ML20246P158

Amend 39 to License NPF-49,changing Tech Specs to Allow Storage of Fuel W/Enrichment of Up to 5.0 Nominal Weight Percent U-235

ML20246P158
Person / Time
Site:	Millstone
Issue date:	08/29/1989
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Northeast Nuclear Energy Co (NNECO)
Shared Package
ML20246P161	List: ML20246P158 ML20246P169
References
NPF-49-A-039 NUDOCS 8909110059
Download: ML20246P158 (17)

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION J

wAsmucTON,0. C. 20555

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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.

DOCKET NO.-50-423 MILLETONE NUCLEAR POWER STATION, UNIT NO. 3

' AMENDNENT TO FACILITY OPERATING LICEN3 Amendment No. 39 License No. NPF-49 1.

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

A.

The application for amendment by Northeast f uclear Energy Company, 4

et al. (the licensee) dated Ap.*il 20, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amer.ded (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 reasonabl~ assurance (1) that the activities authorized by this amendment can in conducted without endangering the health and safety of the public, and (ii) that such attivities 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 Comission's regulations and all applicable requirements have beet; satisfied.

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Accordingly, the license is amended by changes.to the. Technical l<

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 Specifications 1:

The Technical Specifications contained in Appendix A, as revised through. Amendment No. 39 -

, and the Environmental Prntection Plan contained in Appendix B, both of which are attached hereto are

. hereby. incorporated in the license. The licensee 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, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Joh,. Stolz, Director Rrofect Directorate I/4 dWision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of' Issuance:

August 29, 1989 i

i a

i ATTACHMENT TO LICENSE AMENDMENT NO.39 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50 423 Replace the following pages of the Appendix A Technical Specifications with

. the enclosed pages..The revised pages are identified by anendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.

Remove Insert

.11 ii xii xii

'1-7 1-7 3/4 9-16 3/4 9-17 3/4 9-18 3/4 9-19 B 3/4 9-3 B 3/4 9-3 5-6 5-6

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I-INDEX DEFINITIONS:

'SECTION

_PAGE 1.0 DEFINITIONS l' 1.ACTI0N.......................................................

1-1 1.2 ACTUATION LOGIC TEST.........................................

1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST..............................

1 ~1.4 AXIAL FLUX DIFFERENCE........................................

1-1 1.5 CHANNEL CALIBRATION......................

1-1

1. 6 CHANNEL CHECK.................................................

1-1

1. 7 CONTAINMENT INTEGRITY......................................

1-2 1.8 CONTROLLED LEAKAGE............................................

1-2

1. 9

. CORE ALTERATIONS.............................................

1-2 1.10 DOSE EQUIVALENT I-131........................................

1-2 l'.11 5 - AVERAGE DI$ INTEGRATION ENERGY.............................

1-2 1.-12 ENCLOSURE BUILDING INTEGRITY.................................

1-3 1.13 ENGINEERED SAFETY FEATURES RESPONSE TIME.....................

1-3 1.14 FIRE DETECTOR OPERATIONAL TEST................................

1-3 1.15: FREQUENCY.N0TATION...........................................

1-3 1.16 IDENTIFIED LEAKAGE...........................................

1-3 1.17 MASTER RELAY TEST............................................

1-3 1.18 MEMBER (S) 0F THE PUBLIC......................................

1-4 1.19 OPERABLE - OPERABILITY...........................

1-4 1.20 OPERATIONAL MODE - M0DE......................................

1-4 1.21 PHYSICS TESTS................................................

1-4

.1.22 PRESSURE BOUNDARY LEAKAGE....................................

1-4 1.23 PURGE - PURGING....

1-4 1.24 QUADRANT POWER TILT RATI0....................................

1-5

^

1.25 RADI0 ACTIVE WASTE TREATMENT SYSTEMS..........................

1-5 1.26 RADIOLOGICAL EFFLUENT MONITORING AND 0FFSITE DOSE CALCULATION MANUAL (REM 0DCM).................................

1-5 1.P7 RATED THERMAL P0WER...................

1-5 1.28 REACTOR TRIP SYSTEM RESPONSE TIME............................

1-5

1. ?9 REPORTABLE EVENT.............................................

