ML20216C727

Amend 158 to License NPF-49,allowing Licensee to Credit Soluble Boron for Maintaining Listed Element at Less than or Equal to 0.95 within SFP Rack Matrix Following Seismic Event of Magnitude Greater than or Equal to Earthquake

ML20216C727
Person / Time
Site:	Millstone
Issue date:	04/09/1998
From:	Mckee P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20216C729	List: ML20216C727 ML20216C737
References
NUDOCS 9804150028
Download: ML20216C727 (9)

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UNITED STATES g.

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3De6H001 49.....,o I

NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.

DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE

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Amendment No.

158 License No. NPF-49 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company, et al.

(the licensee) dated November 11,1997, 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 (1) 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; 1

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.

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9804150028 980409 PDR ADOCK 05000423 P

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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 Facility Operating License No. NPF-49 is hereby amended to read as follows:

(2)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.158, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in -

the license. The licensee chall 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 issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

I, "Phillip F. M. ee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

April 9, 1998 I

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ATTACHMENT TO LICENSE AMENDMENT NO.158 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.

Remove Insert i

3/4 9-ia

^3/4 9-1a 3/4 9-16 3/4 9-16 8 3/4 9-1 B 3/4 9-1 B 3/4 9-ia

• B 3/4 9-8 B 3/4 9-8 B 3/4 9-9 1

• Overflow page - no change 1

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REFUELING OPERATIONS BORON. CONCENTRATION LINITING CONDITION'FOR OPERATION 3.9.1.2 The boron concentration of the Spent Fuel Pool shall be maintained uniform and sufficient to ensure that the boron concentration is greater than or equal to 1750 ppm.

l Anolicability Whenever fuel assemblies are in.the spent. fuel pool..

l Action a.

With the boron concentration less than 1750 ppm, initiate action to bring the boron concentration in the fuel pool to at least 1750 ppm within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and b.

With the boron concentration less than 1750 ppm, suspend the movement of all fuel assemblies within the spent fuel pool and loads over the spent fuel racks.

SURVEILLANCE REQUIRENENTS 4.9.1.2 Verify that the boron concentration in the fuel pool is greater than or equal to 1750 ppm every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

NILLSTONE - UNIT 3 3/4 9-la Amendment No. M. 158 j

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REFUELING OPERATIONS 3/4.9.13 SPENT FUEL P00L - REACTIVITY LINITING CONDITION FOR OPERATION 3.9.13 The Reactivity Condition of the Spent Fuel Pool shall be such that k,ff is less than or equal to 0.95 at all. times.

APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.

EIl0N: With k ff greater than-0.95:

a..

Borate.the Spent Fuel Pool until k fr is less than or equal to 0.95, and b.

Initiate action to correct the cause of the misplaced / dropped fuel assembly, if required, and c.

Following the drop of a load on.the spent fuel racks, with fuel in the fuel rack location, close and administrative 1y control the opening of dilution pathways to the Spent Fuel Pool until Boraflex in the Spent Fuel Pool is determined to be within design, and d.

Following a seismic event of Operating Basis Earthquake (OBE) magnitude or greater:

1)

Close and administrative 1y control the opening of dilution pathways to the Spent Fuel Pool until Boraflex in the Spent Fuel Pool is determined to be within design.

2)

Notify the Commission of the action taken for Spent Fuel Reactivity control as part of the report required by Specification 4.3.3.3.2.

SURVEILLANCE REQUIRENENTS 4.9.13.1 Ensure that all fuel assemblies to be placed in Region II of the l

spent fuel pool are within.the enrichment and burn-up limits of Figure 3.9-1

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by checking the fuel assembly's design and burn-up documentation.

4.9.13.2. Following a seismic event of Operating Basis Earthquake (0BE) magnitude or greater, perform an engineering evaluation to determine that kerf is less than or equal to 0.95 and that solublesboron is not required i

for control of kefr in the Spent Fuel Pool. Pending completion of engineering evaluation, take action as required for keff being greater than 0.95.

4.9.13.3 Following the drop of a load on,the Spent Fuel Racks, with fuel in the-fuel rack location, perform an engineering evaluation to determine that k rf is less than or equal to 0.95 and that soluble boron is not required efor control of keft in the Spent Fuel Pool.

Pending completion of

. engineering evaluation, take action as required for keft being greater than 0.95.

.M.I.LLSTONE - UNIT 3 3/4 9-16 Amendment No. M. 158

3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCEriiRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain suberitical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.

The value of 0.95 or less for Kefa includes a 1%

Ak/k conservative allowance for uncertainties.

Similar'y, the boron concentration value of 2600 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron. The 2600 ppm provides for boron concentration measurement uncertainty between the spent fuel pool and i

the RWST.-

The locking closed of the required. valves during refueling operations precludes the possibility of uncontrolled boron dilution cf the filled portion of the RCS.

This action prevents flow to the RCS of unbarated water by closing flow paths from sources of unborated water.

i 3/4.9.1.2 Boron Concentration in Soent Fuel Pool During normal Spent Fuel Pool operation, the spent fuel racks are capable of maintaining Keff at less than or equal to 0.95 in an unborated water environment due to the geometry of the rack spacing and the presence of Boraflex neutron absorber in the spent fuel racks. Seismic analysis has shown that there is a possibility that the Boraflex absorber could degrade following a seismic event greater in magnitude than an Operating Basis Earthquake (OBE). At least 1500 ppm boron in Spent Fuel Pool is required in anticipation that a seismic event could cause a loss of Boraflex integrity.

