RS-13-035, Quad Cities, Units 1 & 2 - Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051): Difference between revisions

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#REDIRECT [[RS-13-035, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)]]
| number = ML13060A124
| issue date = 02/28/2013
| title = Quad Cities, Units 1 & 2 - Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
| author name = Kaegi G T
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000254, 05000265
| license number = DPR-029, DPR-030
| contact person =
| case reference number = EA-12-051, RS-13-035
| document type = Letter type:RS, Operating Plan
| page count = 12
| project =
| stage = Other
}}
 
=Text=
{{#Wiki_filter:U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-051 February 28, 2013 Reference 3, Appendix A-2 contains the specific reporting requirements for the Overall Integrated Plan. The information in the enclosure provides the Quad Cities Nuclear Power Station, Units 1 and 2 Overall Integrated Plan pursuant to Appendix A-2 of Reference 3. The enclosed Integrated Plan is based on conceptual design information. Final design details and associated procedure guidance, as well as any revisions to the information contained in the Enclosure, will be provided in the 6-month Integrated Plan updates required by Reference 1.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.
 
==Enclosure:==
 
1.Quad Cities Nuclear Power Station, Units 1 and 2 Reliable Spent Fuel Pool Instrumentation (SFPI) Overall Integrated Plan NRC Senior Resident Inspector - Quad Cities Nuclear Power Station, Units 1 and 2 NRC Project Manager, NRR - Quad Cities Nuclear Power Station, Units 1 and 2 Mr. Robert J. Fretz, Jr, NRRIJLD/PMB, NRC Illinois Emergency Management Agency - Division of Nuclear Safetyth J. 
 
(9 pages)
(9 
 
of Order EA-12-051
-
Quad Cities Station is a two unit BWR Station. The two units share a common ReactorBuilding (RB) refueling floor and two interconnected Spent Fuel Pools (SFP). Normal SFP water level is approximately at elevation 689' 6". Top of the spent fuel racks is elevation 666' 2" and top of active fuel is elevation 665' 5" (Ref. 5).Note: In all subsequent discussions in this plan unless otherwise noted, dimensions will be referenced to elevation 666' 2" which is the top of the fuel racks in either unit.
The installation of reliable level instrumentation for the SFPs associated with Unit 1 and Unit 2 is scheduled for completion by the end of Q1 R23 (Spring 2015) based on the end of the second refueling outage for Unit 1 following submittal of this integrated plan. This is the earlier outage sequence of the units discharging to the pools. Unit 1 and Unit 2 discharge irradiated fuel to a set of two interconnected spent fuel storage pools.
With the exception of limited time periods for maintenance or non-refueling operations, administrative controls maintain the gates between the following pools open: Unit 1 SFP and the Transfer Canal, and Unit 2 SFP and the Transfer Canal. Thus, the Unit 1 and Unit 2 pools are normally interconnected and at the same water level when the water level in either SFP is 1 foot above the top of the spent fuel storage racks.
 
Complete and Issue SFPI Modification PackageComplete SFPI Installation and Put Into Service For both units, indicated level on either primary or backup instrument channel must be greater than 23 feet 1 inch (elevation 689' 3") plus instrument accuracy above the top of the storage racks based on the design accuracy of the instrument channel (which is to be determined) and a resolution of 1 foot or better for both the primary and backup instrument channels. This is based on the 11 inch opening of the SFP weir gate design demonstrating a water level above 23 feet 1 inch (elevation 689' 3") is adequate for normal fuel pool cooling system operation.
For both units, indicated level on either the primary or backup instrument channel of greater than 10 feet (elevation 676' 2") plus instrument channel accuracy above the top of the storage racks basedon specification of this level as adequate in NRC JLD-ISG-2012-03 (Ref. 2) and NEI 12-02 (Ref. 3), the specified design accuracy of the instrument channel, and the relatively low sensitivity of dose rates to changes in water depth at this level. Thismonitoring level ensures there is an adequate water level to provide substantial radiation shielding for a person standing on the spent fuel pool operating deck from direct gamma radiation from stored spent fuel.
202013 202013 102014 402014 102015 2 
 