1-5 1.30 SHUTDOWN MARGIN..............................................

1-5 1.31 SITE B00NDARY................................................

1-6 MILLSTONE - UNIT 3 i

1N_Q.[1 DEFINITIONS SECTION

?.EGE 1.32 SLAVE RELAY TEST.......................;.....................

1-6 1.33 SOURCE CHECK.................................................

1-6 1.34 STAGGERED TEST BASIS......................

1-6

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1.35 THERMAL P0WER...............................................

1-6 i

1.36 TRIP ACTUATIhG DEVICE OPERATIONAL TEST.....................

1-6 1.37 UNIDENTIFIED LEAKAGE.......................................

1-6 1.38 UNRESTRICTED AREA............................................

1-6 1.39 VENTING.....................................................

1-7 1.40 SPENT FUEL POOL STORAGE PATTERNS.............................

1-7 l'.41 SPENT FUEL POOL STORAGE PATTERNS.............................

1-7 TABLE-1.1 FREQUENCY N0TATION......................................

1-8 j

TABLE 1.2 OPERATIONAL M0 DES.......................................

1-9 1

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Mll.LSTONE - UNIT 3 11 Amendment N7. 39

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lEEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 4

i SECTION pag [

. 3/4.8 ELECTRICAL' POWER SYSTEMS 3/4.8.1 A.C. SOURCES

' Operating................................................ 3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................ 3/4 8-8 Shutdown................................................. 3/4 8-9 3/4.8.2' D.C. SOURCES Operating................................................ 3/4 8-10 TABLE 4.8-2a 8ATTERY SURVEILLANCE REQUIREMENTS.................... 3/4 8-12 TABLE 4.8-2b BATTERY CHARGER CAPACITY............................. 3/4 8-13 Shutdown................................................. 3/4 8-14 3/4.8.3 ONSI1E POWER DISTRIBUTION Operating................................................ 3/4 8-15 Shutdown................................................. 3/4 8-17 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Ovarcurrent Protective Devices....................................... 3/4 8-18 Motor-Operated Valves Thermal Overload Protection........ 3/4 8-28 Motor-Operated Valves Thermal Overload Protection l

Not Bypassed............................................. 3/4 8-32 l

l A. C. Citrcuits Inside Containment........................ 3/48-37 3/4.9' REFUELING OPERATIONS 1

I.

L 3/4.9.1 BORON CONCENTRATION...................................... 3/4 9-1 l

3/4.9.2

-INSTRUMENTATION.......................................... 3/4 9-2 3/4.9.3 DECAY. TIME............................................... 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................ 3/49-4 3/4.9.5 COMMUNICATIONS.......................................... 3/4 9-5 HILLSTONE - UNIT 3' xi AmendmentNo.j)([39 lV

b INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS l

SECTION

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3/4.9.6 REFUELING MACHINE........................................

3/4 9-6 l

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS..................

3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION H i g h Wa t e r L e v e l.........................................

3/4 9-8 Low Water Level..........................................

3/4 9-9 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...........

3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL.............................

3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE POOL..............................

3/4 9-12 3/4.9.12 FUEL BUILDING EXHAUST FILTER SYSTEM......................

3/4 9-13 3/4.9.13 SPENT FUEL POOL - REACTIVITY.............................

3/4 9-16 3/4.9.14 SPENT FUEL POOL - STORAGE PATTERN........................

3/4 9 17 FIGURE 3.9-1 MINIMUM.BURNUP VERSUS U23S ENRICHMENT.................

3/4 9-18 FIGURE 3.9-2 REGION I LOADING SCHEMATIC............................

3/4 9-19 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS Four Loops 0perating.....................................

3/4 10-2 Three loops 0perating........................

3/4 10-3 3/4.10.3 PHYSICS TESTS..................................

3/4 10-4 3/4.10.4 REACTOR COOLANT L00PS...........................

3/4 10-5 3/4.10.5 POSITJON INDICATION SYSTEM - SHUTD0WN....................

3/4 10-6 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration............................................

3/4 11-1 Dose - Li?91ds...........................................

3/4 11-2 3/4.11.2 GASEOUS E.8 LUENTS Dose Rate................................................