If, in addition to a loss of Boraflex, a single misplaced fuel assembly is postulated, then a minimum of 1750 ppm baron is required. The 1750 ppm boron concentration requirement bounds conditions for a loss of all Boraflex in the fuel racks.

The boron requirement in the spent fuel pool also ensures that in the event of a fuel assembly handling accident involving either a dropped or misplaced fuel assembly, the Keff of the spent fuel storage rack will remain less than or equal to 0.95.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the safety analyses.

MILLSTONE - UNIT 3 8 3/4 9-1 Amendment No. JJ, pp. 158 0662

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3/4.9 REFUELING OPERATIONS BASES 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.

The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS

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The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the i

facility status or core reactivity conditions during CORE ALTERATIONS.

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N NILLSTONE - UNIT 3 B 3/4 9-la Amendment No.

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REFUELING 0PERATIONS BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.

3/4.9.12 FUEL BUILDING EXHAUST FILTER SYSTEM The limitations on the Fuel Building Exhaust Filter System ensure that all radioactive iodine released from an irradiated fuel assembly and storage pool water will be-filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Operation of the system with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the' buildup of moisture on the adsorbers and HEPA filters.

The OPERABILITY of this system i

and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

The heater kW measured must be corrected to its i

name >1 ate rating.

Variations in system voltage can lead to measurements of kW whici cannot be compared to the nameplate rating because the output kW is proportional to the square of the voltage. The filtration system removes radiciodine following a fuel handing or heavy load drop accident.

Noble gases would not be removed by the system. Other radionuclides would be scrubbed by the storage pool water. Iodine-131 has the longest half-life: -8 days. After 60 days decay time, there is essentially negligible iodine and filtration is unnecessary.

3/4.9.13 SPENT FUEL POOL - REACTIVITY The limitations described by Figure 3.9-1 ensure that the reactivity of j

fuel assemblies introduced into Region II are conservatively within the assumptions of the safety analysis.

Administrative controls have been developed and instituted to verify that the enrichment and burn-up limits of Figure 3.9-1 have been maintained for the fuel assembly.

During normal Spent Fuel Pool operation, the spent fuel racks are capable of maintaining keff at less than 0.95 in an unborated water environment due to the geometry of the rack spacing and the presence of Boraflex neutron absorber in the s sent fuel racks. Due to radiation induced embrittlement, there is a possibility t1at the Boraflex absorber could degrade following a seismic event.

At least 1500 ppe boron in the Spent Fuel Pool is required in anticipation that a seismic event could cause a complete loss of all Boraflex.

If, in addition to a loss of Boraflex, a single misplaced fuel assembly is postulated, then a minimum of 1750 ppe boron is required.

The 1750 ppe boron concentration requirement bounds conditions for a loss of all Boraflex in the fuel racks.

The action requirements of this specification recognize the possibility of a seismic event which could degrade the Boraflex neutron absorber in the spent fuel racks.' Seismic analysis has shown that there is a possibility that the Boraflex absorber could degrade following a seismic event greater in magnitude than an NILLSTONE - UNIT 3 8 3/4 9-8 Amendment No. 79. JP), 177. 158 om

REFUELING OPERATIONS BASES 3/4.9.13 SPENT FUEL POOL - REACTIVITY fcontinued)

Operating Basis Earthquake (OBE). The action statement specifies that following a seismic event at the OBE level or greater, which is approximately one-half the Safe Shutdown Earthquake (SSE) level, action will be taken to determine the condition of the Boraflex. Once a seismic event of greater than or equal to an OBE has occurred, then the boron in the Spent Fuel Pool will be credited to maintain k ra less than or equal to 0.95. The specification requires that dilution paths e

to uhe Spent Fuel Pool be closed and administrative 1y controlled until the racks can be inspected and the condition of the Boraflex can be determined.

The specification also assumes that piping systems external to the Spent Fuel Pool are mounted such that they remain leak tight following an earthquake up to the level of an SSE, or will not direct water into the Spent Fuel Pool should they leak, or have been isolated from flow to prevent leakage into the Spent Fuel Pool.

3/4.9.14 SPENT FUEL POOL - STORAGE PATTERN The limitations of this specification ensure that.the reactivity conditions of the Region I storage racks and spent fuel pool keff will remain less than or equal to 0.95.

The Cell Blocking Devices in the 4th location of the Region I storage racks are designed to prevent inadvertent placement and/or storage of fuel assemblies in the blocked locations. The blocked location remains empty to provide the flux trap to maintain reactivity control for fuel assemblies in adjacent and diagonal locations of the STORAGE PATTERN.

STORAGE PATTERN for the Region I storage racks will be established and expanded from the walls of the spent fuel pool per Figure 3.9-2 to ensure definition and control of the Region I/ Region II boundary and minimize the number of boundaries where a fuel misplacement incident can occur.

NILLSTONE - UNIT 3 B 3/4 9-9 Amendment No. U, JPP, JPJ 158 om