ML13295A674

Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation

ML13295A674
Person / Time
Site:	Comanche Peak
Issue date:	11/04/2013
From:	Balwant Singal Plant Licensing Branch IV
To:	Flores R Luminant Generation Co
Singal B
References
TAC MF0862, TAC MF0863
Download: ML13295A674 (34)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Rafael Flores Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Luminant Generation Company LLC P.O. Box 1002 Glen Rose, TX 76043 November 4, 2013

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 - INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION REGARDING THE OVERALL INTEGRATED PLAN FOR IMPLEMENTATION OF ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION (TAC NOS. MF0862 AND MF0863)

Dear Mr. Flores:

On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12054A679), to all power reactor licensees and holders of construction permits in active or deferred status. This order requires the licensee to have a reliable indication of the water level in associated spent fuel storage pools capable of supporting identification of the following pool water level conditions by trained personnel: (1) level that is adequate to support operation of the normal fuel pool cooling system, (2) level that is adequate to provide substantial radiation shielding for a person standing on the spent fuel pool operating deck, and (3) level where fuel remains covered and actions to implement make-up water addition should no longer be deferred.

By letter dated February 28, 2013 (ADAMS Accession No. ML13071A344, Luminant Generation Company LLC (the licensee) provided the Overall Integrated Plan (OIP) for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2, describing how it will achieve compliance with of Order EA-12-051 by fall2014, for Unit 1, and fall2015, for Unit 2. By letter dated June 7, 2013 (ADAMS Accession No. ML13141A626), the NRC staff sent a request for additional information (RAI) to the licensee. The licensee provided supplemental information by letters dated July 3, 2013 (ADAMS Accession No. ML13193A014), and August 28, 2013 (ADAMS Accession No. ML13252A078).

The NRC staff has reviewed these submittals with the understanding that the licensee will update its OIP as implementation of the Order progresses. With this in mind, the staff has included an interim staff evaluation with this letter to provide feedback on the OIP. The staff's findings in the interim staff evaluation are considered preliminary and will be revised as the OIP is updated. As such, none of the staff's conclusions are to be considered final. A final NRC staff evaluation will be issued after the licensee has provided the information requested.

The interim staff evaluation also includes RAis, response to which the NRC staff needs to complete its review. The licensee should provide the information requested in the 6-month status updates, as the information becomes available. However, the staff requests that all information be provided by October 31, 2014, to ensure that any issues are resolved prior to the date by which the licensee must complete full implementation of Order EA-12-051. The licensee should adjust its schedule for providing information to ensure that all this information is provided by the requested date.

If you have any questions regarding this letter, please contact me at 301-415-3016 or via e-mail at Balwant.Singal@nrc.gov.

Docket Nos. 50-445 and 50-446

Enclosure:

Interim Staff Evaluation and Request for Additional Information cc w/encl: Distribution via Listserv Sincerely,

£:,~----\\ ~1~~

Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE OVERALL INTEGRATED PLAN IN RESPONSE TO ORDER EA-12-051, RELIABLE SPENT FUEL POOL INSTRUMENTATION LUMINANT GENERATION COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446

1.0 INTRODUCTION

On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Order EA-12-051, "Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12054A679), to all power reactor licensees and holders of construction permits in active or deferred status. This order requires, in part, that all operating reactor sites have a reliable means of remotely monitoring wide-range spent fuel pool (SFP) levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis (BOB) external event. The order required all holders of operating licenses issued under Title 10 of the Code of Federal Regulations ( 10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities," to submit to the NRC an Overall Integrated Plan (OIP) by February 28, 2013.

By letter dated February 28, 2013 (ADAMS Accession No. ML13071A344, Luminant Generation Company LLC (the licensee) provided the OIP for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2, describing how it will achieve compliance with Attachment 2 of Order EA-12-051 by fall2014, for Unit 1, and fall2015, for Unit 2. By letter dated June 7, 2013 (ADAMS Accession No. ML13141A626), the NRC staff sent a request for additional information (RAI) to the licensee. The licensee provided supplemental information by letters dated July 3, 2013 (ADAMS Accession No. ML13193A014), and August 28, 2013 (ADAMS Accession No. ML13252A078).

2.0 REGULATORY EVALUATION

Order EA-12-051 requires all holders of operating licenses issued under 10 CFR Part 50, notwithstanding the provisions of any Commission regulation or license to the contrary, to comply with the requirements described in Attachment 2 to the Order except to the extent that a more stringent requirement is set forth in the license. Licensees shall promptly start implementation of the requirements in Attachment 2 to the Order and shall complete full implementation no later than two refueling cycles after submittal of the OIP or December 31, 2016, whichever comes first.

Enclosure Order EA-12-051 required the licensee, by February 28, 2013, to submit to the Commission an OIP, including a description of how compliance with the requirements described in Attachment 2 of the Order will be achieved. of Order EA-12-051 requires the license to have a reliable indication of the water level in associated spent fuel storage pools capable of supporting identification of the following pool water level conditions by trained personnel: (1) level that is adequate to support operation of the normal fuel pool cooling system, (2) level that is adequate to provide substantial radiation shielding for a person standing on the SFP operating deck, and (3) level where fuel remains covered and actions to implement make-up water addition should no longer be deferred. of Order EA-12-051, states that the SFP level instrumentation shall include the following design features:

1.1 Instruments

The instrumentation shall consist of a permanent, fixed primary instrument channel and a backup instrument channel. The backup instrument channel may be fixed or portable. Portable instruments shall have capabilities that enhance the ability of trained personnel to monitor spent fuel pool water level under conditions that restrict direct personnel access to the pool, such as partial structural damage, high radiation levels, or heat and humidity from a boiling pool.

1.2 Arrangement

The spent fuel pool level instrument channels shall be arranged in a manner that provides reasonable protection of the level indication function against missiles that may result from damage to the structure over the spent fuel pool. This protection may be provided by locating the primary instrument channel and fixed portions of the backup instrument channel, if applicable, to maintain instrument channel separation within the spent fuel pool area, and to utilize inherent shielding from missiles provided by existing recesses and corners in the spent fuel pool structure.

1.3 Mounting

Installed instrument channel equipment within the spent fuel pool shall be mounted to retain its design configuration during and following the maximum seismic ground motion considered in the design of the spent fuel pool structure.

1.4 Qualification

The primary and backup instrument channels shall be reliable at temperature, humidity, and radiation levels consistent with the spent fuel pool water at saturation conditions for an extended period.

This reliability shall be established through use of an augmented quality assurance process (e.g., a process similar to that applied to the site fire protection program).

1.5 Independence

The primary instrument channel shall be independent of the backup instrument channel.

1.6 Power supplies: Permanently installed instrumentation channels shall each be powered by a separate power supply. Permanently installed and portable instrumentation channels shall provide for power connections from sources independent of the plant [alternating current (ac)] and [direct current (de)] power distribution systems, such as portable generators or replaceable batteries. Onsite generators used as an alternate power source and replaceable batteries used for instrument channel power shall have sufficient capacity to maintain the level indication function until offsite resource availability is reasonably assured.

