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Category:Meeting Briefing Package/Handouts
MONTHYEARML24311A1572024-11-0606 November 2024 Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24180A0092024-06-28028 June 2024 July 23, 2024, Portable Lighting Amendment 237 Meeting Slides ML24157A0642024-06-13013 June 2024 Earls 2024 Workshop Presentation ML24071A2102024-03-25025 March 2024 March 25, 2024, Portable Lighting Revised SE Meeting Slides ML24085A2732024-03-21021 March 2024 Comments for March 25, 2024 Meeting on Portable Lighting Revised SE ML23275A1712023-10-16016 October 2023 October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station ULNRC-06767, Presentation Information for Planned Pre-Application Meeting2022-09-0606 September 2022 Presentation Information for Planned Pre-Application Meeting 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 ML22047A0952022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML22047A0942022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21333A1512021-11-29029 November 2021 Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions ML21271A6132021-09-28028 September 2021 Enclosure 2: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21271A6122021-09-28028 September 2021 Enclosure 1: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21211A0712021-07-30030 July 2021 Meeting Slides for Pre-submittal Teleconference to Discuss EP Revision LAR ML21179A0892021-07-13013 July 2021 Background Information July 13, 2021, Pre-Submittal Public Teleconference ML21123A2622021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21123A2602021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21050A2042021-03-31031 March 2021 March 2021 Meeting Slides ML20308A7332020-11-18018 November 2020 Slides for GSI-191 Pre-Submittal Public Teleconference November 18, 2020 ML20248H4672020-09-0404 September 2020 Rict & 50.69 LARs - NRC Pre-Submittal Meeting Slides ML20170A2032020-06-24024 June 2020 6/24/2020 - Pre-Submittal Meeting for Callaway Plant License Amendment Request to Defer Steam Generator Eddy Current Testing ML19247B3842019-09-12012 September 2019 GSI-191 / GL 2004-02 Licensing Amendment Request ML18299A0492018-10-30030 October 2018 Accident Analyses Methodology Transition LAR Public Meeting ML18158A5532018-06-14014 June 2018 Pre-Submittal Meeting for Full Implementation of Alternative Source Term IR 05000482/20174072017-12-22022 December 2017 Summary of Closed Regulatory Conference to Discuss Wolf Creek, Unit 1, Security Inspection Report 05000482/2017407 ML16271A4822016-09-27027 September 2016 Summary of Regulatory Conference to Discuss Safety Significance of Wolf Creek Generating Station Emergency Generator Excitation Diode Apparent Violation ML16236A0952016-08-25025 August 2016 and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16152A1232016-06-0101 June 2016 Strainer Testing for GSI-191 ML16095A0782016-04-12012 April 2016 Slides for the WCGS Meeting Discussion 4/12/16 ML16095A0852016-04-12012 April 2016 Large Scale Head Loss Test Specification 4/12/16 ML16095A0802016-04-12012 April 2016 Large Scale Penetration Test Specification 4/12/16 ML16095A0922016-03-31031 March 2016 Large Scale Penetration and Head Loss Test Plan 4/12/16 ML14188C4812014-07-0707 July 2014 Summary of Annual Assessment Meeting with Wolf Creek Generating Station ML14134A1842014-05-14014 May 2014 Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station ML14050A4022014-02-20020 February 2014 License Renewal Public Meeting Slides 2 20 2014 ML14038A3852014-02-0606 February 2014 1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter ML13218A0212013-08-0707 August 2013 Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13205A2142013-07-30030 July 2013 Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station ML13042A1882013-02-11011 February 2013 01/31/2013 Summary of the Public Meeting to Discuss the Results of the Grand Gulf Nuclear Station License Renewal Inspection IR 05000483/20120092013-01-25025 January 2013 1/17/2013 - Summary of Public Meeting to Discuss the Results of the Callaway Nuclear Plant License Renewal Inspection (05000483-12-009) ML12320A3052012-11-15015 November 2012 Licensee Slides for November 15, 2012 Public Meeting to Discuss License Amendment to