Text

Amend 104 to License DPR-65,deleting App B Tech Specs, Providing New App a Sections & Defining Limiting Conditions for Operation & Surveillance Requirements for Radioactive Liquid & Gaseous Effluent Monitoring
	ML20132A841
Person / Time
Site:	Millstone
Issue date:	09/16/1985
From:	Butcher E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20132A847	List: ML20132A841; ML20132A849; ML20132A855;
References
	TAC-49588, NUDOCS 8509260035
	Download: ML20132A841 (63)
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g UNITED STATES g

p, NUCLEAR REGULATORY COMMISSION L

j WASHINGTON, D. C. 20555

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NORTHEAST NUCLEAR ENERGY COMPANY l

THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE

. Amendment No.104 License No. DPR-65 1.

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

A.

The application for amendment by Northeast Nuclear Energy Company, etal.(thelicensee),datedMay 29, 1985, complies 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 Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without end 1gering the health and.

safety of the public, and (ii) that such activities will be j

conducted in compliance with the Comission's regulations; 4

i D.

The issu'ance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and,

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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 licensi 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.104, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective on January 1,1986.

FOR THE NUCLEAR REGULATORY COMMISSION C-<

Edward J.

utcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: September 16, 1985 O

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ATTACHMENT TO LICENSE AMENDMENT NO.104 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET N0. 50-336

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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 lines indicating the area of change. The corresponding overleaf pages are provided to maintain document completeness.

Appendix A Remove Pages Insert Pages I-XVII I-XVIII 1-4 1-4 1-6 1-6 1-8 1-8 1-9 (renumbered) 3/4 3-50 thru 3/4 3-60 3/411-1 thru 3/411-6 B 3/4 3-5 B 3/4 11-1 thru B 3/4 11-4 6-14 6-14 6-16 6-16 6-17 6-17 6-21 6-21 I

6-22 6-22 renumbered) 6-23 6-23 renumbered) 6-24 6-24 renumbered) 6-25 6-25 renumbered) 6-26 Appendix B Delete Appendix B in its entirety, including title page j

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.INDEX DEFINITIONS SECTION

. PAGJ 1.0 DEFINITIONS 1-1 Defined Terms..............................................

1-1 Thermal Power..............................................

1-1 Rated Thermal Power........................................

1-1 O pe ra ti on al Mod e...........................................

1-1 Action.....................................................

1-1 O pe rabl e - O perabi l i ty.....................................

1-1 Reportabl e Occurrence......................................

C o n ta i nme n t I nt e g ri ty......................................

1-2 C ha nn el Cal i bra ti o n........................................

1-2 1-2 Channel Check..............................................

i Channel Functional Test....................................

1-2 Core Alteration............................................

1-3 1-3 Shutdown Margin............................................

1-3 I de n ti fi e d Leaka ge.........................................

2 1-3 :

Unidentified Leakage.......................................

P ressu re Bounda ry Leakage..................................

1-3 1-3 l

Co ntroll ed Leaka ge.........................................

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Az i mu th al P owe r T i 1 t.......................................

1-4 1-4 Dose Equi val ent I-131......................................

1-4 E-Average Disintegration Energy............................

1-4 Staggered Test Basis.......................................

1-4 Frequency Notation.........................................

1-5 Axi al S ha pe I ndex..........................................

1-5 Unrodded Planar Radial Peaking Factor - FXy................

Encl osure Buil di ng Integri ty...............................

1-5 R'eactor Trip System Response Time...................... fii.

1-5 Engineered Safety Feature Response Time....................

1-5 1-6 Physics Tests..............................................

Unrodded Integrated Radial Peaking Factor - F.............

1-6 l

r MILLSTONE - UNIT 2 I

Amendment No. d. 38,104

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1 INDEX 1

DEFINITIONS SECTION PAGE i

1.0 DEFINITIONS i

SOURCE CHECK..................................................

1-6 i

1 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)................................

1-6 4

i RADIOACTIVE WASTE TREATMENT SYSTEMS...........................

1-6 i

1 PURGE - PURGING...............................................

1-6 j

VENTING.......................................................

1-8 1

i MEMBER (S) 0F THE PUBLIC.......................................