For both units, indicated level on either the primary or backup instrument channel of greater than 0 feet (elevation 666' 2")
plus instrument channel accuracy above the top of the storage racks based upon the design accuracy (which is to be determined) of the instrument channel for both the primary and backup instrument channels. This monitoring level assures that water is covering the stored fuel seated in the racks.
The design of the instruments will be consistent with the guidelines of NRC JLD-ISG-2012-03 (Ref. 2) and NEI 12-02 (Ref. 3). Specifically, the channels will be designed as discussed below:
The primary instrument channel level sensing components will be located and permanently mounted in the Unit 1 SFP. The primary instrument channel will provide continuous level indication over a minimum range of approximately 23 feet 7 inches from the high pool level elevation of 689' 9" (Normal + 3") to the top of the spent fuel racks at elevation 666' 2". This continuous level indication will be provided by a guided wave radar system, submersible pressure transducer, or other appropriate level sensing technology that will be
 
determined during the detailed engineering design phase of the project.
The backup instrument channel level sensing components will be located and permanently mounted in the Unit 2 SFP. The backup instrument channel will provide continuous level indication over a range from the high pool level elevation the same as primary to the top of the spent fuel racks at elevation the same as primary. This continuous level indication will be provided by the same level sensing technology as the primary instrument channel.
Reliability of primary and backup instrument channels will be assured by conformance with the guidelines of NRC JLD-ISG-2012-03 (Ref. 2) and NEI 12-02 (Ref. 3) as discussed below under Design Features and Program Features sections. Both primary and backup level instrumentation channels will be functional at all times when there is fuel in the SFP with allowance for maintenance, testing or repair as described in NEI 12-02 (Ref. 3).
Reliability will be established through the use of an augmented quality assurance process (e.g., a process similar to that applied to the site fire protection program).
3 
 
Instrument channel design will be consistent with the guidance of NRC JLD-ISG-2012-03 (Ref. 2) and NEI 12-02 (Ref. 3).
The current plan is to install SFP level sensors in the southwest corner of the Unit 1 SFP and in the northwest corner of the Unit 2 SFP separated by a distance in excess of 50 feet. The sensors themselves will be mounted, to the extent practical, near the pool walls and below the pool curb to minimize their exposure to damaging debris and not interfere with SFP activities. Instrument channel electronics and power supplies will be located in seismic and missile protected areas either below the SFP operating floor or in buildings other than the RB.The areas to be selected will provide suitable radiation shielding and environmental conditions for the equipment consistent with instrument manufacturer's recommendations.
Equipment and cabling for power supplies and indication for each channel will be separated equivalent to that provided for redundant safety related services as required by the Quad Cities design basis.
Design of the mounting of the sensors in the SFP shall be consistent with the seismic Class I criteria. Installed equipment will be verified to be seismically adequate for the seismic motions associated with the maximum seismic ground motion considered in the design of the plant area in which it is installed.
Reliability of both instrument channels will be demonstrated via an appropriate combination of design, analyses, operating experience, and/or testing of
 
channel components for the following sets of parameters:conditions in the area of instrument channel component use for all instrument components,
 
Temperature, humidity and radiation levels consistent with the conditions in the vicinity of the SFP and the area of use considering normal operation, event and post-event conditions for no fewer than seven days post-event or until off-site resources 4 
 
can be deployed by the mitigating strategies resulting from Order EA-12-049 (Ref. 4) will be addressed in the detailed design engineering phase of the project. Examples of post-event (beyond-design-basis) conditions to be considered are:radiological conditions for a normal refueling quantity of freshly discharged (100 hour) fuel with SFP water level 3 as described in Order EA-12-051,temperature of 212 degrees F and 100% relative humidity environment,boiling water and/or steam environment, Components of the instrument channels will be qualified for shock and vibration using one or more of the following methods:components are supplied by manufacturers using commercial quality programs (such as ISO9001, "Quality management systems -Requirements")
with shock and vibration requirements included in the purchase specification at levels commensurate with portable hand-held device or transportation applications;components have substantial history of operational reliability in environments with significant shock and vibration loadings, such as portable hand-held device or transportation applications; or For seismic effects on instrument channel components used after a potential seismic event for only installed components (with the exception of battery chargers and replaceable batteries), the following measures will be used to verify that the design and installation is adequate.
Applicable components are rated by the manufacturer (or otherwise tested) for seismic effects at levels commensurate with those of postulated design basis event conditions in the area of instrument channel component use using one or more of the following methods:
5 Quad Cities instrument channel components use known operating principles and are supplied by manufacturers with commercial quality programs (such as IS09001). The procurement specification and/or instrument channel designshall include the seismic requirements and specify the need for commercial design and testing under seismic loadings consistent with design basis values at the installed locations;substantial history of operational reliability in environments with significant vibration, such as for portable hand-held devices or transportation applications.
Such a vibration design envelope shall be inclusive of the effects of seismic motion imparted to the components proposed at the location of the proposed installation;adequacy of seismic design and installation is demonstrated based on the guidance in Sections 7, 8, 9, and 10 of IEEE Standard 344-2004, "IEEE Recommended Practice for Seismic Qualification of Class 1 E Equipment forNuclear Power Generating Stations", or a substantially similar industrial standard;demonstration that proposed devices are substantially similar in design to models that have been previously tested for seismic effects in excess of the plant design basis at the location where the instrument is to be installed (g-levels and frequency ranges); or The primary instrument channel will be independent of the backup instrument channel. This independence will be achieved through physical and electrical separation of each channels' components commensurate with hazard and electrical isolation needs.
Each channel will be normally powered from a different 120Vacbus.Upon loss of normal ac power, individual channel installed batteries will automatically maintain continuous channel operation. The batteries will be replaceable and be sized to maintain channel operation until off-site resources can be deployed by the mitigating strategies resulting from Order EA-12-049 (Ref. 4).6 
 
