ML19352B123

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Amend 69 to License DPR-65,changing Tech Specs W/Respect to Decay Heat Removal Capability
ML19352B123
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/19/1981
From: Clark R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19352B124 List:
References
TAC-47390, NUDOCS 8106030142
Download: ML19352B123 (25)
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i NUCLEAR REGULATORY COMMISSION g{ j j WASHINGTON, D. C. 20586 s,,.mj NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336' MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO TA'CILITY OPERATING LICENSE Amendment No.69 License No. DPR-65 1.

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

A.

The application for amendment by hortheast Nuclear Energy Company (the licensee) dated October 17, 1980 com;ilies with the standards -*

and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can ce conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amer.dment will not be inimical to the comon defense and security okto 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 been satisfied.

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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. DPR-65 is hereby amended to, read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION b'

Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 19, 1981

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ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE N0. OPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical 1ines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages IV VIII X

XII XIII 3/4 4-1 3/4 4-la 3/4 4-lb 3/4 4-lc 3/4 4-2 (reprint) 3/4 9-8 B 3/4 4-1 B 3.4 9-2 t

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.o INDEX LIMITING C0f.DITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY...........................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.....................................

3/4 1-1 Shutdown Margin - T

> 200*F.......................

3/4 1-1 avg Shutdown Margin - T,yg < 200*F.......................

3/4 1-3 Boron Dilution... 7.~...............................

3/4 1-4 i

Moderator Temperature Coefficient (MTC)..............

3/4 1-5 Minimum Temp'erature for Criticality.................. 3/4 1-7 3/4.1.2 B0 RATION SYSTEMS.........'............................

3/4 1-8 Fl ow Path s - Shu tdown................................ 3/4 1-8 Fl ow Pa th s - Operati n g............................... 3/4 1-10

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C ha rgi n g P ump - S hu tdow n............................. 3/4 1-12 C ha rgi n g P ump s - O pera ti ng........................... 3/4 1-13 Bo ri c Aci d P ump s - S hutdown..........................

3/4 1-14 Boric Acid Pumps - Operating......................... 3/4 1-15 Borated Water Sources - Shutdown..................... 3/4 1-16 Borated Water Sources - Operati ng.................... 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...........................

3/4 1-20 Ful l Length CEA Group Position....................... 3/4 1-20 Pos i ti on I ndi cator Channel s.......................... 3/4 1-24 C EA D ro p Ti me.. 245... < re............................

3/4 1-26 Shutdown CEA Insertion Limit......................... 3/4 1-27 Regulating CEA Inse rtion Limi ts...................... 3/4 1-28 i

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MILLSTONE - UNIT 2 III Amendnent No. 38 I

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o INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER OISTRIB" TION LIMITS 3/4.2.1 L I N EAR H EAT RAT E...................................... 3 / 4 2 - 1 T

3/4.2.2 TOTAL PLANAR RADIAL PEAXING FACTOR - Fxy..............

3/4 2-6 T

3/4.2.3 TOTAL INTEGRATED RADIAL PEAXING FACTOR - Fr........... 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TI LT.................................. 3/4 2-10 3/4.2.5 FUEL RESIDENCE TIME...................................

3/4 2-12 3/4.2.6 DN S MARG I N............................................

3 / 4 2-13 3/4.3 INSTRUMENTATION 3/4. 3.1 REACTOR PROTECTIVE INSTRUMENTATION.................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..................................... 3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION............................ 3/4 3-26 Radi atio n Moni to ri ng.................................. 3/4 3-26 Incore Detectors......................................

3/4 3-30 Seismic Instrumentation...............................

3/4 3-32 Meteorological Instrumentation........................

3/4 3-36 Remote Shutdown Instrumentation.......................

3/4 3-39 Chlorine Detection Systems............................

3/4 3-42 Fi re Detection Instrumentation........................ 3/4 3-43 Acci dent Moni to ri ng................................... 3/4 3-46 3/4.4 REACTOR COOLANT SYSitM i

3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION................. 3/4 4-1 Startup and Power Opera tion...........................

