L-MT-13-058, Responses to Requests for Additional Information Regarding Monticello Overall Integrated Plan Submitted in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrument
| ML13193A324 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/12/2013 |
| From: | Schimmel M Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-MT-13-058, TAC MF0924 | |
| Download: ML13193A324 (18) | |
Text
Xcel Energy Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 July 12, 2013 L-MT 058 10 CFR 2.202 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Responses to Requests for Additional Information Regarding Monticello Nuclear Generating Plant's Overall Integrated Plan Submitted 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) (TAC No. MF0924)
References:
- 1. NRC Email to NSPM, "Monticello Nuclear Generating Plant - Requests for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (TAC No. MF0924)," dated June 7,2013 (ADAMS Accession No. ML13176A331).
- 2. NSPM Letter to NRC, "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)," dated February 28,2013 (ADAMS Accession No. ML13060A447).
- 3. NRC Order EA-12-051, "Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," dated March 12,2012 (ADAMS Accession No. ML12054A679).
- 4. NSPM Letter to NRC, "Initial Status Report 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),"
dated October 29,2012 (ADAMS Accession No. ML12305A383).
Document Control Desk Page 2 On March 12, 2012, the NRC Staff issued Order EA-12-051, "Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation,"
(Reference 3) to all NRC power reactor licensees and holders of construction permits in active or deferred status. The Reference 3 Order was immediately effective and directs Northern States Power Company (NSPM), a Minnesota corporation, d/b/a Xcel Energy, to have a reliable indication of the water level in the spent fuel storage pool for Monticello Nuclear Generating Plant (MNGP). Specific requirements are outlined in Attachment 2 of Reference 3.
On October 29, 2012, NSPM submitted an initial status report (Reference 4) regarding reliable spent fuel pool instrumentation (SFPI), as required by Reference 3.
NSPM provided the overall integrated plan (Reference 2), pursuant to Section IV, Condition C.1 of Reference 3 on February 28, 2013. The overall integrated plan included a description of how compliance with the requirements of Attachment 2 of Reference 3 would be achieved.
On June 7, 2013, the NRC Staff provided requests for additional information (RAI) in Reference 1 regarding the SFPI overall integrated plan of Reference 2. The enclosure to this letter provides NSPM's responses to the NRC RAls. The NRC has indicated in Reference 1 that if requested information is not available at the time of submittal, NSPM is to provide the date the information will be submitted. NSPM's current plan is to begin the design phase for the SFPI by January 2014, with design completion expected in July 2014. Based on this schedule, the majority of the RAls cannot be fully answered at this time. The requested information will be provided in either the August 2014 or the February 2015 six-month status updates as indicated in the individual RAI responses.
Please contact Lynne Gunderson, Licensing Engineer, at 612-396-0173, if additional information or clarification is required.
Document Control Desk Page 3 Summary of Commitments:
This letter makes no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on July 12, 2013.
mJ£~
Mark A. Schimmel Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Administrator, Region III, USNRC Director of Nuclear Reactor Regulation (NRR), USNRC NRR Project Manager, MNGP, USNRC Senior Resident Inspector, MNGP, USNRC
ENCLOSURE Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
1.0 INTRODUCTION
By letter dated February 28, 2013 (Reference 2), Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy submitted an Overall Integrated Plan (OIP) in response to the March 12,2012, U.S. Nuclear Regulatory Commission (NRC) Order modifying licenses with regard to requirements for Reliable Spent Fuel Pool (SFP) Instrumentation (Reference 3) for the Monticello Nuclear Generating Plant (MNGP). The NRC staff endorsed Nuclear Energy Institute (NEI) 12-02, "Industry Guidance for Compliance with NRC Order EA-12-051, to Modify Licenses with Regard to Reliable SFP Instrumentation," Revision 1, dated August 2012 (Reference 5), with exceptions as documented in Interim Staff Guidance (lSG) 2012-03, "Compliance with Order EA-12-051, Reliable SFP Instrumentation," Revision 0, dated August 29,2012 (Reference 4).
The NRC staff reviewed Reference 2 and determined that the Request for Additional Information (RAI) in Reference 1 was needed to complete the NRC's Technical Review (Reference 1). If any part of the requested information is not available by the July 19, 2013, the response date for the RAls, NSPM will provide the date the information will be submitted.
