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Category:Letter type:ULNRC
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications ULNRC-06398, Special Report 2017-02: Non-Functional Seismic Instrument for Greater than 30 Days2017-11-0808 November 2017 Special Report 2017-02: Non-Functional Seismic Instrument for Greater than 30 Days 05000483/LER-2017-0022017-10-13013 October 2017 Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design, LER 17-002-00 for Callaway Plant, Unit 1, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design 05000483/LER-2017-0012017-08-15015 August 2017 Violation of Technical Specification 3.7.9 Due to Ultimate Heat Sink (UHS) Cooling Tower Train Inoperability, LER 17-001-00 for Callaway, Unit 1, Regarding Violation of Technical Specification 3.7.9 Due to Ultimate Heat Sink (UHS) Cooling Tower Train Inoperability 05000483/LER-2015-0012016-12-0202 December 2016 Completion of a Shutdown Required by the Technical Specifications - TS 3.4.13, LER 15-001-01 for Callaway Plant, Unit 1, Regarding Completion of a Shutdown Required by the Technical Specifications - TS 3.4.13 05000483/LER-2015-0022016-09-0707 September 2016 Manual Auxiliary Feedwater System Actuation, LER 15-002-00 for Callaway, Unit 1, Regarding Manual Auxiliary Feedwater System Actuation 05000483/LER-2016-0012016-06-20020 June 2016 Control Room Air Conditioning Inoperability Due To Essential Service Water Pressure Transient, LER 16-001-00 for Callaway, Unit 1, Regarding Control Room Air Conditioning Inoperability Due to Essential Service Water Pressure Transient 05000483/LER-2015-0032016-01-21021 January 2016 Reactor Trip Caused by Transmission Line Fault, LER 15-003-01 for Callaway, Unit 1, Regarding Reactor Trip Caused by Transmission Line Fault ULNRC-06162, Special Report 2014-05 Inoperability of Loose Parts Monitoring Instrument for Greater than 30 Day2014-12-11011 December 2014 Special Report 2014-05 Inoperability of Loose Parts Monitoring Instrument for Greater than 30 Day ULNRC-06142, SR-14-002 Callaway, Unit 1 - Special Report 2014-02-PAM Report Inoperability of Post Accident Monitoring (PAM) Instrument2014-09-16016 September 2014 SR-14-002 Callaway, Unit 1 - Special Report 2014-02-PAM Report Inoperability of Post Accident Monitoring (PAM) Instrument ULNRC-05991, Special Report 13-001-00 for Callaway, Unit 1, Inoperability of a Seismic Instrument for Greater than 30 Days2013-05-13013 May 2013 Special Report 13-001-00 for Callaway, Unit 1, Inoperability of a Seismic Instrument for Greater than 30 Days ULNRC-05932, Special Report 2012-02 - Pam Report: Inoperability of a Post Accident Monitoring (PAM) Instrument for Greater than 30 Days2012-11-14014 November 2012 Special Report 2012-02 - Pam Report: Inoperability of a Post Accident Monitoring (PAM) Instrument for Greater than 30 Days ULNRC-05824, Special Report 2011-01 for Callway, Unit 1 Regarding Inoperability of a Seismic Instrument for Greater than 30 Days2011-11-10010 November 2011 Special Report 2011-01 for Callway, Unit 1 Regarding Inoperability of a Seismic Instrument for Greater than 30 Days ULNRC-05721, Special Report, Inoperable Channel 8 of the Loose Parts Monitoring System (Lpms)2010-07-22022 July 2010 Special Report, Inoperable Channel 8 of the Loose Parts Monitoring System (Lpms) ULNRC-05374, Special Report 07-001 Re Historical Inoperability of Seismic Instrument SGAR00082007-03-0808 March 2007 Special Report 07-001 Re Historical Inoperability of Seismic Instrument SGAR0008 ML0413203792004-05-0303 May 2004 Special Report for Callaway Plant Unit 1 Regarding Inoperability of 60 Meter Meteorological Monitoring Instrumentation on the Primary Meteorological Tower 2023-11-29
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WAmeren Callaway Plant MISSOURI September 16, 2014 ULNRC-06142 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 2014 PAM REPORT INOPERABILITY OF A POST ACCIDENT MONITORING (PAM) INSTRUMENT
Reference:
ULNRC-06139 dated September 2, 2014, "Special Report 2014 PAM Report Inoperability of a Post Accident Monitoring (PAM) Instrument" Enclosed Special Report 2014-02 (PAM Report) addresses inoperability of the Reactor Vessel Level Indicating System (RVLIS). Since the period of inoperability for the Reactor Vessel Level Indicating System (RVLIS) has exceeded the Completion Times specified within Technical Specification (TS) 3.3.3 Condition C and is projected to exceed the Completion Time of Condition A, TS 3.3.3 Conditions Band F (ofTS 3.3.3) require submittal of a report in accordance with TS 5.6.8, "PAM Report."
No new commitments are identified in this correspondence. None of the material in this report is considered proprietary by Union Electric.
If you have any questions or require additional information, please contact Mr. Thomas Elwood, Supervising Engineer, Regulatory Affairs and Licensing at 314-225-1905.
