ML14036A005

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Issuance of Amendment License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System - Increase in Isotopic Enrichment of Boron-10
ML14036A005
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/14/2014
From: Bhalchandra Vaidya
Plant Licensing Branch 1
To: Costanzo C
Nine Mile Point
Vaidya B, NRR/DORL/LPL1-1, 415-3308
References
TAC MF2462
Download: ML14036A005 (17)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 14, 2014 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P. 0. Box 63 Lycoming, NY 13093

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT NO.2- ISSUANCE OF AMENDMENT, RE: LICENSE AMENDMENT REQUEST PURSUANT TO 10 CFR 50.90: STANDBY LIQUID CONTROL SYSTEM- INCREASE IN ISOTOPIC ENRICHMENT OF BORON-10 (TAC NO. MF2462)

Dear Mr. Costanzo:

The Commission has issued the enclosed Amendment No. 143 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Unit No. 2 (NMP2). The amendment consists of changes to the NMP2 Technical Specifications (TSs) in response to your application dated July 5, 2013, as supplemented by letter dated December 6, 2013.

The amendment includes changes to NMP2 Technical Specification (TS) 3.1.7, "Standby Liquid Control (SLC) System," to increase the isotopic enrichment of boron-1 0 in the sodium pentaborate solution utilized in the SLC System and decrease the SLC System tank volume.

Specifically, the amendment revised the NMP2 TS 3.1.7, "Standby Liquid Control (SLC)

System" as follows:

  • Revised the acceptance criterion in [Surveillance Requirement] SR 3.1. 7.10 by increasing the sodium pentaborate boron-10 enrichment requirement from;:: 25 atom percent to;:: 92 atom percent, and make a corresponding change in TS Figure 3.1.7-1, "Sodium Pentaborate Solution Volume/Concentration Requirements."
  • Revised TS Figure 3.1. 7-1 to account for the decrease in the minimum volume of the SLC system tank. At a sodium pentaborate concentration of 13.6% the minimum volume changes from 4,558.6 gallons to 1,600 gallons. At a sodium pentaborate concentration of 14.4%, the minimum volume changes from 4,288 gallons to 1,530 gallons.

C. A. Costanzo A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.

Sincerely,

~#r Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-41 0

Enclosures:

1. Amendment No. 143 to NPF-69
2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC (NMPNS)

DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 143 Renewed License No. NPF-69

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Nine Mile Point Nuclear Station, LLC (the licensee) dated July 5, 2013, as supplemented by letter dated December 6, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-69 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 143, are hereby incorporated into this license.

Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of its issuance and shall be implemented prior to the startup from the spring 2014 NMP2 refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: March 14, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 143 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page Insert Page Page 4 Page 4 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages TS 3.1.7-3 TS 3.1.7-3 TS3.1.7-4 TS 3.1.7-4

(1) Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (1 00 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, both of which are attached hereto, as revised through Amendment No.14:?are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Fuel Storage and Handling (Section 9.1, SSER 4)*

a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.

(4) Turbine System Maintenance Program (Section 3.5.1.3.1 0, SER)

The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.

(Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, Ill).

  • The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.

Renewed License No. NPF 69 Amendment 117 through 140, 141, 143

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.7 Verify each pump develops a flow rate In accordance

~ 41.2 gpm at a discharge pressure with the

~ 1327 psig. lnservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem 24 months on a from pump into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Verify all heat traced piping between 24 months storage tank and pump suction valve is unblocked.

Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after piping temperature is restored to

~ 70°F SR 3.1.7.10 Verify sodium pentaborate enrichment Prior to is ~ 92 atom percent B-1 0. addition to SLC tank NMP2 3.1.7-3 Amendment 91, 111, 117, 123, 140, 143

SLC System 3.1.7 5200 (13.6% (14.4%,

5000 5013 GAL) 5013 GAL) 4800 4600 4400 4200 4000 Ill 3800 z

g 3600

<(

~ 3400 11.1

!: 3200

....::l 0 ACCEP ABLE

> 3000 OPERA ION*

tu z 2800 2600 2400 2200 2000 1800 (13.6%, (14.4%,

1600 1600 GAL) 1530 GAL) 1400 13.0 13.5 14.0 14.5 15.0 SODIUM PENTABORATE CONCENTRATION (WEIGHT PERCENT)