3/4 4-1 Ho t S ta n d by...........................................

3 / 4 4 - l a Shutdown.............................................. 3/4 4-lb l

3/4.4.2 SA FE TY VA LV ES.........................................

3 / 4 4 - 2 3/4.4.3 R ELI E F VA LV ES.........................................

3 / 4 4-3 MILLSTONE - UNIT 2.,

IV

/mendment No. Jb, 38, 66, 69

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TU RB I N E CY CLE....................................... 3/4 7-1 Safety Va1ves........................................

3/4 7-1 Auxiliary Feedwater Pumps........................... 3/4 7-4 Steam Generator Water Addition.......................

3/4 7-5.

Condensate Storaga Tank..............................

3/4 7-6 Activity............................................

3/4 7-7 Main Steam Line Isolation Val ves.................... 3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION......

3/4 7-10 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM.........

3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM.................................

3/4 7-12 e

3/4.7.5 FLOOD LEVEL..........................................

3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SiSTEM........... 3/4 7-16 3/4.7.7 S EALED SOURCE CONTAMINATION.......................... 3/4 7-19 3/4.7.8 HYDRAULIC SNUBBERS...................................

3/4 7-21 3/4.7.9 FIRE SUPPRESSION SYSTEMS.............................

3/4 7-33 Fire Suppression Water System........................

3/4 7-33 Spray and/or Sprinkler Systems....................... 3/4 7-37 Fi re Ho s e S ta ti ons................................... 3/4 7-39 3/4 7-41 3/4.7.10 PENETRATION FIR,E BARRIERS..........

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

SOURCES..........................................

3/4 8-1 Operating.'.......f.4...T!7............................

3/4 8-1

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Shutdown..............................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS.....................

3/4 8-6 A. C. Distribution - Operating.........................

3/4 8-6 A.C. Distribution - Shutdown..........................

3/4 8-7 0.C. Distribution - Operating.........................

3/4 8-8 D.C. Distribution - Shutdown..........................

3/4 8-10

. MILLSTONE - UNIT 2 VII Amendment No. 77,35 l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION....................................

3/4 9-1 3/4.9.2 INSTRUMENTATION........................................

3/4 9-2 i

3/4.9.3 DECAY TIME........ -

3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS...............................

3/4 9-4 3/4.9.5 COMMUNICATIONS.........................................

3/4 9-5 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING...............

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING........

3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION............... 3/4 9-8 l

3/4.9.9 CONTAINMENT RADIATION MUNIT0 RING.......................

3/4 9-9 3/4.9.10 CONTAINMENT PURGE VALVE ISOLATION SYSTEM............... 3/4 9-10 3/4.9.11 WATER L EVEL - REACTOR VESSEL........................... 3/4 9-11 3/4.9.12 STO RAGE P OOL WATER L EV EL............................... 3/4 9-12 3/4.9.13 STORAGE POOL RADIATION MONITORING......................

3/4 9-13 i

i 3/4.9.14 STORAGE POOL AREA VENTILATION SYSTEM -

FUEL M0VEMENT........................................

3/4 9-14 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM -

l FUEL ST0 RAGE.........................................

3/4 9-16 l

3/4.9.16 S H I E L D ED CA S K.'.......................................

3/4 9-19 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..,,...;,............................... 3/4 10-1 l

3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS......................

3/4 10-2 l

3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY..........................................

3/4 10-3

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3/4.10.4 PHYSICS TESTS..........................................

3/4 10-4 l

3/4.10.5 C ENTER C EA M I SAL IG NM ENT................................ 3/4 10-5 MILLSTONE - UNIT 2 VIII Amendment No. 69 l

o INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY..........................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.....................................

B 3/4 1-1 3/4.1.2 BO RATION SY STEMS.. r;;7~.'............................. B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...........................

B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE.....................................

B 3/4 2-1 T

3/4.2.f TOTAL PLANAR RADIAL PEAKING FACTOR -

Fxy.............