3/4 11-3 Dose - Noble Gases.......................................

3/4 11-4 Dose - Radiciodines, Radioactive Material in Particulate form and Radionuclides Other Than Noble Gases............

3/4 11-5 3/4.11.3 TOTAL D0SE...............................................

3/4 11-6 MILLSTONE - UNIT 3 xii Amendment No. 39

.e 4 DEFINITIONS VENTING 1.39 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

SPENT FUEL POOL STORAGE PATTERNS:

1.40 Region I spent fuel racks contain a cell blocking device in every 4th

. location for criticality control.

This 4th location will be referred to as the blocked location.

A STORAGE PATRERN refers to the blocked location and all adjacent and diagonal Region I cell locations surrounding the blocked location.

Boundary configuration b:2.reen Region I and Region 11 must have cell blockers positioned in the outermost' row of the Region I perimeter, as-shown in Figure 3.9-2.

I.41. Region II contains no cell blockers.

MILLSTONE - UNIT 3 1-7 Amendment No. 39 i

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o TABLE-1.1 l

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FREQUENCY. NOTATION NOTATION FREQUENCY iS At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W-

'At.least once per 7 days.

4.

At-least.once per 31 days.

Q.

At least once per 92 days.

SA At least once per 184 days.

'R At least once per 18 months.

H S/U Prior to each reactor startup.

N. A.'

Not applicable.

P

-Completed prior to each release.

l, 1-MILLSTONE - UNIT 3 1-8 g

er REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2)

Verifying that the system maintains the spent fuel storage pool area at a negative _ pressure of greater.than or equal to 1/4 inch Water Gauge relative to the outside atmosphere during system operation, and 3).

Verifying that the heaters. dissipate 350 15 kW when tested in accordance with ANSI N510-1980.

e.

After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 0.05%'in accordance with ANSI N510-1980 for a DOP. test aerosol while operating the system at a f'iow rate of 20,700 cfm 10%; and f.

'After each complete or partial replacement of a charcoal adsorber

~ bank, by verifying that the cleanup system satisfies the-in place penetration and bypass leakage testing acceptance criteria of less than.0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a-flow rate of 20,700 cfm t'10%.

4.9.12.2 The Fuel Building Exhaust Filter System shall be verified to be operating within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the initiation of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during either fuel movement within the fuel storage pool or crane operations with loads over the fuel storage pool.

• ANSI N510-1980 shall be used in place of ANSI N510-1975 referenced in Regulatory Guide 1.52, Revision 2, March 1978.

i 1 ptLLSTONE - UNIT 3 3/4 9-15

p REFUELING OPERATIONS SPENT FUEL POOL - REACTIVITY 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.

ACTION: With the-requirements of the above specification not satisfied:

Borate until k,ff 1 95 is reached, and a.

b.

Perform surveillance 4.9.1.2 until the misplaced / dropped fuel assembly causing k,ff >.95 is corrected.

SURVEILLANCE RE0VIREMENTS 4.9.13 Ensure that all fuel assemolies to be placed in Region II of the spent fuel pool. are within the enrichment and burn-up limits of Figure 3.9-1 by checking the fuel assembly's design and burn-up documentation.

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f MILLSTONE UNIT 3 3/4 9-16 Amendment No. 39

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j-REFUELING OPERATIONS

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SPENT FUEL POOL - STORAGE PATTERN LIMITING CONDITION FOR OPERATION' 3.9.14. Each STORAGE PATTERN of the Region I spent fuel pool racks shall require that:

a.

Prior to storing fuel assemblies in the STORAGE PATTERN per Figure 3.9-2, the cell blocking device for the cell location must be installed.

b.

Prior to removal 'of' a cell blocking device from.the cell. location per Figure 3.9-2, the STORAGE PATTERN must be vacant of all stored fuel asseelies.

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

ACTION: Take immediate action to comply with 3.9.14(a), (b).

SURVEILLANCE REQUIREMENT 4.9.14 Verify that 3.9.14 is satisfied with no fuel assemblies stored in the STORAGE PATTERN prior to installing and removing a cell blocking device in the spent fuel racks.