This enclosure provides the NSPM response to the RAI for the OIP and, in cases where design information is not yet available, the date the information will be submitted. This enclosure quotes each RAI in italics followed by the NSPM response.
2.0 RESPONSES FOR LEVELS OF REQUIRED MONITORING NRC RAI-1:
The OIP states, in pari, that Level 1 is the level that is adequate to suppori operation of the normal fuel pool cooling system. Currently, the level in the fuel pool is maintained at a constant level due to overflow weirs that spill into skimmer surge tanks. This configuration permits the total water volume to change within the skimmer surge tanks but it does not impact the spent fuel pool water level. The minimum level, without weirs, where the skimmer surge tank and the spent fuel pool become decoupled is 37 feet and 3 inches from the bottom of the spent fuel pool. This level will be used for Level 1. Allowance for instrumentation accuracy will be applied to this setpoint.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Level 2 represents the range of water level where any necessary operations in the vicinity of the spent fuel pool can be completed without significant dose consequences from direct gamma radiation from the stored spent fuel. Based on the guidance in Section 2.3 of NE112-02, Level 2 is 10 feet above the top of the spent fuel rack, which corresponds to 24 feet and 9 inches from the bottom of the MNGP spent fuel storage pool. Therefore, Level 2 will be 24 feet and 9 inches from the bottom of the spent fuel storage pool. Allowance for instrumentation accuracy will be applied to this setpoint.
Level 3 is the level where the fuel remains covered and actions to implement make-up water addition should no longer be deferred. Level 3 corresponds nominally to the highest point of the fuel rack in the spent fuel pool. Level 3 will be 14 feet and 9 inches from the bottom of the spent fuel storage pool. Allowance for instrumentation accuracy will be applied to this setpoint.
Please provide the following:
a) For Level 1, specify how the identified location represents the HIGHER of the two points described in the NEI 12-02 guidance for this level.
b) A clearly labeled sketch depicting the elevation view of the proposed typical mounting arrangement for the portions of instrument channel consisting of permanent measurement channel equipment (e.g., fixed level sensors and/or stilling wells, and mounting brackets). Indicate on this sketch the datum values representing Level 1, Level 2, and Level 3 as well as the top of the fuel. Indicate on this sketch the portion of the level sensor measurement range that is sensitive to measurement of the fuel pool level, with respect to the Level 1, Level 2, and Level 3 datum points.
c) The OIP states, "An evaluation of other hardware stored in the spent fuel pool will be conducted as part of the design process to ensure other hardware will not adversely interact with the fixed instrument locations. Given the potential for JJ varied dose rates from hardware stored in the SFP, describe how level 2 will be adjusted to other than the elevation provided in section 2 above.
NSPM Response:
a) The fuel pool cooling system returns cooled SFP water to the pool. The SFP level rises until it is slightly above the top of the weirs in the SFP walls, at which point the water flows into the skimmer surge tanks and then to the fuel pool cooling and cleanup pumps and fuel pool heat exchangers before returning to the SFP. A steady-state SFP level is reached slightly above the weir height.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
The water level in the skimmer surge tanks, not the water level in the SFP, provides the required net positive suction head to the fuel pool cooling and cleanup pumps. The fuel pool cooling and cleanup pumps are tripped on low level in the skimmer surge tank.
The minimum SFP level that assures water is delivered to the fuel pool cooling and cleanup pumps is a SFP level that is above the height of the weir. Therefore, the SFP "level that is adequate to support operation of the normal fuel pool cooling system" is slightly above the height of the weir. In the MNGP OIP, Level 1 was established based on the minimum SFP level, without the weirs attached, where the skimmer surge tank and the SFP become decoupled.