B 3/4 2-1 T

3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F........... B 3/4 2-1 r

3/4.2.4 AZIMUTHAL POWER TI LT................................. B 3/4 2-1 3/4.2.5 FUEL RESIDENCE TIME..................................

B 3/4 2-2 3/4.2.6 DNB MARGIN...........................................

B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION...........................

B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE INSTRUMENTATION............

B 3/4 3-1

=n 3/4.3.3 MONITORING INSTRUMENTATION...........................

B 3/4 3-2 MILLSTONE - UNIT 2 IX Amendment No. 38,49 4

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INDEX BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.................... B 3/4 4-1 3/4.4.2 SAFETY VALVES........................................... B 3/4 4-1 3/4.4.3 R ELI EF VALV ES.......................................... B 3/4 4-2 3/4.4.4 PRES S U R I ZER............................................. B 3/ 4 4-2 3/4.4.5 ST EAM GENERATORS ".T'.. '.................................... B 3 / 4 4-2

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3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.......................... B 3/4 4-3 3/4.4.7 C H EM I S TR Y............................................... B 3 / 4 4-4 3/4.4.8 S.' EC I F I C ACT I V I TY....................................... B 3 / 4 4-4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................. B 3/4 4-5 3/4.4.10 STRUCTURALINTEGRITY...............l....................B'/44-11 3

3/4.4.11 CORE BARREL MOV EMENT.................................... B 3/4 4-12 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TAN KS.................................. B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYST EMS.............................. B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK (RWST)..................... B 3/4 5-2 xu.

MILLSTONE - UNIT 2 X

Amendment No.,tWu 69 l

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INDEX BASES PAGE SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT................................. B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.........._.......

B 3/4 6-3 3/4.6.3 CONTAINMENT ISO.LATION. VALVES......................... B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTR0L..............................

B 3/4 6-4 3/4.6.5 SECONDARY CCNTAINMENT.'...............................

B 3/4 6-5 rg 1

MILLSTONE - UNIT 2 XI i

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INDEX BASES PAGE SECTION 3/4./ PLANT SYSTEMS B 3/4 7-1 3/4.7.1 TURBINE CYCLE.......................................

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.....

B 3/4 7-3 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM........ B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM.7~.'.............................

B 3/4 7-4 B 3/4 7-4 3/4.7.5 FLOOD LEVEL.........................................

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM...........

B 3/4 7-4 3/4.7.7 SEALED SOURCE CONTAMINATION.........................

B 3/4 7-5

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3/4.7.8 HYDRAULIC SNUBBERS..................................

B 3/4 7-5 3/4.7.9 FIRE SUPPRESSION SYSTEMS............................

B 3/4 7-6

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3/4.7.10 PENETRATION FIRE BARRIERS........................... B 3/4 7-7

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3/4.8 ELECTRICAL POWER SYSTEMS..............................

3/4.9 REFUELING OPERATIONS 5

3/4.9.1 BORON CONCENTRATION.................................

B 3/4 9-1 B 3/4 9-1 3/4.9.2 INSTRUMENTATION.....................................

i B 3/4 9-1 3/4.9.3 DECAY TIME..........................................

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3/4.9.4 CONTAINMENT PENETRATIONS............................

B 3/4 9-1 i

B 3/4 9 3/4.9.S COMMUNICATIONS......................................

3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING............

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING.......... B 3/4 9-2 i

B 3/4 9-2 3/4.9.8 SHUTDOWN C00LERG AND COOLANT CIRCULATION.........

MILLSTONE - UNIT 2 XII Arendment No. 77,38. 69

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o INDEX BASES SECTION PAGE 3/4.9.9 and 3/4.9.10 CONTAINMENT AND RADIATION MONITORING AND CONTAINMENT PURGE VALVE ISOLATION SYSTEM.................... B 3/4 9-2 3/4.9.11 and 3/4.9.12 WATER LEVEL - REACTOR VESSEL AND STO RAG E POOL WATER L EV EL....................................