1. 7 Accuracy: The instrument channels shall maintain their designed accuracy following a power interruption or change in power source without recalibration.

1.8 Testing

The instrument channel design shall provide for routine testing and calibration.

1.9 Display

Trained personnel shall be able to monitor the spent fuel pool water level from the control room, alternate shutdown panel, or other appropriate and accessible location. The display shall provide on-demand or continuous indication of spent fuel pool water level. of Order EA-12-051, states that the SFP instrumentation shall be maintained available and reliable through appropriate development and implementation of the following programs:

2.1 Training

Personnel shall be trained in the use and the provision of alternate power to the primary and backup instrument channels.

2.2 Procedures

Procedures shall be established and maintained for the testing, calibration, and use of the primary and backup spent fuel pool instrument channels.

2.3 Testing and Calibration: Processes shall be established and maintained for scheduling and implementing necessary testing and calibration of the primary and backup spent fuel pool level instrument channels to maintain the instrument channels at the design accuracy.

On August 29, 2012, the NRC issued an Interim Staff Guidance document (the ISG),

JLD-ISG-2012-03, "Compliance with Order EA-12-051, Reliable Spent Fuel Pool Instrumentation" (ADAMS Accession No. ML12221A339), to describe methods acceptable to the NRC staff for complying with Order EA-12-051. The ISG endorses, with exceptions and clarifications, the methods described in the Nuclear Energy Institute (NEI) guidance document NEI 12-02, Revision 1, "Industry Guidance for Compliance with NRC Order EA-12-051, 'To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation,"' dated August 2012 (ADAMS Accession No. ML12240A307). Specifically, the ISG states:

The NRC staff considers that the methodologies and guidance in conformance with the guidelines provided in NEI 12-02, Revision 1, subject to the clarifications and exceptions in Attachment 1 to this ISG, are an acceptable means of meeting the requirements of Order EA-12-051.

3.0 TECHNICAL EVALUATION

3.1 Background and Schedule CPNPP, Units 1 and 2, has two independent SFPs, each approximately 30-feet (ft.) wide by 40-ft. 3-inches (in.) long. The SFPs have similar configurations.

The licensee submitted its OIP on February 28, 2013. The OIP states that installation of the SFP level instrumentation at CPNPP will be completed by fall 2014, for Unit 1, and fall 2015, for Unit 2, which is before startup from the second refueling outage for each unit.

The NRC staff has reviewed the licensee's schedule for implementation of SFP level instrumentation provided in its OIP. The NRC staff concludes that the schedule is acceptable because implementation is expected to be achieved within two refueling cycles after submittal of the OIP and before December 31, 2016, as required by Order EA-12-051.

3.2 Spent Fuel Pool Water Levels of Order EA-12-051 states, in part, that All licensees identified in Attachment 1 to this Order shall have a reliable indication of the water level in associated spent fuel storage pools capable of supporting identification of the following pool water level conditions by trained personnel: (1) level that is adequate to support operation of the normal fuel pool cooling system [Level 1 ], (2) level that is adequate to provide substantial radiation shielding for a person standing on the SFP operating deck [Level 2],

and (3) level where fuel remains covered and actions to implement make-up water addition should no longer be deferred [Level 3].

NEI 12-02 states, in part, that Level 1 represents the HIGHER of the following two points:

The level at which reliable suction loss occurs due to uncovering of the coolant inlet pipe, weir or vacuum breaker (depending on the design), or The level at which the water height, assuming saturated conditions, above the centerline of the cooling pump suction provides the required net positive suction head specified by the pump manufacturer or engineering analysis.

In its OIP, the licensee stated that Level 1 is the indicated level on either the primary or backup instrument channel of 22ft. 1.25 in. above the top of the fuel storage racks. The licensee also stated that this level aligns with the LO-LO level process setpoint that trips the fuel pool cooling pump.

In its letter dated July 3, 2013, the licensee stated, in part, that Comanche Peak designated Level I to be EL. 856 feet 4 inches (22 feet, 1.25 inches above the top of the fuel racks). This level corresponds to the LO-LO level process setpoint that trips the fuel pool cooling pump as described in Comanche Peak Final Safety Analysis Report (FSAR) Section 9.1.3.2. The LO-LO level process set point is selected to ensure that the pump will trip prior to a point where a void will occur in the suction lines. Analysis has demonstrated that there is adequate NPSH [net positive suction head] for pump operation at saturated conditions for water at plant elevation 856 feet.

The LO-LO level setpoint is thus the higher of the two pump-limiting conditions specified in NEI 12-02.

The NRC staff notes that Level 1 at 22ft. 1.25 in. is adequate for normal SFP cooling system operation; it is also sufficient for NPSH and represents the higher of the two points described in NEI 12-02 for Level 1.

NEI 12-02 states, in part, that 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. Level 2 is based on either of the following:

10 feet (+I-1 foot) above the highest point of any fuel rack seated in the spent fuel pools, or a designated level that provides adequate radiation shielding to* maintain personnel radiological dose levels within acceptable limits while performing local operations in the vicinity of the pool. This level shall be based on either plant-specific or appropriate generic shielding calculations, considering the emergency conditions that may apply at the time and the scope of necessary local operations, including installation of portable SFP instrument channel components.

In its OIP, the licensee stated that Level 2 is the indicated level on either the primary or backup instrument channel of greater than 10ft.(+/- 1 foot) above the top of the fuel storage racks is based on References 2 and 3 (NEI 12-02, Revision 1 and NRC ISG JLD-ISG-2012-03).

In its letter dated July 3, 2013, the licensee provided a sketch depicting the SFP elevations and levels. The NRC staff reviewed this sketch and notes that Level 2 is identified at elevation 844ft. 2. 75 in. which is approximately 10ft. above the top of the storage racks. The staff also notes that the licensee designated Level 2 using the first of the two options described in NEI 12-02 for Level 2.

NEI 12-02 states, in part, that Level 3 corresponds nominally (i.e., +/- 1 foot) to the highest point of any fuel rack seated in the spent fuel pool. Level 3 is defined in this manner to provide the maximum range of information to operators, decision makers and emergency response personnel.

In its OIP, the licensee stated that Level 3 is the indicated level on either the primary or backup instrument channel of greater than 1 ft. 0 in. above the top of the storage racks.

In its letter dated July 3, 2013, the licensee provided a sketch depicting the SFP elevations and levels. The NRC staff reviewed this sketch and notes that the elevation provided for Level 3 is identified at elevation 835ft. 2. 75 in. which is above the highest point of any spent fuel storage rack seated in the SFP at elevation 834ft. 2.75 in.

The licensee's proposed plan, with respect to identification of Levels 1, 2, and 3, appears to be consistent with NEI 12-02, as endorsed by the ISG.

3.3 Design Features: Instruments of Order EA-12-051, states, in part, that The instrumentation shall consist of a permanent, fixed primary instrument channel and a backup instrument channel. The backup instrument channel may be fixed or portable. Portable instruments shall have capabilities that enhance the ability of trained personnel to monitor spent fuel pool water level under conditions that restrict direct personnel access to the pool, such as partial structural damage, high radiation levels, or heat and humidity from a boiling pool.