Therefore, Level 1 for Monticello appropriately reflects the intent of the first of the two bullets in NEI 12-02, Section 2.3.1.
b) The sketch on the next page provides an elevation view of the Monticello SFP showing the proposed Level 1, 2, and 3 values, the top of the fuel racks and the bottom of the SFP. The sketch also depicts the proposed mounting arrangement and level sensor range. NSPM's current plan is to begin the design phase for the Spent Fuel Pool Instrumentation (SFPI) system by January 2014. It is anticipated that the final mounting arrangement will be available upon design completion in July 2014. Final mounting arrangement will be provided with the August 2014 six-month status report as part of response to RAI 3.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Figure - Simplified Elevation Sketch (Not to Scale)
- e~~~~:t~u~e;~ l _________ ~ _______________ Refuel Floor _ 38' 9" Adjustable _~___________ ~_::::::::::::: ~~~~~ ~~~;,~:vel Weir --- /" (Lowest weir height)
Skimmer Surge Tank Proposed Sensor Range
---1--- LEVEL 2 - 24' 9" 10' rT""T""l"""""'''''"TTTTTT"l - - J--- LEVEL 3 - 14' 9" Top of Rack
..,.------- Fuel Racks To Fuel Pool Cooling and Cleanup Pumps Bottom of Spent L~L:~Lt:t:==t:I~ _____ . Fuel Pool- 0' c) As noted in the RAI, the MNGP alP, Section 3.3, Mounting, stated that an evaluation of other stored hardware will be conducted as part of the design process. NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
3.0 INSTRUMENT DESIGN FEATURES NRC RAI-2 3.2 Arrangement The alP states, in pari, that Page 5 of 15
Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
The probe for the primary channel level transmitter will be located near or in a corner of the spent fuel pool to utilize the inherent shielding from missiles. The final length, location, and mounting of the probe will be determined during the design process. The probe for the backup channel level transmitter will be located across the spent fuel pool from the probe of the primary level transmitter. The backup channel probe will be located in or near a different corner of the pool. The final length, location and mounting of the backup channel probe will be determined during the design process. The primary and backup level transmitter probes will be located in separate corners, which will allow separation between the probes and will also provide protection against a single missile damaging both the primary and the backup spent fuel {Jool probes.
Please provide a clearly labeled sketch or marked-up plant drawing of the plan view of the SFP area, depicting the SFP inside dimensions, the planned locations/ placement of the primary and back-up SFP level sensor and mounting brackets, and the proposed routing of the cables that will extend from the sensors toward the location of the read-out/display device.
NSPM Response:
The planned locations for the primary and back-up level sensors, the mounting brackets and the proposed routing of the cables have not been determined. The final component locations will be available upon completion of the final design. NSPM's current plan is to begin the design phase for the SF PI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
NRC RAI-3 3.3 Mounting The OIP states, in part, that Both the primary and backup system mounting will be installed as Seismic Category I to meet the NRC JLO-ISG-2012-03 and NE112-02 guidance requirements. An evaluation of other hardware stored in the spent fuel pool will be conducted as part of the design process to ensure other hardware will not adversely interact with the fixed instrument locations.
Please provide the following:
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) a) The design criteria that will be used to estimate the total loading on the mounting de vice (s), including static weight loads and dynamic loads. Describe the methodology that will be used to estimate the total loading, inclusive of design basis maximum seismic loads and the hydrodynamic loads that could result from pool sloshing or other effects that could accompany such seismic forces.
b) A description of the manner in which the level sensor (and stilling well, if appropriate) will be attached to the refueling floor and/or other support structures for each planned point of attachment of the probe assembly. Indicate in a schematic the portions of the level sensor that will serve as points of attachment for mechanical/mounting or electrical connections.
c) A description of the manner by which the mechanical connections will attach the level instrument to permanent SFP structures so as to support the level sensor assembly.
d) Address how other hardware stored in the SFP will not create adverse interaction with the fixed instrument location(s).
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
NRC RAI-4 3.4 Qualification The OIP states, in part, that The primary and backup instrument channels will be qualified through the use of an augmented quality assurance process that meets the NRC JLD-ISG-2012-03 and NEI 12-02 guidance requirements. The following sections describe the conditions and details of the qualification.
The applicable primary and backup instrument channel components will be qualified for reliable operation following a seismic event. The methods used to qualify components will be consistent with the guidance of NEI 12-02 and the exceptions and clarifications to NE112-02 provided by the NRC Staff in NRC JLD-ISG-2012-03.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Please provide the following:
a) A description of the specific method or combination of methods you intend to apply to demonstrate the reliability of the permanently installed equipment under Beyond-Design-Basis (BOB) ambient temperature, humidity, shock, vibration, and radiation conditions.
b) A description of the testing and/or analyses that will be conducted to provide assurance that the equipment will petform reliably under the worst-case credible design basis loading at the location where the equipment will be mounted.