B 3/4 9-2 3/4.9.13 STORAGE POOL RADIATION MONITORING................... B 3/4 9-3 3/4.9.14 and 3/4.9.15 STORN'G[ POOL AREA VENTILATION SYSTEM... B 3/4 9-3 3/4.9.16 SHIELDED CASK....................................... B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..................................... B 3/410-1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS..,................ B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY......................................... B 3/410-1 3/4.10.4 PHYSICS TESTS.......................................

B 3/410-1 3/4.10.5 CENTER CEA MISALIGNMENT.............................

B 3/410-1 2 46 s-i t

MILLSTONE - UNIT 2 XIII Amendment No. 69 4

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a INDEX DESIGN FEATURES 1

SECTION PAGE 5.1 SITE Exclusion Area............................................

5-1 5-1 Low Popu l a ti on Zone.......................................

5-1 Flood Contro1.............................................

5.2 CONTAINMENT 5-1 Configuration.............................................

Design Pressure a'nd Temperature...........................

5-4 5-4 P e ne tra ti o n s..............................................

5.3 REACTOR CORE Fuel Assemblies...........................................

5-4 Co ntrol El ement As s embl i es................................

5-4 5.4 REACTOR COOLANT SYSTEM 5-4 Design Pressure and Temperature...........................

Volume....................................................

5-5 5.5 EMERGENCY CORE COOLING SYSTEMS............................

5-5 5.6 FUEL STORAGE C ri t i ca l i ty......... '.->t.... rt.............................

5-5 5-5 Drainage..................................................

5.7 SEISMIC CLASSIFICATION.........

5-5 l

5.8 METEOROLOGICAL TG4ER LOCATION.............................

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l MILLSTONE - UNIT 2 XIV I

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REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.

APPLICABILITY: MODES 1 and 2*.

ACTION:

With less than the above required reactor coo' ant pumps in operation, be in at least HOT STANDBY with'in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.1.1 The Flow Dependent Selector Switch shall be determined to be in the 4 pump position within 15 minutes prior to making the reactor critical 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 /> thereafter.

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MILLSTONE - UNIT 2 3/4 4-1 Amendment No. 30, 69 j

o REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION HOT STANDBY LIMITING CONCITION FOR OPERATION 3.4.1.2 a.

The reactor coolant loops listed below shall be OPERABLE:

1.

Reactor Coolant Loop A and at least one associated reactor coolant pump.

2.

Reactor Coclant Loop B and at least one associated reactor coolant pump.

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At least ons"of the above Reactor Coolant Loops shall be in operation *.

APPLICABILITY: MODE 3 ACTION:

a.

With less than the above required reactor coolant loops OPERABLE restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With no reactor coolant loop ia operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return. the required loop to operation within one hour.

SURVEILLANCE REQUIREMENTS

4. 4.1. 2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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  • All reactor coolant pumps may be de-energized for up to I hour provided (1) no operations are permitted that would cause dilution of the reactor coolant system boron cgncentration, and (2) core outlet temperature is t

maintained at least 10 F below saturation temperature.

i MILLSTONE - UNIT 2 3/4 4-la Amendment No. 69 I

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REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION SHUTDOWN LIMITING CONDITION FOR OPERATION

3. 4.1. 3 a.

At least two of the coolant loops listed below shall be OPERABLE:

1.

Reactor Coolant Loop A and its associated steam generator and at least one associated reactor coolant pump, 2.

Reactor Coolant Loop B and its associated steam generator and at least one associated reactor coolant pump, 3.

Shutdown Cooling,j. cop A,

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ShutdowECooling loop B '

b.

At least one of the above coolant loops shall be in operation *.

APPLICABILITY: MODES 4** and 5**.

ACTION:

a.

With less than the above required coolant loops OPERABLE, initiate corrective action to return the required coolant loops to OPERABLE status within one hour; be in COLD SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

b.

With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return the required coolant loop to operation within one hour.

SURVEILLANCE REQUIREMENTS

4. 4.1. 3.1 The required shutdown cooling loop (s), if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker align-ment and indicated power availability for pump and shutdown cooling loop valves.
  1. The nor:aal or. emergency powey source may be inoperable in MODE 5.