NEI 12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3

[Instrumentation Design Features] of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features].

In its OIP, the licensee stated, for both units, that the CPNPP SFP instrumentation will use fixed primary and backup guided wave radar (GWR) sensors. The licensee also stated that each instrument channel will be capable of monitoring SFP water level over a continuous range of 23ft. 9.25 in. from the top of the fuel racks (835ft. 2.75 in.) to the high pool level elevation (859ft. 0 in.). The OJP also indicated that the level indicators would use a wireless technology to send signals from the transmitter panel to the receiver panel, which would include digital displays of the SFP levels.

Regarding wireless technology, NEI 12-02 states, in part, that Wireless and other advanced technologies may be used provided that an evaluation is performed to address their interaction with other plant systems, failure modes, and impact on plant cyber security controls. The use of such wireless technology must be evaluated for any possible adverse impact it may have on other plant equipment likely to be in use at the same time as the wireless SFP instrumentation is functioning. Licensees should also consider the ability of a wireless communication link to perform in the environment (e.g., high humidity, radiation) in which it may be called upon to function. Wireless technologies must meet the same requirements as wired technologies as specified in this guidance document. Wireless technologies that might be used in either the permanent or backup water level instrument channels are not Critical Digital Assets as defined in NEI 08-09, Cyber Security Plan for Nuclear Power Reactors (Reference 7); however, licensees should be cognizant of the logical connections that the wireless system may enable and adhere to the controls in their plant-specific cyber security plans with respect to its implementation.

The NRC staff has concerns regarding the performance evaluation of the wireless technology to be used in the SFP instrumentation in accordance with the guidance on instruments as described in NEI 12-02. The staff has identified this request as:

RAI #1 Please provide the following:

a)

The plant-specific performance evaluation result and a brief summary of the proposed wireless technology that will be used in the primary and backup measurement systems to address the criteria summarized in Section 3.1 of NE112-02.

b)

A description of the proposed wireless SFP instrumentation connections. Indicate whether the proposed SFP wireless instrumentation will use an existing wireless network or would use a dedicated point-to-point transmission path.

c)

Further information on how the proposed SFP wireless instrumentation will be designed and installed to address EMI/RFI emissions/susceptibility issues under BOB event conditions.

d)

A description of the manner by which the proposed SFP wireless instrumentation will be operable and available under BOB event conditions.

The NRC staff notes that the range specified for the licensee's instrumentation will cover Levels 1, 2, and 3 as described in Section 3.2 above. The licensee's proposed plan, with respect to the number of channels and the range of the instrumentation for its SFP appears to be consistent with NEI 12-02, as endorsed by the ISG.

3.4 Design Features: Arrangement of Order EA-12-051, states, in part, that The spent fuel pool level instrument channels shall be arranged in a manner that provides reasonable protection of the level indication function against missiles that may result from damage to the structure over the spent fuel pool. This protection may be provided by locating the primary instrument channel and the fixed portions of the backup instrument channel, if applicable, to maintain instrument channel separation within the spent fuel pool area, and to utilize inherent shielding from missiles provided by existing recesses and corners in the spent fuel pool structure.

NEI 12-02 states, in part, that The intent of the arrangement requirement is to specify reasonable separation and missile protection requirements for permanently installed instrumentation used to meet this order. Although additional missile barriers are not required to be installed, separation and shielding can help minimize the probability that damage due to an explosion or extreme natural phenomena (e.g., falling or wind-driven missiles) will render fixed channels of SFP instrumentation unavailable.

Installation of the SFP instrument channels shall be consistent with the plant-specific SFP design requirements and should not impair normal SFP function.

Channel separation should be maintained by locating the installed sensors in different places in the SFP area.

In its OIP, the licensee stated, in part, that, The preliminary locations of the primary and backup instrument sensing components are at the plant southeast and southwest corners of SFP 1 (X-01) and at the plant northeast and northwest corners of SFP 2 (X-02). The design for installation will include physical separation of the two sensors, separate extension cables from the electronics to the sensors, routing all cables in separate conduit I trays, separate UPS [uninterruptible power supply] power supplied from different ac sources, and seismically qualified mounting with physical separation of both the level sensing and indications.

The final location of the primary and backup system mounting brackets will be determined during the detailed design with consideration of power availability and separation requirements to protect against missiles.

The level sensing electronics for both primary and backup systems will be located in the shared auxiliary building, compliant with Reference 2 [NEI 12-02, Revision 1] and Reference 3 [JLD-ISG-2013-03] for separation and accessibility.

The primary system indicator will be located in the vicinity of the control room.

The backup system indications will be located in accessible locations.

In its letter dated July 3, 2013, the licensee provided a sketch depicting the conceptual locations of the two permanently mounted sensor probes and cable routings for the two redundant channels. This sketch depicts the two routings to be run from probes to wireless transmitters located in the Auxiliary Building (AB), and from there the transmitting signals are sent to the wireless receivers in the main control room (MCR) at the Control Building. In its July 3, 2013, letter, the licensee also stated, in part, that Within the SFP area, the brackets will be mounted as close to the Southeast (primary sensor) and Southwest (back-up sensor) corners of the X-01 pool and Northeast (primary sensor) and Northwest (back-up sensor) corners of the X-02 pool, as permanent plant structures allow. Placing the brackets and probes in the corners allows for natural protection from a single event or missile from disabling both systems.

In addition, in its July 3, 2013, letter, the licensee also stated, in part, that The level transmitter electronics will be located in the Auxiliary Building EL 852'0", which is separated from the SFP area by pressure boundary doors.

The level transmitters located in the Auxiliary Building have a local display, although the credited display units will be located in the main control room on the east wall, just off the control board area. The final locations of the channel components and cable routing will be determined during the design phase, anticipated to be completed by December 31, 2013.

In its letter dated August 28, 2013, the licensee stated that locations for the channel components, cable routing, and wireless receivers have changed from the July 3, 2013, submittal. In its August 28, 2013, letter, the licensee stated, in part, that The credited display units will not be located in the main control room but will be in the vicinity of the control room. The related figure (page 8 of Attachment to Reference 4 "[letter" contains a listed "[" character as part of the property label and has therefore been classified as invalid.]) showing the tentative component locations of the wireless receivers will also need to be updated. The location of the display units is being developed as part of the detailed design and more information will be provided by November 30, 2013.

In its letter dated August 28, 2013, the licensee stated that probe locations have not been finalized and that detailed engineering and design work is ongoing with expected completion by November 30, 2013.

The NRC staff notes that the final locations for the probes have not been finalized and that detailed engineering work is still ongoing. The staff has concerns regarding the lack of information about the routing of these two channels in accordance with the guidance on channel separation as described in NEI 12-02. The staff has identified this request as:

RAI#2 Please provide the following:

a)

The final locations/placement of the primary and back-up SFP level channel components, cable routing, credited display units, and wireless instruments.

b)

Additional information describing how the proposed arrangement of the sensor probe assembly and routing of the cabling between the sensor probe assembly and the electronics in the Auxiliary Building meets the Order requirement to arrange the SFP level instrument channels in a manner that provides reasonable protection of the level indication function against missiles that may result from damage to the structure over the SFP.