  • For Boron-10 Isotope Enrichment 0!: 92 Atom Percent Figure 3.1.7-1 (Page 1 of 1)

Sodium Pentaborate Solution Volume/Concentration Requirements NMP2 3.1.7-4 Amendment 91 111 I I 143

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 143 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, LLC (NMPNS)

NINE MILE POINT NUCLEAR STATION UNIT NO.2 DOCKET NO. 50-41 0

1.0 INTRODUCTION

By letter dated July 5, 2013 (Reference 1, Agencywide Documents Access and Management System (ADAMS) Accession No. ML13197A221}, as supplemented by letter dated December 6, 2013 (Reference 2, ADAMS Accession No. ML13345A609), Nine Mile Point Nuclear Station, LLC (NMPNS, the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station Unit No.2 (NMP2), renewed facility operating license, Technical Specifications {TSs).

The proposed amendment includes changes to NMP2 TS 3.1.7, "Standby Liquid Control (SLC)

System," to increase the isotopic enrichment of boron-1 0 in the sodium pentaborate solution utilized in the SLC System and decrease the SLC System tank volume.

Specifically, the licensee proposed the following changes to the NMP2 TS 3.1.7, "Standby Liquid Control (SLC) System":

  • Revise the acceptance criterion in [Surveillance Requirement] SR 3.1. 7.10 by increasing the sodium pentaborate boron-1 0 enrichment requirement from ~ 25 atom percent to ~

92 atom percent, and make a corresponding change in TS Figure 3.1.7-1, "Sodium Pentaborate Solution Volume/Concentration Requirements."

  • Revise TS Figure 3.1.7-1 to account for the decrease in the minimum volume of the SLC system tank. At a sodium pentaborate concentration of 13.6% the minimum volume changes from 4,558.6 gallons to 1,600 gallons. At a sodium pentaborate concentration of 14.4%, the minimum volume changes from 4,288 gallons to 1,530 gallons.

The supplement dated December 6, 2013, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's initial proposed no significant hazards consideration determination noticed in the Federal Register on September 3, 2013 (78 FR 54284).

2.0 REGULATORY EVALUATION

The licensee in its letter dated July 5, 2013, identified the applicable regulatory requirements.

The regulatory requirements and guidance which the NRC staff considered in its review of the application include the following:

  • Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50 establishes the fundamental regulatory requirements with respect to the reactivity control systems.

Specifically, General Design Criterion (GDC)-26, "Reactivity control system redundancy and capability," in 10 CFR, Part 50, Appendix A to, "General Design Criteria for Nuclear Power Plants," states:

Two independent reactivity control systems of different design principles shall be provided. One of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck rods, specified acceptable fuel design limits are not exceeded. The second reactivity control system shall be capable of reliably controlling the rate of reactivity changes resulting from planned, normal power changes (including xenon burnout) to assure acceptable fuel design limits are not exceeded. One of the systems shall be capable of holding the reactor core subcritical under cold conditions.

For NMP2, these systems are the control rod drive system and the SLC system.

  • GDC-27, "Combined reactivity control systems capability," states:

The reactivity control system shall be designed to have a combined capability, in conjunction with poison addition by the emergency core cooling system, of reliably controlling reactivity changes to assure that under postulated accident conditions and with appropriate margin for stuck rods the capability to cool the core is maintained.

  • §1 0 CFR 50.62(c)(4), "Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants," (ATWS Rule) states, in part:

Each boiling-water reactor (BWR) must have [an SLC] system with the capability of injecting into the reactor pressure vessel a borated water solution at such a flow rate, level of boron concentration and boron-1 0 isotope enrichment, and accounting for reactor pressure vessel volume, that the resulting reactivity control is at least equivalent to that resulting from injection of 86 gallons per minute of 13 weight percent sodium pentaborate decahydrate solution at the natural boron-1 0 isotope abundance into a 251-inch inside diameter reactor pressure vessel for a given core design.