All reactor coolant pumps and shutdown cooling pumps may be deenergized for up to I hour provided: (1) no operations are permitted that would cause dilution of the reactor coolant system baron cogcentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.

    • A reactor coolant pump shall not be started witg one or more of the RCS cold leg temperatures less than or equa' to 275 F unless: (1) the i

pressurizer water volume is less than 600 cubic feet or (g) the secondary g

i water temperature of each steam generator is less than 43 F (31 F when measured by a surface contact instrument) above each of the RCS cold leg i

temperatures.

MILLSTONE - UNIT 2 3/4 4-1b Amendment No. 69 I

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REACTOR COOLANT SYSTEM-COOLANT LOOPS AND COOLANT CIRCULATION SHUTDOWN SURVEILLANCE REQUIREMENTS (Continued) 4.4.1.3.2 The required reactor coolant pump (s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE, if it is being used to meet 3.4.1.3.a by verifying the secondary side water level to be 3,10% of span,at.least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4. 4.1. 3. 4 At least one coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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i MILLSTONE - UNIT 2 3/4 4-lc Amendment No. 69

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SAFETY VALVES LIMITING CONDITION FOR OPERATI?1 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE l

with a 1tft setting of 2500 PSIA 1 %.

APPLICABILITY: MODES 4 and 5.

ACTION:

With no pressurizer code safety valve OPEP.ABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.

3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2500 PSIA ! 1%.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the -

inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.2 Each pressurizer code safety valve shall be demonstrated OPERABLE with a lift setting of 2500 PSIA 1%, in accordance with Subsection IWV-3510 of Section XI of the ASME Boiler and Pressure Vessel Code, dated July 1,1974.

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MILLSTONE - UNIT 2 3/4 4-2 Amendment No. 66

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REFUELING OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING LIMITING CONDITIO!! FOR OPERATION 3.9.7 Loads in excess of 1800 pounds shall be prohibited from travel over irradiated fuel assemblies in the storage pool.

APFLICABILITY: DURING ALL CRANE OPERATION.

ACTION:

With the requirements of the above specification not satisfied, place load in a safe condition.

SURVEILLANCE REQUIREMENTS i

4.9.7 Crane interlocks and/or physical stops which prevent crane travel with loads in excess of 1800 pounds over irradiated fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to initiation of irradiated fuel handling operations and at least once per 7 days during irradiated fuel handling operations.

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l MILLSTONE - UNIT 2 3/4 9-7 t

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l REFUELING OPERATION,S, SHUTDOWN COOLING AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdawn cooling loop shall be in operation *.

i APPLICABILITY: MODE 6 at all rea'ctor water levels.

ACTION-With less than one shutdown cooling loop in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in baron concentration of the Reactor Coolant Syst.2m.

Close all containment = penetra-tions providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE **.

APPLICABILITY: MODE 6 when the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet above the reactor pressure vessel flange.

ACTION:

l With less than the required shutdown cooling'us within one hour.

loops OPERABLE, initiate correc-tive action to return loops to OPERABLE stat

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The provisions of Specification 3.0.3 are not applicable for 3.9.8.l'and 3.9.8.2.

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SURVEILLANCE REQUIREMENTS i

4.9.8.1 At least one shutdown cooling loop shall be verified to be in opera-tion and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.9.8.2 The required shutdown cooling loops, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments i

and indicated power availability for pump and shutdown cooling loop valves.

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The shutdown cooling loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />'. period during the perfomance of CORE ALTERATIONS in the' vicinity of the reactor pressure vessel hat legs.

    • The normal or emergency power source may be inoperable for each shutdown i

cooling loop.

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MILLSTONE - UNIT 2 3/4 9-8 Amendment No. 69 4

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o 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients.

l A single reactor coolant loop with its steam generator filled above 10%

of the span provides sufficient heat removal capability for core cooling while in MODES 2 and 3; however, single failure considerations require plant cool-down if component repairs and/or corrective actions cannot be made within the allowable out-of-service time.