3.5 Design Features: Mounting of Order EA-12-051 states, in part, that Installed instrument channel equipment within the spent fuel pool shall be mounted to retain its design configuration during and following the maximum seismic ground motion considered in the design of the spent fuel pool structure.

NEI 12-02 states, in part, that The mounting shall be designed to be consistent with the highest seismic or safety classification of the SFP. An evaluation of other hardware stored in the SFP shall be conducted to ensure it will not create adverse interaction with the fixed instrument location(s).

The basis for the seismic design for mountings in the SFP shall be the plant seismic design basis at the time of submittal of the Integrated Plan for implementing NRC Order EA-12-051.

In its OIP, the licensee stated that the mounting of both primary and backup system will be installed to maintain its integrity during and following a design bases seismic event. The licensee indicated that all locations will be reviewed for two-over-one seismic interference.

In its letter dated July 3, 2013, the licensee stated, in part, that The mounting bracket for the sensing probe will be designed according to the plant design basis for the SSE [Safe Shutdown Earthquake] seismic hazard curve at the appropriate plant elevation. Loads that will be considered in the evaluation of the bracket and its mounting are: 1-Static loads including the dead weight of the mounting bracket in addition to the weight of the level sensing instruments, pipe guard and cabling; 2-Dynamic loads including the seismic load due to excitation of the dead weight of the system in addition to the hydrodynamic effects resulting from the excitation of the spent fuel pool water. A response spectra analysis will be performed for the seismic evaluation of the mounting bracket using a Finite Element Analysis (FEA) software and using floor response spectrum at Elevation 860' in the Fuel Building (i.e. mounting floor elation). Damping values will be according to Safe Shutdown Earthquake (SSE) and consistent with the design basis of the station. The material properties that will be used for the bracket and its mounting will take into consideration the environmental conditions in the spent fuel pool area following an event. The design of the bracket and its mounting will maintain a design margin of 10% or more from the plant design basis criteria. Hydrodynamic effects on the mounting bracket will be evaluated using TID-7024 (Nuclear Reactors and Earthquakes, dated 1963). Plant acceptance criteria and applicable codes will be used for the design of the bracket and its anchorage.

The probe attaches to the bracket via a 11/2 inch threaded connection. The schematic below details the vertical portion of the bracket where the probe will thread into the bracket. Non-movable connections of parts will be welded.

Dimensions are nominal and may be adjusted for seismic qualification and final delivery. It is undetermined if a stilling well will be installed. The sitting well option will be determined during the design phase, anticipated to be completed by December 31, 2013. If a stilling well installed, it will be welled to the lower portion of the bracket, surrounding the sensor probe cable.

The attachment of the seismically qualified bracket to the pool deck will be through permanently installed anchors. With the permanently installed anchors, the bracket pedestal will be secured to the poolside deck with adequate washers and bolts.

In addition, in its letter dated July 3, 2013, the licensee provided a schematic showing details the pedestal that would attach the bracket to the pool deck.

The NRC staff notes that the proposed application of such seismic design criteria appears to be reasonable and addresses the staff-endorsed NEI 12-02 guidance stating that the channel be designed to be consistent with the highest seismic or safety classification of the SFP. The licensee's proposed plan, with respect to the seismic design of the mounting, appears to be consistent with NEI 12-02, as endorsed by the ISG. The staff plans to verify the results of the licensee's seismic testing and analysis report. The staff has identified these requests as:

RAI#3 Please provide the results of the analyses used to verify the design criteria and methodology for seismic testing of the SFP instrumentation and the electronics units, including, design basis maximum seismic loads and the hydrodynamic loads that could result from pool sloshing or other effects that could accompany such seismic forces.

RAI#4 For each of the mounting attachments required to attach SFP Level equipment to plant structures, please describe the design inputs, and the methodology that was used to qualify the structural integrity of the affected structures/equipment.

3.6 Design Features: Qualification of Order EA-12-051 states, in part, that The primary and backup instrument channels shall be reliable at temperature, humidity, and radiation levels consistent with the spent fuel pool water at saturation conditions for an extended period. This reliability shall be established through use of an augmented quality assurance process (e.g. a process similar to that applied to the site fire protection program).

NEI 12-02 states, in part, that The instrument channel reliability shall be demonstrated via an appropriate combination of design, analyses, operating experience, and/or testing of channel components for the following sets of parameters, as described in the paragraphs below:

conditions in the area of instrument channel component use for all instrument components, effects of shock and vibration on instrument channel components used during any applicable event for only installed components, and seismic effects on instrument channel components used during and following a potential seismic event for only installed components...

The NRC staff assessment of the instrument qualification is discussed in the following subsections below: (3.6.1) Augmented Quality Process, (3.6.2) Post Event Conditions, (3.6.3) Shock and Vibration, and (3.6.4) Seismic Reliability.

3. 6. 1 Augmented Quality Process Appendix A-1 of the guidance in NEI 12-02 describes a quality assurance process for non-safety systems and equipment that is not already covered by existing quality assurance requirements. Within the ISG, the NRC staff found the use of this quality assurance process to be an acceptable means of meeting the augmented quality requirements of Order EA-12-051.

In its OIP, the licensee stated that the instrumentation systems will meet the requirements for augmented quality in accordance with NEI 12-02 and the ISG.

The licensee's proposed augmented quality assurance process appears to be consistent with NEI 12-02, as endorsed by the ISG.

3. 6. 2 Post Event Conditions NEI 12-02 states, in part, that The temperature, humidity and radiation levels consistent with conditions in the vicinity of the [SFP] and the area of use considering normal operational, event and post-event conditions for no fewer than seven days post-event or until off-site resources can be deployed by the mitigating strategies resulting from Order EA-12-049 should be considered. Examples of post-event (beyond-design-basis) conditions to be considered are:

radiological conditions for a normal refueling quantity of freshly discharged (1 00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) fuel with the SFP water level 3 as described in this order, temperatures of 212 degrees F and 100% relative humidity environment, boiling water and/or steam environment, a concentrated borated water environment, and...

In its OIP, the licensee stated, consistent with NEI 12-02, in part, that The normal operational, event and post-event for temperature, humidity, and radiation will be addressed for no fewer than seven days post-event or until off-site resources can be deployed by mitigating strategies resulting from the NRC issued Order EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigating Strategies for Beyond Design-Basis External Events," dated March 12, 2012 (Reference 6). Examples of post-event (beyond-design-basis) conditions to be considered are:

(1) radiological conditions for a normal refueling quantity of freshly discharged (1 00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) fuel with the SFP water level 3 (Section Ill, Item

2) as described in Reference 1, (2) temperatures of 212°F and 100 percent relative humidity environment, (3) boiling water and/or steam environment (4) a concentrated borated water environment,...