Use Reg Guide 1.6 Revision 1 ML12263A3622012-09-20020 September 2012 Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495) ML12241A2922012-08-29029 August 2012 Class 1E AC Meeting Slides August 29, 2012 ML12241A2912012-08-29029 August 2012 UHS Meeting Slides August 29, 2012 ML12191A1742012-07-0909 July 2012 6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation ML1115400922011-06-0303 June 2011 Summary of Annual Performance Assessment Meeting with Union Electric Company to Discuss the Callaway Plant Performance for the NRC Inspection Period Ending December 31, 2010 ML1115304052011-05-26026 May 2011 Licensee Slide'S from 5/26/11 Pre-Application Meeting ML1110104292011-04-11011 April 2011 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010 ML1016901162010-06-16016 June 2010 6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases) ML1016204902010-06-16016 June 2010 Notice of Construction Reactor Oversight Process Category 2 Public Meeting Handout: Wolf Creek 2, Notice of Violation and Proposed Imposition of Civil Penalty, Dated 11/21/1984 2024-06-28
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24311A1572024-11-0606 November 2024 Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24180A0092024-06-28028 June 2024 July 23, 2024, Portable Lighting Amendment 237 Meeting Slides ML24157A0642024-06-13013 June 2024 Earls 2024 Workshop Presentation ML24071A2102024-03-25025 March 2024 March 25, 2024, Portable Lighting Revised SE Meeting Slides ML23275A1712023-10-16016 October 2023 October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station ULNRC-06767, Presentation Information for Planned Pre-Application Meeting2022-09-0606 September 2022 Presentation Information for Planned Pre-Application Meeting 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 ML22047A0942022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML22047A0952022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21333A1512021-11-29029 November 2021 Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions ML21271A6122021-09-28028 September 2021 Enclosure 1: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21271A6132021-09-28028 September 2021 Enclosure 2: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21211A6012021-07-30030 July 2021 Annual Assessment Meeting (Public) ML21123A2622021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21123A2602021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML20310A2232020-11-19019 November 2020 Slides for ERO Staffing pre-submittal Public Teleconference November 19, 2020 (L-2020-LRM-0104) ML20248H4672020-09-0404 September 2020 Rict & 50.69 LARs - NRC Pre-Submittal Meeting Slides ML20170A2032020-06-24024 June 2020 6/24/2020 - Pre-Submittal Meeting for Callaway Plant License Amendment Request to Defer Steam Generator Eddy Current Testing ML19247B3842019-09-12012 September 2019 GSI-191 / GL 2004-02 Licensing Amendment Request ML18158A5532018-06-14014 June 2018 Pre-Submittal Meeting for Full Implementation of Alternative Source Term IR 05000482/20174072017-12-22022 December 2017 Summary of Closed Regulatory Conference to Discuss Wolf Creek, Unit 1, Security Inspection Report 05000482/2017407 ML16236A0952016-08-25025 August 2016 and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16236A0972016-08-25025 August 2016 Operating Corporation - August 25, 2016, Core Design and Safety System Analysis Methodology Transition License Amendment Request Revised ML16152A1232016-06-0101 June 2016 Strainer Testing for GSI-191 ML16095A0782016-04-12012 April 2016 Slides for the WCGS Meeting Discussion 4/12/16 ML14188C4812014-07-0707 July 2014 Summary of Annual Assessment Meeting with Wolf Creek Generating Station ML14134A1842014-05-14014 May 2014 Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station ML14050A4022014-02-20020 February 2014 License Renewal Public Meeting Slides 2 20 2014 ML14038A3852014-02-0606 February 2014 1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter ML13219A1932013-08-0707 August 2013 Licensee Slides (Final), 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13218A0212013-08-0707 August 2013 Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13205A2142013-07-30030 July 2013 Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station