Mill. STONE - UNIT 3 3/4 9-17 Amendment No. 39

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MILLSTONE UNIT 3 FUEL ASSEMBLY MINIMUM BURNUP VS INITIAL U235 ENRICHMENT FOR STORAGE IN REGION 11 SPENT FUEL RACKS Mii.LSTONE - UNIT 3 3/49-18 Amendment No. 39

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This f ace must be along the vall of the spent fuel pool, or other Region I modules.

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Region II fuel may be placed along this face l

vall of the spent fuel pool, l

or other ReRion I modules.

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Region II fuel cay be placed along this face.

Tuel Assembly Location Cell Blocker Location Figure 3.9-2 MILLSTONE UNIT 3 REGION I THREE OF FOUR FUEL ASSEMBLY LOADING SCHEMATIC FOR A TYPICAL 6 X 6 STORAGE MODULE 1

MILLSTONE - UNIT 3 3/4 9 19 Amendment No. 39

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REFUELING OPERATIONS i

. 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 naterial released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Operuion 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 OPERAB.!LITY of this system and the resulting iodine removal upacity are consistent with the assumptions of the safety analyses.

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

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

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 k,ff wiH 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 inadverter.t placement and/or storage of fuel

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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.

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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.

MILLSTONE - UNIT 3 B 3/4 9-3 Amendment No. 39

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!IS:0N TEATURES 5.?

FEACTOR CORE TUEL ASSEM3L!ES 5.3.1 The core shall centain 193 fuel assemblies with each fuel assembly containing 26L fuel rods clad with 2irealoy-4 Each fuel red shall have a n::inal a:tive fuel length of 144 inches. The initial core leading shall have a caxima: nominal enrich =ent of 3.4 weight percent U-235 Reload fuel shall-be similar in physical design to the initial core leading and shall have a maxima: nominal enrichment of 3.8 weight percent U-235 CONTFDL F00 ASSEv.3;IES 5'3 2 The core shall contain 61 full-length control red assemblies. The full-length centrol red asse:blies shall contain a no:inal 142 inches of abs:rber caterial. The n::inal values of absorber material shall be 95 3%

haf.iu: and 4.55 natural zirconiu:.

All control rods shall be clad with stainless steel.

5.t FIA !:F COOLANT SYSTEM EES:0N ? FESS *.'EE AND TEMPERATURE 5.4.1 Tne Peacter coora.t Syste: is designed and shall be maintained:

a.

Ir. accordance with the Code require =ents specified in Section 5.2 of the TSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.

for a pressure of 2500 psia, and c.

for a temperature of 6500F, except for the pressurizer which is 6800f.

TOLUME 5.4.2.

The total water and steam volume of the Reactor Coolant System is 12,240 cubic feet at a nominal 7,yg of 5870T.

5.5 METEOPOLODICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 51-3 MILLSTONE - UNIT 3 5-5 Amendment No. )4I, 39

DESIGN FEATORES 5.6 FUEL-STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

A k ((ted water. equivalent to less than or equal to 0.95. when flooded with a.

unb8 b.

A nominal 10.35-inch center-to-center distance between fuel assemblies placed in the storage racks.

Fuel assemblies stored in Region I of the spent fuel pool may have a c.

maximum nominal. fuel enrichment of up to 5.0 weight percent U Region I is designed to permit starage of fuel in a 3-out-b4 array with the 4th storage location blocked as shown in Figure

-3.9-2.

d.

Fuel assemblies stored in Region II of the spent fuel pool may have a maximum nominal fuel enrichment of up to 5.0 weight percent, conditional upon compliance with Figure 3.9-1 to ensure that the design burnup of the fuel has been sustained.

Racks are qualified to maximum nominal enrichment of 5.0 w/o U e.

however, actual plant analysis is performed on a Cycle 3 specNIc; basis due to considerations on the pool cooling and piping systems and pool structure.

DRAINAGE 5.6.2 The spent fuel storage pool is' designed and shall be maintained to prevent inadvertent draining of the pool below elevation 45 feet.

CAPACITY 5.6.3 The spent fuel storage pool contains 756 storage locations of which a maximum of 100 locations will be blocked.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT i

5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

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1 MILLSTONE UNIT 3 5-6 Amendment No. 39 L-

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