Related to radiological conditions, in its letter dated July 3, 2013, the licensee stated, in part, that Components subject to significant radiation under beyond design basis conditions are those in the spent fuel pool area. These include the sensor probe, bracket, coupler and interconnecting cable. The sensor probe and bracket are stainless steel and will not be affected by the anticipated radiation. The coupler and cable are selected by design for the beyond design basis radiation service.

Supplemental radiation testing of the interconnecting cable to total integrated dose will be completed to demonstrate operation for more than one week with spent fuel pool water at level 3.

The NRC staff has concerns with the lack of information regarding the expected radiological conditions in the vicinity where the transmitter electronics equipment will be located under normal and worst case postulated conditions. The staff has identified this request as:

RAI#5 Please provide analysis of the maximum expected radiological conditions (dose rate and total integrated dose) to which the transmitter electronics will be exposed. Also, please provide documentation indicating the radiological dosage amount that the electronics for this equipment is capable of withstanding. Please discuss the time period over which the analyzed total integrated dose was applied.

While addressing post-event temperature conditions, in its letter dated July 3, 2013, the licensee stated, in part, that SFPIS [SFP Instrumentation System] materials and components were selected and specified by design to meet or exceed the temperature and humidity requirements of 212 oF and 100% humidity in the SFP area, and design basis conditions for locations of sensor and system electronics. Design is supplemented by tests of system components as shown.....

In its letter dated July 3, 2013, the licensee provided information regarding the SFP instrumentation components and the basis for validating the design of these components. In this letter, the licensee explained that the sensor probe and sensor bracket are inherently tolerant to the effects of the specified temperature and humidity and this will be demonstrated by design and analysis. The sensor coupler is specifically designed by the manufacturer for high temperature and humidity applications. The coaxial cable will be selected by design for conditions and tested for performance at 212 degrees Fahrenheit (°F), saturated steam. The sensor electronics design temperature and humidity exceeds the requirements for the mounting locations. The sensor and system electronics design temperature exceeds the requirements for the mounting locations which will be in the AB.

The NRC staff has concerns with the lack of information regarding whether the sensor electronics and wireless instruments are capable of continuously performing its required functions under this expected temperature and humidity condition. The staff has identified this request as:

RAI#6 Please provide the following:

a)

Information describing the temperature ratings for all system electronics (including sensor electronics, system electronics, level and wireless transmitter, wireless receiver and display) and whether the ratings are continuous duty ratings; and, b)

Information describing what will be the maximum expected temperature and relative humidity conditions in the room{s) in which the sensor electronics and wireless technologies will be located under BOB conditions in which there is no ac power available to run Heating, Ventilation, and Air Conditioning (HVAC) systems.

3. 6. 3 Shock and Vibration NEI 12-02 states, in part, that Applicable components of the instrument channels are rated by the manufacturer (or otherwise tested) for shock and vibration 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:

instrument channel components use known operating principles, are supplied by manufacturers with commercial quality programs (such as IS09001) with shock and vibration requirements included in the purchase specification and/or instrument design, and commercial design and testing for operation in environments where significant shock and vibration loadings are common, such as for portable hand-held devices or transportation applications; substantial history of operational reliability in environments with significant shock and vibration loading, such as transportation applications, or use of component inherently resistant to shock and vibration loadings or are seismically reliable such as cables.

In its OIP, the licensee stated that demonstration of shock and vibration adequacy will be consistent with the guidelines in Reference 2 [NEI 12-02], and Reference 3 [JLD-ISG-2012-03].

Passive components located within the SFP building In its letter dated July 3, 2013, the licensee stated, in part, that All components located within the spent fuel pool are passive components, inherently resistant to shock and vibration loadings. These include the stainless steel sensor cable probe, sensor bracket, coupler and interconnecting cable....

However, assurance of reliability under conditions of shock and vibration is supported by manufacturer operating experience, which includes use of components in high vibration installations, such as compressed air systems and transportation industries.

Active components located outside the SFP building In its letter dated, July 3, 2013, the licensee stated, in part, that Active electronic components, located outside the spent fuel pool building, are permanently and rigidly attached to seismic racks or structural walls, and are not subject to significant shock and vibration loadings from sloshing. However, assurance of reliability under conditions of shock and vibration is supported by manufacturer operating experience, which includes use of components in high vibration installations, such as compressed air systems and transportation industries.

The NRC staff notes that while the passive components may inherently be resistant to shock and vibration loadings, the actual resistance depends on the component material property, structure, and the final installation. The staff has concerns with the licensee's lack of information regarding the tests, applied forces and their directions, frequency ranges, and the operability of the sensor after shock and vibration tests are completed. The staff has identified this request as:

RAI#7 Please provide the following:

a)

Information describing the evaluation of the sensor electronics design, the shock test method, test results, and forces applied to the sensor electronics applicable to its successful tests demonstrating that the testing provides an appropriate means to demonstrate reliability of the sensor electronics under the effects of severe shock.

b)

Information describing the evaluation of the sensor electronics design, the vibration test method, test results, the forces and their frequency ranges and directions applied to the sensor applicable to its successful tests, demonstrating that the testing provides an appropriate means to demonstrate reliability of the sensor electronics under the effects of high vibration.

3. 6. 4 Seismic Reliability The ISG recommends the use of Sections 7, 8, 9, and 10 of IEEE 344-2004 for seismic qualification of the SFP level instrumentation.

In its OIP, the licensee stated, in part, that Demonstration of seismic adequacy will be achieved using one or more of the following methods:

1) demonstration of seismic motion consistent with that of existing design basis loads at the installed location;

2) 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;

3) adequacy of seismic design and installation is demonstrated based on the guidance in Sections 7, 8, 9, and 10 of [Institute of Electrical and Electronics Engineers (IEEE)] Standard 344-2004, "IEEE Recommended Practice for Seismic Qualification of Class 1 E Equipment for Nuclear Power Generating Stations," (Reference 7) or a substantially similar industrial standard;

4) 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

5) seismic qualification using seismic motion consistent with that of existing design basis loading at the installation location.

Passive components located within the SFP building In its letter dated July 3, 2013, the licensee stated, in part, that The sensor probe and supporting bracket are functionally passive components.

Analysis will be used to demonstrate they will maintain their structural integrity and design configuration and to establish their reliability. The coupler and interconnecting cable are also passive components; however, they will be included in the seismic testing of the sensor electronics....

All components except for the stainless steel sensor cable probe and the stainless steel bracket will be seismically tested in a rigidly-mounted condition equivalent to their as-installed condition. The cable probe and bracket are passive components for which maintenance of structural or physical integrity is the only requirement.

Active components located outside the SFP building In its letter dated July 3, 2013, the licensee stated, in part, that All active system components, including sensor electronics, system electronics, batteries, display and enclosures will be seismically tested based on rigid mounting conditions. Testing is tri-axial, using random multi-frequency inputs, in accordance with IEEE 344-2004. Analyses and testing will conservatively envelope the conditions at equipment mounting locations resulting from the design basis maximum ground motion.....