Include a discussion of this seismic reliability demonstration as it applies to a) the level sensor mounted in the SFP area, and b) any control boxes, electronics, or read-out and re-transmitting devices that will be employed to convey the level information from the level sensor to the plant operators or emergency responders.
c) Please provide a description of the specific method or combination of methods that will be used to confirm the reliability of the permanently installed equipment following seismic conditions to maintain its required accuracy.
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
NRC RAI-5 3.5 Independence The OIP states, in part, that The primary channel will be independent of the backup channel. Both channels will have their own probes located in separate corners of the spent fuel pool with separate cable routes and separate electronics. Where routed in conduit and cable trays, the primary and backup channel cabling will be routed in separate conduit or cable trays to achieve independence. Power supply independence is addressed in Section 3.6.
Please provide the following:
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) a) A description of how the two channels of the proposed level measurement system meet this requirement so that the potential for a common cause event to adversely affect both channels is precluded.
b) Furiher information on how each level measurement system, consisting of level sensor electronics, cabling, and readout devices will be designed and installed to address independence through the application and selection of independent power sources, the use of physical and spatial separation, independence of signals sent to the location(s) of the readout devices, and the independence of the displays.
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
NRC RAI-6 3.6 Power supplies The OIP states, in pari, that The instrument channels will each have an independent backup battery power supply that will be capable of supporiing the instrument until repowered as specified by the mitigating strategies of NRC Order EA-12-049 and NEI12-06. Any onsile generators used as an alternate power source and replaceable batteries used for instrument channel function will have sufficient capacity to maintain level indication function until offsile resource availability is reasonably assured. Any poriable power supplies used will be stored consistent with the requirements of NRC Order EA-12-049 and NEI12-06.
The design process will determine the normal power source, battery power supply, and any additional power sources required for the instrument channels. Both the primary and the backup instrument channels will maintain their design accuracy without recalibration following a power interruption or change in the power source as required by NRC Order EA-12-051.
Please provide the following:
a) A description of the electrical AC power sources and capacities for the primary and backup channels.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) b) If the level measurement channels are to be powered through a battery system (either directly or through an uninterruptible power supply (UPS)), provide the design criteria that will be applied to size the battery in a manner that ensures, with margin, that the channel will be available to run reliably and continuously following the onset of the BOB event for the minimum duration needed, consistent with the plant FLEX Program plans.
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
NRC RAI-7 3.7 Accuracy The OIP states, in part, that The accuracy will be consistent with the guidelines of NRC JLD-ISG-2012-03 and NEI 12-02. The primary and backup instrument channels will maintain their design accuracy without requiring recalibration following a power interruption or change in the power source as required by NRC Order EA-12-051. The total loop accuracy of the primary system and the backup system will be determined for the entire span (Level 1 through
- 3) during the design process.
Please provide the following:
a) An estimate of the expected instrument channel accuracy performance (e.g., -in
% span) under both a) normal SFP level conditions (approximately Level 1 or higher) and b) at the BOB conditions (i.e., radiation, temperature, humidity, post-seismic and post-shock conditions) that would be present if the SFP level were at the Level 2 and Level 3 datum points.
b) A description of the methodology that will be used for determining the maximum allowed deviation from the instrument channel design accuracy that will be employed under normal operating conditions as an acceptance criterion for a calibration procedure to flag to operators and to technicians that the channel requires adjustment to within the normal condition design accuracy.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
NSPM Response:
Setpoints will be determined following Monticello procedure ESM-03.02, "Design Requirements, Practices & Topics (Instrumentation & Controls)." This procedure allows for several options for setpoint determination. Determination of setpoints using this procedure is part of the NSPM design process. NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
NRC RAI-8 3.8 Testing The OIP states, in pari, that Instrument channel design will provide for routine testing and calibration. The primary and backup instrumentation channels will be capable of in-situ testing and calibration.
Testing will be consistent with the guidelines of NRC JLD-ISG-2012-03 and NEI 12-02 and will be petformed in accordance with station procedures.