ML13121A4892013-05-0101 May 2013 End of Cycle Meeting Summary 4-18-13 ML13042A1882013-02-11011 February 2013 01/31/2013 Summary of the Public Meeting to Discuss the Results of the Grand Gulf Nuclear Station License Renewal Inspection IR 05000483/20120092013-01-25025 January 2013 1/17/2013 - Summary of Public Meeting to Discuss the Results of the Callaway Nuclear Plant License Renewal Inspection (05000483-12-009) ML12320A3052012-11-15015 November 2012 Licensee Slides for November 15, 2012 Public Meeting to Discuss License Amendment to Use Reg Guide 1.6 Revision 1 ML12263A3622012-09-20020 September 2012 Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495) ML12241A2912012-08-29029 August 2012 UHS Meeting Slides August 29, 2012 ML12241A2922012-08-29029 August 2012 Class 1E AC Meeting Slides August 29, 2012 ML12191A1742012-07-0909 July 2012 6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation ML12096A3942012-03-14014 March 2012 Enclosure 5: Callaway Public Meeting Slides ML1115400922011-06-0303 June 2011 Summary of Annual Performance Assessment Meeting with Union Electric Company to Discuss the Callaway Plant Performance for the NRC Inspection Period Ending December 31, 2010 ML1115304052011-05-26026 May 2011 Licensee Slide'S from 5/26/11 Pre-Application Meeting ML1110104292011-04-11011 April 2011 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010 ML1016901162010-06-16016 June 2010 6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases) ML1013404892010-05-14014 May 2010 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009 ML1008804082010-03-25025 March 2010 Licensee Slides Pre-LAR Submittal Telecon ML0933702032009-12-0303 December 2009 Summary of Public Meeting for Wolf Creek Generating Station ML0933801482009-11-20020 November 2009 Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S ML0932104872009-11-17017 November 2009 Summary of Regulatory Conference with Ameren Ue Regarding Callaway Plant 2024-06-28
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Text
HANDOUTS FROM THE LICENSEES (WOLF CREEK NUCLEAR OPERATING CORPORATION AND UNION ELECTRIC COMPANY)
FOR THE MEETING ON AUGUST 16, 2006 ON THE MAIN STEAM ISOLATION VALVE (MSIV) OPERABILITY 1 MSIV/MFIV OPERATION, 24 pages (Wolf Creek Nuclear Operating Corporation)
- 2. MSIV ACTUATOR ISSUE -
SUMMARY
AND HISTORY FOR CALLAWAY, 4 pages (Union Electric Company)
/
MSIV/MFIV OPERATION AGENDA August 16, 2006
- Introductions/Purpose of Meeting
- MSIV/MFIV bescription and Operation
)PURPOSE OF MEETING
- Provide WCNOC's basis for MSIV/MFIV OPERABILITY with one actuation train out of service
" Provide a description of the design and operation of the MSIVs/MFIVs
" Provide a description of the analysis supporting MSIV/MFIV operability
- Discuss associated Technical Specifications compliance 2
MSIV/MFIV tlESCRIPTON/OPERATION
" One MSIV installed in each of the four main steam lines
" One MFIV installed in each of the four main feedwater lines
" Bidirectional, double disc, parallel slide gate valves
" D)esigned to close between 1.5 and 5 seconds to isolate line breaks on either side of valve
" Each valve equipped with two redundant electric/
pneumatic / hydraulic actuation trains such that either actuation train can independently perform the safety function to fast-close the valve on demand
" Both actuation trains simultaneously receive the actuation signal 3
Turbine Building Steam Tunnel Containment Containment Steam Tunnel MF Turbine Building 77.,
Main Feedwater Header
'B' ESFAS Actuating Train (Control Room) (Control Room)
'A' Train 'B' Train MSFIS MSFIS (Control Room) (Control Room)
'A' Actuating 'B' Actuating Train Train Pneumatic/Hydraulic Pneumatic/Hydraulic (Local) (Local)
Valve Actuator (Local)
7crt WefC7KAl PIPING LEGEND
- HYMfAULUC QPC5PXA1E ESTER VUJC)
PNEuMATIC
--...... PILOT
MSIV/MFIV
-I D)ESCRIPTION/OPERA TION
'7 Pneumatic/Hydraulic Actuation Trains
" High Pressure energy stored in hydraulic accumulator
" Operation of solenoid valves results in pneumatic operation of the hydraulic 4-way valves
" Under Fast Close demand, high pressure hydraulic fluid of accumulator is directed to the top of the valve actuator piston
" Each accumulator contains sufficient stored energy and volume to fully close the valve 7
A 1MSIV/MFIV LESCRIPTION/OPERATION
