System voiding, using pressurizer level, Reactor Coolant System subcooling, hot and cold leg temperature, and core exit thermocouple instrumentation, have been initiated as required by plant procedures.
CAUSES OF INOPERABILITY The cause of inoperability is the failure of six sensors (one is located in the upper region and five are located in the lower region of the reactor vessel). The cause of these failures is unknown at this time.
An apparent cause evaluation is in progress to determine the cause of these failures.
PLANS AND SCHEDULES FOR RESTORING THE SYSTEM TO OPERABLE STATUS Calvert Cliffs Nuclear Power Plant will repair or replace as necessary the Channel A Reactor Vessel Water Level cable and associated connectors during the next forced outage of sufficient duration. If these activities do not resolve the problem, the Channel A Reactor Vessel Water Level sensors will be replaced during the scheduled Unit 2 2009 Refueling Outage. Following these maintenance activities, it is expected that the Reactor Vessel Water Level Monitor Channel A will be returned to operable status.
1