Sincerely, tf/a /1/-k )/
D. Matt Hall Director, Nuclear Operations CSP Enclosure
- PO Box 620 Fulton, MO 65251 AmerenMissouri.com **************
STARS
ULNRC-06142 September 16, 2014 Page 2 cc: Mr. Marc L. Dapas Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Fred Lyon Project Manager, Callaway Plant Office ofNuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8B 1 Washington, DC 20555-2738
ULNRC-06142 September 16, 2014 Page 3 Index and send hardcopy to QA File A160.0761 Hardcopy:
Certrec Corporation 4150 International Plaza Suite 820 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Responses and Reports ULNRC Distribution:
F. M. Diya D. W. Neterer L. H. Graessle B. L. Cox S. A. Maglio T. B. Elwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)
Enclosure to ULNRC-06142 Page 1 of2 Special Report 2014-02 PAM Report Requirement Callaway Plant Unit 1 Technical Specification (TS) 3.3.3, "Post Accident Monitoring (PAM)
Instrumentation," contains requirements for the Reactor Vessel Level Indicating System (RVLIS) instrumentation. TS 3.3.3 Limiting Condition For Operation (LCO) requires two channels ofRVLIS instrumentation to be Operable while in MODES 1, 2, and 3. With one of the required RVLIS instruments inoperable for more than 30 days, Required Action B.1 specifies, "Initiate action in accordance with Specification 5.6.8." With two of the required RVLIS instruments inoperable for more than 7 days, Required Action F.l also specifies, "Initiate action in accordance with Specification 5.6.8."
TS 5.6.8, "PAM Report," states, "When a report is required by Condition B or F ofLCO 3.3.3, 'Post Accident Monitoring (PAM) Instrumentation,' a report shall be submitted within the following 14 days.
The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status."
Background:
The Reactor Vessel Level Indicating System (RVLIS) provides an indication of reactor vessel level from the bottom of the reactor vessel to the top of the reactor under natural (narrow range) and forced (wide range) circulation conditions. In addition to the two differential pressure transmitters that support this function, resistance temperature detectors (RTDs) are provided on the sensing lines to these transmitters to allow for density compensation of the fluid within the sensing lines. This system solely supports the Post Accident Monitoring functions required by Technical Specification 3.3.3 Function 5.
Summary of the PAM Instrument Inoperability On August 7, 2014, B Train RVLIS was declared inoperable due to intermittent spiking within the narrow range (static) level indication. This loop was restored to service on August 18, 2014 following replacement of the power supply card for this instrument loop.
On August 19, 2014, A Train RVLIS was declared inoperable due to a failed RTD input to the narrow range (static) and wide range (dynamic) level indications. From a review of the plant computer archives, evidence exists that this input had been experiencing performance concerns back to July 3, 2014.
On August 26, 2014, B Train RVLIS was again declared inoperable due to intermittent spiking within the narrow range level indication. Additional reviews of the plant computer archives determined that intermittent spiking concerns in this instrument loop appear to have been present dating back to April 2014.
The above was previously reported in accordance with Technical Specification 3.3.3 Conditions Band F since firm evidence of these operational concerns existed prior to the date of discovery. (Refer to Callaway Special Report 2014-01 submitted under Ameren letter ULNRC-06139 dated September 2, 2014.)
Enclosure to ULNRC-06142 Page 2 of2 On September 2, 2014, the seven-day Completion Time of Technical Specification 3.3.3 Condition C was exceeded when neither RVLIS train was returned to service following entry into this condition on August 26,2014.
On September 10,2014, A Train RVLIS was returned to service following the rework of an electrical splice in the affected RTD circuit. However, this loop was declared inoperable on September 11, 2014, following a recurrence of the operational concerns with this RTD.
Neither of these trains will be returned to service prior to September 18, 2014. As a result, this report also addresses the following:
- 1. Exceeding the 30-day Completion Time for Technical Specification 3.3.3 Condition A since both trains of RVLIS will not be restored prior to this date, and
- 2. Exceeding the 7-day Completion Time for Technical Specification 3.3.3 Condition C since neither of the RVLIS trains will be restored prior to this date.
Preplanned Alternate Method of Monitoring An alternate means of monitoring, as described in TS Bases 3.3.3 Required Action F.1, is monitoring the core exit thermocouples, pressurizer level indication, and Reactor Coolant System subcooling monitor indication. These three parameters provide diverse information for verifying adequate core cooling.
Cause of the Inoperability As noted above, the reported concerns within both RVLIS trains have been intermittent in nature.
The first attempt to restore the B Train RVLIS cabinet on August 18, 2014 was based upon addressing one of the two potential causes that could contribute to intermittent spiking within the loop (loop power supply card). Following recurrence of this concern on August 26, 2014, temporary recording equipment was capable of capturing a subsequent transient within this loop. The data revealed the corresponding level transmitter as the source of the concern.
The first attempt to restore the A Train RVLIS cabinet on September 10, 2014 was based upon reworking an inner containment penetration splice. This rework was pursued due to a correlation that was observed between the failed A Train RVLIS RTD and variations in containment temperatures. This rework activity did reveal a loose termination within a spliced connection, which provided reasonable assurance that the source of this concern had been identified. Following recurrence of this concern on September 11, 2014, additional troubleshooting was performed while the loop was failed which revealed the RTD or its corresponding leads as the source of this concern.
Plans and Schedule for Restoring the Instrumentation Channel to OPERABLE status Replacement of the A Train R TD and its corresponding leads will be pursued during the upcoming fall 2014 refueling outage (currently scheduled to begin on October 11, 2014).
The potential for performing an online replacement of the B Train transmitter is currently under evaluation. Replacement of this transmitter will be pursued no later than the forthcoming fall2014 refueling outage.