- MSIV/MFIV Actuation Trains n Engineered Safety Features Actuation System (ESFAS) and Main Steam and Feedwater Isolation System (MSFIS)
" Main Steam Line Isolation Signal
" Ctmt Pressure
" Low Steam Line Pressure
" High Steam Pressure Rate
" Feedwater Isolation Signal
" Safety Injection Signal
" SG high-high level
" SG low-low level m Reactor Trip with low Tavg 8
tESIGN BASES
" Provides for isolation of the secondary side of the steam generator to deal with leakage or malfunctions and to isolate non-safety related portions of the system
" Prevent uncontrolled blowdown from more than one steam generator in the event of a main steamline break
" MFIVs
" Provide pressure boundary for Aux Feedwater injection
" Terminate feedwater addition to limit mass/energy release from a break 9
A OESIGN BASES Safety Design Bases (cont)
" Isolates the main steam and feedwater when required
" No single failure can prevent any valve from performing its required function 10
I -SA FETY ANALYSES m Accident analyses crediting closure of MSIVs and MFIVs only require 3 of the 4 valves close to meet acceptance criteria of the event analysis m Most limiting event analysis is the Main Steam Line Break (MSLB) 11
I MAIN STEAM LINE BREAK
- MSLB mass and energy release analysis
" Assess the effect of a high energy line break on the containment
" Number of cases run by the analysis to determine limiting conditions
" Limiting case includes combination of several failures that adversely affect the containment pressure and temperature response 12
MAIN STEAM LINE BREAK
- MSLB mass and energy release analysis (cont)
" Faulted loop M5IV fails to close
" Steam released to ctmt directly from faulted S&
" Steam released to ctmt is supplemented by steam residing in the unisolable steamline
" Non-faulted loop MSIVs close isolating faulted loop from other loops BIowdown B from multiple SGs prevented by closure of MSIV for each non-faulted SG 13
MAIN STEAM LINE BREAK
- MSLB mass and energy release analysis (cont)
" Faulted loop MFIV fails to close
- Mass/Energy added to ctmt from hot water in feedwater piping
- Non-faulted loop MFIV close
" Terminates feedwater flow
" Provides boundary for AFW addition to non-faulted SG 14
MAIN STEAM LINE BREAK
] M5LB mass and energy release analysis (cont)
" MSIV failure on any other loop will result in reduced mass/energy at the break and less limiting results
" MFIV failure on any other loop will result in reduced mass/energy at the break and less limiting results
" Conclusion - MSIV and MFIV failure on the faulted loop scenario has been conservatively accounted for in the MSLB analysis for the limiting containment pressure case 15
OTHER ANALYSIS
" Events where MSIV and MFIV do not close during the event (no effect)
" Events where MSIV or MFIV failure to close will mitigate the response
" Events where transfer of single failure to the MSIV or MFIV mitigates the response 16
A SINGLE FAILURE
" In absence of single failure, with one actuating train out of service, all valves will close
" A single failure is required for a valve to fail to close with one actuating train out of service
" Due to the configuration, any single failure can prevent only one valve from closing
- Thus, as a minimum, with single failure, 3 valves will always close
" Depending upon the failure, the degraded valve may or may not be the one that fails to close 17
TECHNICAL SPECIFICATIONS
- 10 CFR 50.36 - the TSs will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto,
- WCGS TSs support the language chosen (i.e., the singular 'an' vs. plural in SR 3.7.2.2) based on the design and analysis 18
TECHNICAL SPECIFICATIONS
" Section 1.1, Definitions OPERABLE-OPERABILITY - A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function~s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support functions.
" SR 3.0.1 - SRs shall be met.... Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO.
19
TECHNICAL SPECIFICATIONS
" TS 3.7.2, "Main Steam Isolation Valves (MSIVs)," LCO 3.7.2 requires four MSIVs be OPERABLE
" TS 3.7.2 LCO Bases, states in part:
" "This LCO requires that four MSIVs in the steam lines be OPERABLE. The MSIVs are considered OPERABLE when the isolation times are within limits, and they close on an isolation actuation signal."