The active components of the spent fuel pool instrumentation system will be functionally tested before and after seismic simulation. Water level inputs to the system will be simulated by grounding the sensor probe at selected, repeatable positions. Comparison of system output will be made both to pre-test results and to the measured position of the sensor probe input.

The NRC staff notes that the licensee will demonstrate the reliability of the seismic design and installation in accordance with NEI 12-02, as endorsed by the ISG. The licensee's planned approach with respect to the seismic reliability of the instrumentation appears to be consistent NEI 12-02, as endorsed by the ISG. However, the staff plans to verify the results of the licensee's seismic test when it is completed. The staff has identified this request as:

RAI#8 Please provide analysis of the seismic testing results and show that the instrument (including wireless technology) performance reliability, following exposure to simulated seismic conditions representative of the environment anticipated for the SFP structures at CPNPP has been adequately demonstrated. Include information describing the design inputs and methodology used in any analyses of the mountings of electronic equipment onto plant structures, as requested in RAI #4 above.

3. 6. 5 Qualification Evaluation Summary Upon acceptable resolution of the RAisin Section 3.6, the NRC staff will be able to make a conclusion regarding the instrument qualification.

3.7 Design Features: Independence of Order EA-12-051 states, in part, that The primary instrument channel shall be independent of the backup instrument channel.

NEI 12-02 states, in part, that Independence of permanently installed instrumentation, and primary and backup channels, is obtained by physical and power separation commensurate with the hazard and electrical isolation needs. If plant AC or DC power sources are used then the power sources shall be from different buses and preferably different divisions/channels depending on available sources of power.

In its OIP, the licensee stated that the backup instrument system will be redundant to and independent of the primary instrument system. The licensee also stated that independence of the two systems include: location, mounting, power sources, power and signal wiring, and indications, to prevent any failure of one system from affecting the other system.

In its letter dated July 3, 2013, the licensee stated, in part, that Each system will be installed using completely independent cabling structures, including routing of the interconnecting cable within the SFP area in separate hard-pipe conduits. Power sources will be routed to the electronics enclosures from electrically separated sources ensuring the loss of one train or bus will not disable both channels. The system displays will be installed in separate qualified NEMA [National Electrical Manufacturers Association] 4X or better enclosures, with the primary display in the control room envelope. Primary and backup systems will be completely independent of each other, having no shared components.

The NRC staff notes that with this arrangement, the loss of one backup power supply will not affect the operation of the independent channel under BOB event conditions. The implementation of such design provisions appears to be consistent with NEI 12-02, as endorsed by the ISG, and the electrical functional performance of each level measurement channel would be considered independent of the other channel. However, the NRC staff plans to verify the final electrical power supply design information when it is provided. The NRC staff has identified this request as:

RAI#9 Please provide the NRC staff with the final configuration of the power supply source for each channel so that the staff may conclude that the two channels are independent from a power supply assignment perspective.

3.8 Design Features: Power Supplies of Order EA-12-051, states in part, that Permanently installed instrumentation channels shall each be powered by a separate power supply. Permanently installed and portable instrumentation channels shall provide for power connections from sources independent of the plant ac and de power distribution systems, such as portable generators or replaceable batteries. Onsite generators used as an alternate power source and replaceable batteries used for instrument channel power shall have sufficient capacity to maintain the level indication function until offsite resource availability is reasonably assured.

NEI 12-02 states, in part, that The normal electrical power supply for each channel shall be provided by different sources such that the loss of one of the channels primary power supply will not result in a loss of power supply function to both channels of SFP level instrumentation.

All channels of SFP level instrumentation shall provide the capability of connecting the channel to a source of power (e.g., portable generators or replaceable batteries) independent of the normal plant AC and DC power systems. For fixed channels this alternate capability shall include the ability to isolate the installed channel from its normal power supply or supplies. The portable power sources for the portable and installed channels shall be stored at separate locations, consistent with the reasonable protection requirements associated with NEI 12-06 (Order EA-12-049). The portable generator or replaceable batteries should be accessible and have sufficient capacity to support reliable instrument channel operation until off-site resources can be deployed by the mitigating strategies resulting from Order EA-12-049.

If adequate power supply for either an installed or portable level instrument credits intermittent operation, then the provisions shall be made for quickly and reliably taking the channel out of service and restoring it to service. For example, a switch on the power supply to the channel is adequate provided the power can be periodically interrupted without significantly affecting the accuracy and reliability of the instrument reading. Continuous indication of SFP level is acceptable only if the power for such indication is demonstrably adequate for the time duration specified in section 3.1 [.]

In its OIP, the licensee stated, in part, that An AC source will be selected for each system's 24-Vdc UPS, with power cables, with power cables routed separately through existing or new tray I conduit and penetrations.

Both channels will be powered by independent batteries following a loss-of-AC power. The minimum battery life will be 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> battery life is sufficient amount of time for an alternate source of power to be provided by plant specific procedures to address Reference 6 [NRC Order EA-12-049]. Each channel will include an externally accessible bulkhead connector and a transfer switch for connection of an alternate power source.

In its letter dated July 3, 2013, the licensee stated, in part, that A description of the electrical AC power sources and capacities for the primary and backup channels will be developed as part of the detailed design and more information will be provided by November 30, 2013.

With respect to operation and use of the SFPIS, no immediate action is required in the event of a loss of AC power. The SFPIS includes a battery-baked, uninterruptible power supply, with battery capacity to power the system for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The overall procedural response to a loss of AC power is governed by the FLEX Support Guidelines which are being developed as a part of the response to NRC Order EA-12-049.

Battery sizing is in accordance with standard IEEE 485-2010. Design criteria applied are: Continuous system operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following loss of ac power. Calculation of system power consumption is based on the specified values listed in component manufacturer specifications. A 10% capacity margin is added to battery sizing calculations, following guidelines of IEEE 485-2010, Section 6.2.2. The time to restore AC power to the primary and backup channels will be within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and will be established in the FLEX Support Guidelines.

In its letter dated August 28, 2013, the licensee stated, in part, that A description of the electrical AC power sources and capacities for the primary and backup channels will be developed as part of the detailed design and more information will be provided by November 30, 2013.

The NRC staff notes that further information regarding the selection of the electrical AC power sources and capacities for the primary and backup SFP level instrumentation channels is not available for review and that the licensee will provide further information to the staff by November 30, 2013. The staff has identified these requests as:

RAI #10 Please provide a description of the electrical AC power sources and capacities for the primary and backup channels.

(This information was previously requested as RAI-6a in the NRC letter dated June 7, 2013)

The NRC staff notes that the proposed criteria for sizing of the battery backup appears to be consistent with NEI 12-02, as endorsed by the ISG. However, the staff plans to verify the results of the licensee's calculation for required duty cycle given the final design load of the instrument channel for its installed configuration. The staff has identified this request as:

RAI #11 Please provide the results of the calculation depicting the battery backup duty cycle requirements demonstrating that its capacity is sufficient to maintain the level indication function until offsite resource availability is reasonably assured.