  • In the NRC-approved licensing topical report, NEDE-31096P-A, "Anticipated Transients Without Scram: Response to NRC ATWS Rule, 10 CFR 50.62," February 1967, General Electric provided guidance on modifications to the SLC system to ensure licensee compliance with the ATWS rule. The NRC approved the methods presented in NEDE-31096P-A for use by BWR licensees to demonstrate compliance with the ATWS Rule.

The application of this guidance demonstrates that the equivalency requirement of 10 CFR 50.62, i.e., ATWS Rule is met.

  • The radiological consequences of certain DBAs [design basis accidents] have been reevaluated using a full implementation of an Alternate Source Term as described in Regulatory Guide (RG) 1.183 and NRC Standard Review Plan (SRP) 15.0.1. The evaluation was performed at 120 percent of the original licensed power to bound the effects of future power uprates.

The supporting analyses for Alternate Source Term assume the pH of the suppression pool is controlled to prevent the re-evolution of iodine following a DBA LOCA [loss-of-coolant accident].

In addition to the above regulatory requirements, the NRC staff also considered the following in its review of the licensing application:

The NRC IN 2001-13 requested licensees to evaluate their SLC system to ensure that modifications made to the system would not cause the SLC relief valves to lift at required injection pressures, thus causing the borated water to discharge to SLC system pump recirculation, rather than to the reactor vessel.

  • Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The NRC's regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (1 0 CFR) Section 50.36, "Technical specifications." That regulation requires that the TSs include items in the following specific categories: ( 1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. However, the regulation does not specify the particular TS to be included in a plant's license.
  • The regulations in 10 CFR 50.36(c)(3) state that, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."
  • The NRC's guidance for the format and content of the licensee's TSs is contained in NUREG-1434, "Standard Technical Specifications, General Electric Plants, BWR/6,"

Revision 4.0 (ADAMS Accession No. ML12104A195).

3.0 TECHNICAL EVALUATION

The SLC system is designed to bring the reactor, at any time during the fuel cycle, from rated power conditions to a cold shutdown, without taking any credit for control rod motion following a scram. This manually operated system pumps a sodium pentaborate solution into the vessel to provide neutron absorption and achieve a subcritical reactor condition. The SLC system is designed to inject over a wide range of reactor operating pressures and to satisfy the requirements of 10 CFR 50.62, "Requirements for reduction of risk from ATWS events for lightwater-cooled nuclear power plants." The SLC System is needed only in the event that sufficient control rods cannot be inserted into the reactor core to accomplish shutdown and cooldown in the normal manner. The SLC System consists of a boron solution storage tank, two positive displacement pumps, two explosive valves (provided in parallel for redundancy),

and associated piping and valves used to transfer borated water from the storage tank to the reactor pressure vessel (RPV). The borated water solution is discharged into the RPV through the high pressure core spray (HPCS) sparger.

The specified neutron absorber solution is sodium pentaborate. It is prepared by dissolving granularly-enriched sodium pentaborate in demineralized water. The sodium pentaborate solution is discharged radially over the top of the core through the HPCS sparger. The boron absorbs thermal neutrons and thereby terminates the nuclear fission chain reaction in the uranium fuel. The sodium pentaborate also acts as a buffer to maintain the suppression pool pH at or above 7.0 to prevent there-evolution of iodine, when mixed in the suppression pool following a LOCA accompanied by significant fuel damage.

The SLC System initiates upon receiving High Dome Pressure signal or Reactor Low Vessel Level 2 with Average Power Range Monitor (APRM) confirmation (power> 4%) with 98 second nominal time delay.

3.1 Proposed TS Changes As stated previously, in its letter dated July 5, 2013, the licensee proposed to change TS 3.1.7, "Standby Liquid Control (SLC) System," by revising SR 3.1.7.1 0 and TS Figure 3.1.7-1 as follows:

  • Revise the acceptance criterion in SR 3.1.7.1 0 by increasing the sodium pentaborate boron-1 0 enrichment requirement from ~ 25 atom percent to ~ 92 atom percent, and make a corresponding change in TS Figure 3.1.7-1, "Sodium Pentaborate Solution Volume/Concentration Requirements."
  • Revise TS Figure 3.1. 7-1 to account for the decrease in the minimum volume of the SLC system tank.