In MODES 4 and 5, a,sinfe reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE. Thus, i f the reactor coolant loups are not OPERABLE, this specification requires two shutdown cooling loops to be OPERABLE.

The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with baron reductions will, therefore, be within the capability of operator recognition and control.

TherestrictionsonstartingaReactorCoolantPumpduringMODESdand5 with one or more RCS cold legs 1275 F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either P ) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into or (2) by restrict-ing starting of the RCPs to wheg the gecondary water temperature of each steam generator is less than 43 F (31 F when measured by a surface contact instrument) above each of the RCS cold leg temperatures.

3/4.4.2 SAFETY VALVES j

The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safetf5Limtt"of' 2750 psia.

Each safety valve is designed to relieve 296,000 lbs per hour of saturated steam at the valve set-i point. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event i

that no safety valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpresnrization.

MILLSTONE - UNIT 2 B 3/4 4-1 Amendment No. 30, 56,69 4

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REACTOR COOLANT SYSTEM BASES During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia.

The combined relief capacity of these valves is sufficient to limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbine generator load while operating at RATED THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or steam dump valves.

3/4.4.3 RELIEF VALVES

.7' The power operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the' pressurizer code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emer-gency power source to ensure the ability to seal this possible RCS leakage path.

3/4.4.4 PRESSURIZER A steam bubble in the pressurizer with the level as programmed ensures l

that the RCS is not a hydraulically solid system and is capable of accommo-dating pressure surges during operation. The steam bubble also protects the pressurizer code safety valves and power operated relief valve against water relief. The power operated relief valves function to relieve RCS l

pressure during all design transients. Operation of the power operated relief valve in conjunction with a reactor trip on a Pressurizer-Pressure-High signal, minimizes the undesirable opening of the spring loaded j

pressurizer code safety valves.

The requirement tha,t 130 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of off-site power condition to maintain natural circulation at HOT STANDBY.

3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-tained. The program for inservice inspection of steam generator tubes is -

based on a modification of Regulatory Guide 1.83, Revision 1.

Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that thare is MILLSTONE - UNIT 2 8 3/a 4-2 Amendment No. 22, 37, 52, 66 l

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3/4.9 REFUELING OPERATIONS i

BASES 3/4.9.1 BORON CONCENTRATION The limitations on minimum baron concentration ensure that: 1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volumes havi-et access to the reactor vessel. The limitation on i

Keff of no than 0.90 is sufficient to prevent reactor criticality with all full eength rods (shutdown and regulating) fully withdrawn.

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 t

the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel 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 accident analyses, f

I 3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY

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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 pressur-ization potential while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS r&6 The requirement for canmunications capability ensures that refueling station personnel can be promptly informed of significant changes in the l

facility status or core reactivity condition during fuel or CEA movement within the reactor pressure vessel.

MILLSTONE - UNIT 2 B 3/4 9-1

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REFUELING OPERATIONS BASES 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING The OPERABILITY requirements of the cranes used for movement of fuel assemblies ensures that: 1) each crane has sufficient load capacity to lift a fuel element, and 2) the core internal: and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifing operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING' The restriction on movement of loads in excess of the nominal weight uf a fuel assembly and CEA over irradiated fuel assemblier. ensures that no more than the contents of one fuel assembly will be ruptured in the event of a release assumed in the ac,Th.i; assumption is consistent with the activity fuel handling accident.

I cident analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION t

The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove gecay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimi;;e the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling loops OPERABLE whe$n there l

is less than 23 feet of water above the core ensures that a single failure l

of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 l

feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling l

loop, adequate time is provided to initiate emergency,.rocedures to cool l

the core.

i 3/4.9.9 and 3/4.9.10 CONTAINHENT RADIATION MONITORING AND CONTAINMENT PURGE i

VALVE ISOLATION SYSTEM l

The OPERABILITY of these systems ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. 4he SPERABILITY of these systems is required to l

restrict the release of radioactive material from the containment atmosphere i

to the environment.

3/4.9.11 and 3/4.9.12 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 13% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

MILLSTONE - UNIT 2 B 3/4 9-2 Amendment No. 69

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