3.9 Design Features: Accuracy of Order EA-12-051 states, in part, that The instrument channels shall maintain their designed accuracy following a power interruption or change in power source without recalibration.

NEI 12-02 states, in part, that Accuracy should consider operations while under SFP conditions, e.g., saturated water, steam environment, or concentrated borated water. Additionally, instrument accuracy should be sufficient to allow trained personnel to determine when the actual level exceeds the specified lower level of each indicating range (levels 1, 2 and 3) without conflicting or ambiguous indication.

In its OIP, the licensee stated, in part, that Instrument channels will be designed such that they will maintain their design accuracy without recalibration following a power interruption or change in power source. The accuracy will be within the resolution requirements of Reference 2, Figure 1 [NEI 12-02, Revision 1]. The instrument accuracy will be sufficient to allow personnel using plant procedures to determine when the water level reaches level 1, 2, and 3 without conflicting or ambiguous indication.

In its letter dated July 3, 2013, the licensee stated, in part, that The instrument channel accuracy will be established during the design phase.

An estimate of the expected instrument channel accuracy under normal and beyond-design-basis conditions will be provided by November 30, 2013.

The calibration procedure, and the methodology and basis for establishing both the criteria indicating the need for recalibration, and the acceptance criterion to be used with the procedure, will be established during the design verification phase. The methodology for defining these criteria will be provided by November 30, 2013.

The NRC staff notes that further information regarding SFP level instrumentation accuracy is not available for review and that the licensee will provide further information to the staff by November 30, 2013. The staff has identified this request as:

RAI #12 Please provide the following:

a)

An estimate of the expected instrument channel accuracy performance 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.

(This information was previously requested as RAI-7 in the NRC letter dated June 7, 2013) 3.10 Design Features: Testing of Order EA-12-051 states, in part, that The instrument channel design shall provide for routine testing and calibration.

NEI 12-02 states, in part, that Static or non-active installed (fixed) sensors can be used and should be designed such that testing and/or calibration can be performed in-situ. For microprocessor based channels the instrument channel design shall be capable of testing while mounted in the pool.

In its OIP, the licensee stated that instrument channel design will provide for routine testing and calibration consistent with Reference 2 [NEI12-02], and Reference 3 [JLD-ISG-2012-03].

In addition, in its letter dated July 3, 2013, the licensee stated that all information regarding the RAJ for testing in NRC letter dated June 7, 2013, would be provided to the staff by November 30, 2013.

The NRC staff notes that further information regarding the design of the SFP level instrumentation to provide for routine testing and calibration is not available for review and that the licensee will provide further information to the staff by November 30, 2013. The staff has identified this request as:

RAI #13 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 of how functional checks will be performed, and the frequency at which they will be conducted. Describe how calibration tests will be performed, 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 of what preventive maintenance tasks are required to be performed during normal operation, and the planned maximum surveillance interval that is necessary to ensure that the channels are fully conditioned to accurately and reliably perform their functions when needed.

(This information was previously requested as RAI-8 in the NRC letter dated June 7, 2013) 3.11 Design Features: Display of Order EA-12-051 states, in part, that Trained personnel shall be able to monitor the spent fuel pool water level from the control room, alternate shutdown panel, or other appropriate and accessible location. The display shall provide on-demand or continuous indication of spent fuel pool water level.

NEI 12-02 states, in part, that The intent of this guidance is to ensure that information on SFP level is reasonably available to the plant staff and decision makers. Ideally there will be an indication from at least one channel of instrumentation in the control room.

While it is generally recognized (as demonstrated by the events at Fukushima Daiichi) that SFP level will not change rapidly during a loss of spent fuel pool cooling scenario more rapid SFP drain down cannot be entirely discounted.

Therefore, the fact that plant personnel are able to determine the SFP level will satisfy this requirement, provided the personnel are available and trained in the use of the SFP level instrumentation (see Section 4.1) and that they can accomplish the task when required without unreasonable delay.

SFP level indication from the installed channel shall be displayed in the control room, at the alternate shutdown panel, or another appropriate and accessible location (reference NEI 12-06). An appropriate and accessible location shall have the following characteristics:

occupied or promptly accessible to the appropriate plant staff giving appropriate consideration to various drain down scenarios, outside of the area surrounding the SFP floor, e.g., an appropriate distance from the radiological sources resulting from an event impacting the SFP, inside a structure providing protection against adverse weather, and outside of any very high radiation areas or LOCKED HIGH RAD AREA during normal operation.

If multiple display locations beyond the required "appropriate and accessible location" are desired, then the instrument channel shall be designed with the capability to drive the multiple display locations without impacting the primary "appropriate and accessible" display.

In its OIP, the licensee stated that the primary system indicator will be located in the vicinity of the control room and the backup system indicators will be located in accessible locations.

In its letter dated July 3, 2013, the licensee stated, in part, that The recognized primary and backup displays, pursuant to NRC Order EA-12-051 will be in the Control Room, EL-830'-0", on the approximate centerline of the East wall for each Unit.

During all drain-down scenarios and external events the main control room will be manned. With the displays inside the main control room they are considered "promptly accessible."

In its letter dated August 28, 2013, the licensee stated, in part, that The credited display units will not be located in the main control room but will be in the vicinity of the control room. The related figure (page 8 of Attachment to Reference 4 "[letter" contains a listed "[" character as part of the property label and has therefore been classified as invalid.]) showing the tentative component locations of the wireless receivers will also need to be updated. The location of the display units is being developed as part of the detailed design and more information will be provided by November 30, 2013.

The NRC staff notes that the licensee indicated that the credited SFP level instrumentation display units will not be located in the MCR but will be located in the vicinity of the control room and that the licensee will provide further information to the staff by November 30, 2013. The staff is concern with the licensee's lack of information regarding the location for the SFP level instrumentation displays. The staff has identified this request as:

RAI #14 Please provide the following:

a)

The specific location for each of the primary and backup instrument channel displays.

b)

For any SFP level instrumentation displays located outside the MCR, please describe the evaluation used to validate that the display location can be accessed without unreasonable delay following a BOB event. Include the time available for personnel to access the display as credited in the evaluation, as well as the actual time (e.g.,

based on walk-throughs) that it will take for personnel to access the display. Additionally, please include a description of the radiological and environmental conditions on the paths personnel might take. Describe whether the display location remains habitable for radiological, heat and humidity, and other environmental conditions following a BOB event. Describe whether personnel are continuously stationed at the display or monitor the display periodically.

3.12 Programmatic Controls: Training of Order EA-12-051 states, in part, that Personnel shall be trained in the use and the provision of alternate power to the primary and backup instrument channels.

NEI 12-02 states, in part, that The personnel performing functions associated with these SFP level instrumentation channels shall be trained to perform the job specific functions necessary for their assigned tasks (maintenance, calibration, surveillance, etc.).

SFP instrumentation should be installed via the normal modification processes.

In some cases, utilities may choose to utilize portable instrumentation as a portion of their SFP instrumentation response. In either case utilities should use the Systematic Approach to Training (SAT) to identify the population to be trained. The SAT process should also determine both the initial and continuing elements of the required training.