3.2 NRC Staff Evaluation 3.2.1 Change in Boron-1 0 Enrichment in Sodium Pentaborate In its application dated July 5, 2013, as supplemented, the licensee performed a new analysis to determine the required boron weight-percent and enrichment, as well as the minimum pump flow rate required to safely shutdown the reactor from operation at 3988 MWt. Consistent with the requirements of 10 CFR 50.62, the analysis assumed no control rod movement and failure of the alternate rod insertion.

§10 CFR 50.62(c)(4) requires that each BWR have an SLC system with a minimum flow capacity and boron content equivalent in control capacity to 86 gallons per minute (gpm) of 13 weight-percent (wt%) sodium pentaborate solution. NEDE-31 096-P-A provides a method by which the boron equivalency requirement of §10 CFR 50.62(c)(4) can be demonstrated.

Equation 1-1 of that document was used to demonstrate injection capacity equivalency as follows:

(Q/86)x(M251/M) x (C/13) x (E/19.8);:: 1 Where:

Q = expected SLC System flow rate; M251 = mass of water in the reactor vessel and recirculation system at hot rated conditions (lbsm) for a 251-inch diameter vessel reference plant; M = Mass of water in the NMP2 reactor vessel and recirculation system at hot rated conditions (lbs);

c = Sodium pentaborate solution concentration (weight percent); and, E = Boron-1 0 isotope enrichment (19.8 atom-percent for natural boron).

As described in NMP2 USAR, Section 15G.5, since NMP2 has a 251-inch diameter reactor vessel, the value of M251/M in the above equation is equal to 1. Applying the values for the remaining parameters from Table 1 of the licensee's July 5, 2013, application, which described the "Assumptions regarding SLC System Performance yields the following:

Case 1 -for the current design of SLC System, using the current value shown in Table 1 of Reference 1:

82.4/86 x 1 x13.6/13 x 25/19.8 =1.27 > 1; and Case 2- for the proposed design of SLC System, using the new values from Table 1 of Reference 1:

80/86 X 1 X 13.6/13 X 92/19.8 = 4.52 > 1.

The above results of the injection capacity equivalency calculation demonstrate that the boron equivalent control capacity requirement of 10 CFR 50.62(c)(4) is met when the changes to the SLC System effective flow rate and the boron-1 0 isotope enrichment are included.

The NRC staff has reviewed the licensee's calculation as presented in its submission dated July 5, 2013, and finds that the calculation shows that the equivalency requirement of §1 0 CFR 50.62(c)(4) is met. Therefore, the NRC staff finds that the proposed revisions to SR 3.1.7.1 0 and TS Figure 3.1. 7-1 are acceptable by increasing the sodium pentaborate boron-1 0 enrichment requirement from <:: 25 atom percent to <:: 92 atom percent. Also, the 92 percent minimum boron-1 0 enrichment is primarily based on (a) injection of sufficient negative reactivity as soon as practical to offset the impact of a future modification, while maintaining approximately the same suppression pool heatup and (b) an 80 gpm suction flow rate from the SLC storage tank used by NMP2 is defined in TS 3.1.7.7 minus dilution flow and additional margin. The NRC staff finds the use of the above input values, as well as the proposed Boron 10 enrichment, acceptable.

3.2.2 Change in SLC System Storage Tank Solution Minimum Volume In its application dated July 5, 2013, as supplemented, the licensee demonstrated that the minimum net solution volume for injection meets all considerations for ATWS boron injection rates and Alternate Source Term suppression pool pH control, and assures that the reactor core boron concentration will be greater than 780 ppm natural boron equivalent. The proposed boron- 10 enrichment value allows the minimum solution volume stored in the SLC System storage tank to be decreased to 1,530 gallons at a sodium pentaborate concentration of 14.4%

and 1,600 gallons at a sodium pentaborate concentration of 13.6%. The mark-up of NMP2 TS Figure 3.1.7-1 provided the proposed change in the minimum SLC System storage tank solution volume. The required minimum volumes for the 13.6 wt% and 14.4 wt% solution volumes were derived by determining the minimum solution volume and then increasing the volume to account for: (1) the dead volume not pumped in the reactor that remains in the SLC System and HPCS piping; and (2) instrument accuracy. The licensee calculated the minimum tank volume requirements as follows:

  • The solution volume necessary to bring reactor coolant boron concentration to 780 parts per million (ppm) of natural boron plus 25% margin is calculated.
  • Following an injection, some of the solution will remain in the piping between the tank and the injection points (HPCS injection spargers) once the SLC pump trips on low level.