Additionally, each channel will have provisions for connection to another suitable power source.
The instrument channels will be designed to maintain their design accuracy following a power interruption or change in power source without recalibration. Instrument channel accuracy, to be determined during detailed design, will consider Spent Fuel Pool conditions (e.g., saturated water, steam environment, concentrated borated water), as well as other applicable radiological and environmental conditions, and include display accuracy.
Instrument channel accuracy will be sufficient to allow trained personnel to determine when the actual level exceeds the specified lower level of each indicating range (levels 1, 2 or 3) without conflicting or ambiguous indications.
Instrument channel design will provide for routine testing and calibration consistent with the guidelines of NRC JLD-ISG-2012-03 (Ref. 2) and NEI 12-02 (Ref.
3).Details will be determined during detailed design engineering.
The primary and backup instrument displays will be located at the control room, alternate shutdown panel, or other appropriate and accessible location. Thespecific location will be determined during detailed design.An appropriate and accessible location will include the following characteristics:
occupied or promptly accessible to the appropriate plant staff giving appropriate consideration to various drain down scenarios,outside the area surrounding the SFP floor (e.g., an appropriate distance from the radiological sources resulting from an event impacting the Spent Fuel Pool), i inside a structure providing protection against adverse weather, and outside of any Very High radiation areas or LOCKED HIGH RAD AREA during normal operation.
Personnel performing functions associated with these SFP level instrumentation channels will be trained to perform the job specific functions
 
necessary for their assigned tasks (maintenance, calibration, surveillance, etc.). This training will be consistent with equipment vendor guidelines, instructions and recommendations. The Systematic Approach to Training (SAT) will be used to identify the population to be trained and to determine the initial and continuing elements of the required training. Training will be completed prior to placing the instrumentation in service.
Procedures will be developed using guidelines and vendor instructions to address the maintenance, operation and abnormal response issues associated with the primary and backup channels of SFP instrumentation.If, at the time of an event or thereafter until the unit is returned to normal service, an instrument channel ceases to function, its function will be recovered within a period of time consistent with the emergency conditions that may exist at the time.If, at the time of an event or thereafter until the unit is returned to normal service, an instrument channel component must be replaced, it may be replaced with a commercially available component that may or may not meetall of the qualifications noted above to maintain instrument channel functionality.
The testing and calibration of the instrumentation will beconsistent with vendor recommendations or other documented basis. Calibration will be specific to the mounted instruments and the displays. Instrument performance will be trended as described in Exelon procedural requirements.
Quad Cities is not requesting relief from the requirements of Order EA-12-051 (Ref. 1) or the guidance in NRC JLD-ISG-2012-03 (Ref. 2) at this time.Consistent with the requirements of Order EA-12-051 (Ref. 1) and the guidance in NRC JLD-ISG-2012-03 (Ref. 2), Exelon's six-month reports will delineate progress made, any proposed changes in compliance methods, updates to the schedule, and if needed, requests for relief and their basis.
calibration, 8 
 
2.NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, Revision 0, dated August 29, 2012 3.NEI 12-02, Industry Guidance for Compliance with NRC Order EA-12-051, "To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation", Revision 1, dated August 24, 2012 4.NRC Order Number EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events, dated March 12, 2012 5.Quad Cities UFSAR Chapter 9.19}}

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