In its OIP, the licensee stated, in part, that A systematic approach will be used to identify the population to be trained and to determine both the initial and continuing elements of the required training.

Personnel will complete training prior to being assigned responsibilities associated with this instrument.

The licensee's proposed plan to train personnel in the use and the provision of alternate power to the primary and backup instrument channels, including the approach to identify the population to be trained appears to be consistent with NEI 12-02, as endorsed by the ISG.

3.13 Programmatic Controls: Procedures of Order EA-12-051 states, in part, that Procedures shall be established and maintained for the testing, calibration, and use of the primary and backup spent fuel pool instrument channels.

NEI 12-02 states, in part, that Procedures will be developed using guidelines and vendor instructions to address the maintenance, operation and abnormal response issues associated with the new SFP instrumentation.

In its OIP, the licensee stated, in part, that Procedures will be developed using guidelines and vendor instructions to address the maintenance, operation and abnormal response issues associated with the new SFP level instrumentation.

In its letter dated July 3, 2013, the licensee stated, in part, that Appropriate quality assurance measures will be selected for spent fuel pool level instrumentation (SFPLI) required by the order (EA-12-051) consistent with Appendix A-1 of NEI 12-02, similar to those imposed by Regulatory Guide 1.155.

Site procedures for inspection, maintenance, repair, operation, abnormal response and administrative controls for the SFP level instrumentation will be developed in accordance with Comanche Peak procedure controls, using the vendor technical manual and other documentation. The vendor technical manual and documentation will include principles of operation, inspection and maintenance recommendations, drawings and technical documentation, individual component manufacturer manuals and documentation and recommended spare parts. Additional procedures for abnormal response will be developed in conjunction with FLEX implementation. As these procedures are developed, additional details will be provided in 6 month updates. These procedures are expected to be complete by June 30, 2014.

In its letter dated August 28, 2013, the licensee stated that the procedures have not been developed and that a description of these procedures will be provided by June 30, 2014.

The NRC staff notes that information regarding inspection, maintenance, repair, operation, abnormal response and administrative controls for the SFP instrumentation is not currently available for review and that as the procedures are developed, additional details will be provided to the staff during the six month status report. The staff previously requested this information as RAI-10 in NRC letter dated June 7, 2013. However, based on feedback from licensees, the staff revised this RAI as follows:

RAI #15 Please provide a list of the procedures addressing operation (both normal and abnormal response), calibration, test, maintenance, and inspection procedures that will be developed for use of the spent SFP instrumentation. The licensee is requested to include a brief description of the specific technical objectives to be achieved within each procedure.

3.14 Programmatic Controls: Testing and Calibration of Order EA-12-051 states, in part, that Processes shall be established and maintained for scheduling and implementing necessary testing and calibration of the primary and backup spent fuel pool level instrument channels to maintain the instrument channels at the design accuracy.

NEI 12-02 states, in part, that Processes shall be established and maintained for scheduling and implementing necessary testing and calibration of the primary and backup SFP level instrument channels to maintain the instrument channels at the design accuracy. The testing and calibration of the instrumentation shall be consistent with vendor recommendations or other documented basis.

In its OIP, the licensee stated, in part, that Processes will be established and maintained for scheduling and implementing necessary testing and calibration of the primary and backup SFP level instrument channels to maintain the instrument channels at the design accuracy. Testing and calibration of the instrumentation will be consistent with vendor recommendations or other documented basis as appropriate.

In its letter dated July 3, 2013, the licensee stated, in part, that Details of the capabilities and provisions of the level instrumentation for periodic calibration and testing will be established during the design phase. A description of these features and the way they will support in-situ testing will be provided November 30, 2013.

A description of how the defined testing and calibration will enable the conduct of regular channel checks of each independent channel against the other, and against any other permanently-installed SPF level instrumentation will be provided November 30, 2013.

Details of functional checks and instrument channel calibrations will be determined during the design phase. A description of how functional checks and calibration tests will be performed, and the frequency at which they will be conducted, will be provided November 30, 2013. An explanation of how these surveillances will be incorporated into the plant surveillance program will be included.

The preventative maintenance tasks required to be performed during normal operation, and the planned surveillance intervals will be determined during the design phase. A description of these tasks and intervals will be provided November 30, 2013.

In addition, in its letter dated July 3, 2013, the licensee stated, in part, that Comanche Peak will establish and implement procedures for control and oversight of SFPIS maintenance and testing. The new procedure(s) will include requirements for all necessary tests to be performed, frequency of testing, acceptance criteria, and requirements for inspection and audit of test performance and results. As these procedures are developed information will be provided to the NRC in 6 month updates. These procedures are expected to be complete by June 30, 2014 Comanche Peak will implement measures to minimize the possibility of either the primary or backup channel being out of service for any extended period.

Sufficient spares components and materials will be maintained to be able to repair or replace defective components in a short time. Comanche Peak will follow the NEI 12-02 guidance with regard to time during which one or more channels may be out of service, including compensatory actions. As details are developed information will be provided to the NRC in 6 month updates. Final details will be provided by June 30, 2014.

The NRC staff notes that as details on the processes for testing and calibration of the SFP level instrumentation are developed, the licensee will submit them to the staff during the six month status reports; with the final details expected to be provided to the staff by June 30, 2014. The staff has identified this request as:

RAJ #16 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 performed 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 the in-situ calibration process at the SFP location that will result in the channel calibration being maintained at its design accuracy.

c)

A description of what compensatory actions are planned in the event that the non-functioning instrument channel cannot be restored to functional status within 90 days.

(This information was previously requested as RAI-11 in NRC letter dated June 7, 2013) 3.15 Instrument Reliability NEI 12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3 [Instrument Design Features] of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features].

In its OIP, the licensee stated that the channel design would meet Section 3 of the NEI guidance and that reliability would be assured through implementation of the programmatic controls that are consistent with the applicable guidance in NEI 12-02.

Upon acceptable resolution of the RAis noted above, the NRC staff will be able to make a conclusion regarding the reliability of the SFP instrumentation.

4.0 CONCLUSION

The NRC staff is unable to complete its evaluation regarding the acceptability of the licensee's plans for implementing the requirements of Order EA-12-051 due to the need for additional information as described above. The staff will issue an evaluation with its conclusion after the licensee has provided the requested information.

ML13295A674 OFFICE NRR/DORULPL4/PM NAME BSingal DATE 10/31/13 OFFICE NRR/DE/EICB/BC*

NAME JThorp DATE 10/7/13 Sincerely, IRA/

Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation CBetancourt, RES/DE/ICEE CRoque-Cruz, NRR DRahn, NRR GCasto, NRR MMitchell, NRR RKuntz, NRR CHunt, NRR BPurnell, NRR

• via memo dated October 7, 2013 NRR/DORULPL4/LA NRR/DSS/SBPB/BC*

JBurkhardt GCasto 10/28/13 10/7/13 NRR/DORULPL4/BC NRR/DORULPL4/PM MMarkley BSingal 11/1/13 11/4/13