This volume is added when calculating the minimum tank volume requirements.

  • The SLC pumps automatically trip when the sensed tank level is "zero", 10.23 inches above the tank bottom to account for the overall instrumentation loop uncertainty in the level instrument.
  • The minimum required tank volume (above tank "zero" level) calculated above is further adjusted for solution temperature variation with added margin. NMP2 administratively maintains the tank solution between 1,800 and 2,000 gallons above the tank "zero" level.

The calculated results show that at a sodium pentaborate concentration of 13.6 percent the minimum volume changes from 4,558.6 gallons to 1,600 gallons and at a sodium pentaborate concentration of 14.4 percent, the minimum volume changes from 4,288 gallons to1 ,530 gallons.

Based on its review, the NRC staff finds that the proposed changes in TS Figure 3.1.7-1 to account for the decrease in the minimum volume of SLC System tank, including the methods described above, is acceptable.

In addition to the above two proposed changes, in its application, as supplemented, the licensee also addressed the following topics:

  • The current ATWS analysis is not adversely affected by the proposed changes because the reactivity insertion rate would increase by a factor greater than 3 (4.52/1.27 = 3.57) and the amount of injected boron-1 0 is not reduced.
  • The SLC System provides suppression pool buffering following a Loss of Coolant Accident (LOCA) accompanied by significant fuel damage, preventing re-evolution of iodine from the suppression pool by maintaining the pool pH above 7.0, in support of the Alternate Source Term methodology (NUREG/CR-5950)
  • The proposed boron-1 0 enrichment changes do not impact the capability to achieve and maintain a pH above 7.0 in the suppression pool following a LOCA, because the chemical properties and concentration of sodium pentaborate solution injected into the suppression pool will remain the same.
  • The maximum time available to add boron is based on a SLC storage tank operating heater failure scenario. In this heater failure scenario, the SLC pump may not function after 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> if no operator action is taken.

However, the NRC staff, upon its review of the discussion of the above topic, finds that the above topics are not directly related to the changes requested in this LAR under review.

Based on its review, the NRC staff concludes that the proposed TS changes are acceptable because the SLC system continues to meet the requirements contained in 10 CFR 50.62(c)(4) for SLC system injection capability for ATWS events. The combination of the neutron absorber boron enrichment of 88 atom-percent, minimum solution concentration of 780 ppm, and minimum SLC system pump flow rate of 80 gpm exceeds the equivalency in control capacity to 86 gpm of 13 weight-percent sodium pentaborate solution for a 251-inch inside diameter reactor vessel contained in 10 CFR 50.62(c)(4).

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20, and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative

occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (September 3, 2013 (78 FR 54284)). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

1. Letter, Nine Mile Point Nuclear Station Unit No. 2, Docket No. 50-410, License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System -

Increase in Isotopic Enrichment of Boron-10, July 5, 2013.

2. Letter, Nine Mile Point Nuclear Station Unit No. 2, Docket No. 50-410, Response to Request for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Standby Liquid Control System -Increase in Isotopic Enrichment of Boron-10, December 6, 2013.

Principal Contributor: T. Huang Date: March 14, 2014

C. A. Costanzo A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.

Sincerely, Ira/

Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-41 0

Enclosures:

1. Amendment No. 143 to NPF-69
2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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DATE 02/10/14 02/10/14 01/31/14 02/10/14 OFFICE NRR/STSB/BC OGC LPL 1-1/BC LPL 1-1/PM NAME REIIiott AGhosh BBeasley BVaidya DATE 02/19/14 03/14/14 03/14/14 03/14/14 OFFICIAL RECORD COPY

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