Please provide the following:
a) A description of the capability and provisions the proposed level sensing equipment will have to enable periodic testing and calibration, including how this capability enables the equipment to be tested in-situ.
b) A description of how such testing and calibration will enable the conduct of regular channel checks of each independent channel against the other, and against any other permanently-installed SFP level instrumentation.
c) A description how functional checks will be petformed and the frequency at which they will be conducted. Describe how calibration tests will be petformed, and the frequency at which they will be conducted. Provide a discussion as to how these surveillances will be incorporated into the plant surveillance program.
d) A description what preventative maintenance tasks are required to be petformed during normal operation, and the planned maximum surveillance interval that is necessary to ensure that the channels are fully conditioned to accurately and reliably petform their functions when needed.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
NRC RAI-9 3.9 Display The OIP states, in pari, that The primary and backup instrumentation displays will be installed per the requirements of NRC JLD-ISG-2012-03 and NE112-02, Section 3.9. The primary display will be located in the control room and will provide the operators an on-demand or continuous display of the spent fuel pool level. The backup display will be located in an area which meets the four characteristics defined in NE112-02, Section 3.9. The location for both of the electronics control cabinets will be determined during the design process.
Please provide the following:
a) The specific location for the backup instrument channel display.
b) If the backup display location is other than the main control room, then provide justification for prompt accessibility to displays including primary and alternate route evaluation, habitability at display location(s), continual resource availability for personnel responsible to promptly read displays, and provisions for communications with decision makers for the various SFP drain down scenarios and external events.
c) The reasons justifying why the locations selected enable the information from these instruments to be considered "promptly accessible" to various drain-down scenarios and external events.
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. The requested information will be provided with the August 2014, six-month status report.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) 4.0 PROGRAM FEATURES NRC RAI-10 4.2 Procedures The OIP states, in pari, that Procedures will be developed for both the primary and backup instrument channels consistent with the requirements of NRC JLO-ISG-2012-03 and NEI 12-02, Section 4.2.
This will include procedures for the maintenance, operation, testing, calibration and normal/abnormal response of the primary and backup instrument channels. As described in Section 3. 1.4, the duration of time required for both the primary and backup spent fuel pool instrumentation channels to be functional will be coordinated with the mitigating strategies being developed for NRC Order EA-12-049 and NEI12-06.
Please provide a description of the standards, guidelines and/or criteria that will be utilized to develop procedures for inspection, maintenance, repair, operation, abnormal response, and administrative controls associated with the SFP level instrumentation.
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. Program and process features will be developed after that date. Therefore, the requested information will be provided with the February 2015, six-month status report.
NRC RAI-11 4.2 Testing and Calibration The OIP states, in pari, that Testing and calibration of the primary and backup instrument channels will be established and implemented by existing MNGP processes, and will be scheduled in intervals such that the design accuracy of the instrument channels is maintained.
Surveillance or testing intervals will be established per the recommendations of NEI 12-02, Section 4.3. Allowed out of service time as identified in NE112-02 will be incorporated consistent with the programmatic process used for compliance with NRC Order EA-12-49.
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
Please provide the following:
a) Further information describing the maintenance and testing program the licensee will establish and implement to ensure that regular testing and calibration is petformed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Include a description of your plans for ensuring that necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment.
b) A description of how the guidance in NE112-02 section 4.3 regarding compensatory actions for one or both non-functioning channels will be addressed.
c) A description of what compensatory actions are planned in the event that one of the instrument channels cannot be restored to functional status within 90 days.
NSPM Response:
NSPM's current plan is to begin the design phase for the SFPI system by January 2014, with design completion expected in July 2014. Program and process features will be developed after that date. The requested information will be provided with the February 2015, six-month status report.
5.0 REFERENCES
- 1. NRC Email to NSPM, "Monticello Nuclear Generating Plant - Requests for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (TAC No. MF0924)," dated June 7, 2013 (ADAMS Accession No. ML13176A331).
- 2. NSPM Letter to NRC, "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)," dated February 28,2013 (ADAMS Accession No. ML13060A447).
- 3. NRC Order EA-12-051, "Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," dated March 12, 2012 (ADAMS Accession No. ML12054A679).
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Monticello Nuclear Generating Plant Responses to Requests for Additional Information Regarding Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
- 4. NRC Interim Staff Guidance JLD-ISG-2012-03, "Compliance with Order EA-12-051, Reliable Spent Fuel Pool Instrumentation," Revision 0, dated August 29,2012 (ADAMS Accession No. ML12221A339).
- 5. 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 2012 (ADAMS Accession No. ML12240A307).
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