" TS LCO Bases includes guidance on MSIV OPERABILITY with one actuation train inoperable
" Procedure AP 26C-004, TS OPERABILITY
- Provides additional guidance when determining OPERABILITY for 2 or more valve actuator configurations out of service (this guidance supplements the TS Bases) 20
TECHNICAL SPECIFICATIONS SR 3.7.2.2 requires verifying each MSIV actuates to the isolation position on an actual or simulated actuation signal
" Testing normally performed in MODE 3 during startup from refueling when conditions are consistent with those under which the acceptance criteria was generated
" Testing verifies isolation time, verifies valve actuates to isolation position on an actuation signal, verifies trip actuating device for manual initiation function
" Testing performed on each train (i.e., 4 valves at a time). Each train is tested due to the redundancy and capability of each actuation train to close the valve 21
TECHNICAL SPECIFICATIONS Surveillance testing (cont)
" If valve does not close (i.e., it does not meet the stroke time and does not actuate to the isolation position) - the valve is declared inoperable - it is undetermined at the time of the test the cause for the valve failing to fully close
" SR 3.7.2.2 only requires that the valve actuate to the isolation position - it does not require the testing of both actuation trains
" Both actuation trains are conservatively tested even though only one actuation train is required to support the valve performing its specified safety function 22
" Each MSIV/MFIV has 2 redundant actuation trains
" Only one actuation train required to close each valve
- An MSIV/MFIV is OPERABLE with one actuation train out of service since the valve is capable of performing its specified safety function(s) assuming a single failure.
The valve will perform its isolation function within the bounds of the accident analysis.
23
lCONCLUSION
" SR 3.7.2.2 is met with an actuation train out of service.
" The SR requires actuation of each valve to the isolation position on an actual or simulated actuation signal.
" With one actuation train of one valve out of service on a single valve, the valve will still actuate to the isolation position on an actual actuation signal.
" Safety analyses functional requirement is 3 MSIVs and 3 MFIV must close to assure the acceptance criteria is met
" One actuating train out of service on an MSIV/MFIV will not prevent a minimum of 3 MSIV/MFIV from closing assuming a single failure 24
MSIV Actuator Issue - Summary and History for Callaway Initial Efforts to Address MSIV Actuator Inoperability e MSIV actuator inoperability initially addressed in surveillance procedure used to perform testing on the MSIVs (i.e., OSP-AB-VO001, "Main Steam Valve Operability") during 1980s.
" Technical Specification interpretation (TSI) created 1991 timeframe
- TSI rolled into Operations surveillance procedure during Callaway conversion to Improved Technical Specifications (ITS).
" Requirements for MSIV actuators incorporated into Chapter 16 of the FSAR (the equivalent of a TRM, ORM, etc. at other plants) in 2004 timeframe.
Technical Specification Interpretation CTSI)
" Based on redundancy of actuator design (i.e., recognizing that only one MSIV actuation train is needed for the associated MSIV to close on demand, so that an MSIV is still operable with only one actuator train inoperable).
" An inoperable MSIV actuator train (due to insufficient accumulator pressure, for example) was not viewed to be equivalent to an MSIV itself being inoperable. The MSIV actuator trains were not explicitly addressed by TS 3.7.2.
" Both actuators (for each MSIV) continued to be tested during the performance of applicable surveillances on the MSIVs. Wording in Bases for SR 3.7.2.1 suggested need to do this, but not taken to mean that SR had to be satisfied via both actuators each time. The SR could be met with one/either actuator.
" As an additional prudent measure, TSI was revised (1997 timeframe) in order to impose an allowed outage time (AOT) of 68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br /> (in addition to the 8-hour AOT specified for an inoperable MSIV itself) for an inoperable MSIV actuator train. This restriction was considered to be above and beyond the TS requirements for the MSIVs.
Issue Identified in 2005
- Corrective action document (CAR 200500238) initiated January 2005 to address concerns identified with the basis for the Chapter 16 MSIV actuator requirements/provisions.
" NRC Resident Inspector staff identified issue with respect to the Chapter 16 provisions.
" Various interactions took place with NRR and Region.
- License Amendment Request (LAR) OL-1262 prepared and submitted May 26, 2005.
- Standing Order developed to provide provisions and actions for plant Operators to follow in the event an MSIV actuator(s) is declared inoperable (while requested license amendment was pending).
Subsequent Developments & Current Status
" NRC position expressed in Inspection Report exit meeting conducted on September 26, 2005.
" Refueling Outage (RF-14)- Fall 2005.
" License Amendment 172 issued June 16, 2006.
" Remains as an NRC Unresolved Item at this time.