1-8 4

i SITE B0VNDARY.................................................

1-8 i

I UNRESTRICTED AREA.............................................

1-8 1

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j MILLSTONE - UNII 2 II Amendment No.

104 i

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INDEX 4

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS PAGE SECTION 2.1 SAFETY LIMITS i

2-1 Reactor Core.................................................

2-1 Reactor Coolant System Pressure.............................

2.2 LIMITING SAFETY SYSTEM SETTINGS 2-3 l

Reacto r Tri p Se tpoi nts......................................'

4 1,

BASES o

2 PAGE SECTION i

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2.1 SAFETY LIMITS B 2-1 i

Reactor Core................................................

B 2-3 Reactor Coolant System Pressure.............................

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2.2 LIMITING SAFETY SYSTEM SETTINGS B 2-4 Reactor Trip Setpoints......................................

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MILLSTONE - UNIT 2 III Amendment No.104 l

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INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS' SECTION PAGE i

j 3/4.0 APPLICABILITY...........................................

3/4 0-1 l

3/4.1 REACTIVITY-CONTROL SYSTEMS l

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j 3/4.1.1 B0 RATION CONTR0L.....................................

3/4 1-1 l

Shutdown Margin - T,yg > 200*F.......................

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

3/4 1-3 i

Boron Dilution...................................... 3/4 1-4 i

Moderator Temperature Coefficient (MTC).............. 3/4 1-5 Minimum Temperatu re for Cri ticali ty.................. 3/4 1-7 1

1 3/4.1.2 BORATION SYSTEMS.....................................

3/4 1-8 i

Fl ow Pa th s - S hu tdown................................ 3/4 1-8 Flow Paths - Operating...............................

3/4 1-10 t

I C ha rgi ng P unp - S hu tdown............................. 3/4 1-12 l

C ha rgi n g P ump s - O pera ti ng........................... 3/4 1-13 I

Bo ri c Aci d Pump s - S hu tdown.......................... 3/4 1-14 Bori c Aci d Pumps - Opera ting......................... 3/4 1-15 J

Bo rated Water Sources - Shutdown..................... 3/4 1-16 i

Borated Water Sources - Operating.................... 3/4 1-18

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l 3/4.1.3 MOVABLE CONTROL ASSEMBLI ES........................... 3/4 1 -20 Full Length CEA Group Position....................... 3/4 1-20 Pos i ti on Indi cator Channel s.......................... 3/4 1-24 l

C E A D ro p T i me........................................ 3/4 1-26 i

Shutdown CEA Insertion Limit......................... 3/4 1-27 Regulating CEA Insertion L1mits...................... 3/4 1-28 h

i i-f MILLSTONE - UNIT 2 IV Amendment No. AS,104 J

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE..........................................

3/4 2-1 T

3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - FXy..................

3/4 2-5 T

3/4.2.3 TOTAL INTEGRATED RADI AL PEAKING FACTOR - F...............

3/4 2-9 r

j 3/4.2.4 AZ IMUTHAL POWE R T I LT...................................... 3/4 2-10 3/4.2.5 Deleted l

3/4.2.6 DN B MA RG I N................................................

3/ 4 ? - 13 I

3/4.3 INSTRUMENTATION i

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION........................

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM i

I NSTRUMENTAT I ON......................................... 3/ 4 3 - 10 3/4.3.3 MONITORING INSTRUMENTATION................................

3/4 3-26 Radiation Monitoring......................................

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 Chlori rie Detection Systems................................ 3/4 3-42 Fire Detection Instrumentation............................

3/4 3-(3 Accident Moni tori ng....................................... 3/4 3-4 6 Radioactive Liquid Effluent Monitoring Instrumentation....

3/4 3-50 l

Radioactive Gaseous Effluent Monitoring Instrumentation...

3/4 3-56 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.....................

3/4 4-1 l

' Startup and Power Operation...........................W.. 3/4 4-1 i

Ho t S t a n d by............................................... 3/ 4 4 -l a l

S h u t d own.................................................. 3 / 4 4 - 1 b I

MILLSTONE - UNIT 2 V

Amendment No. 75.38.66.69.79,104

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INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 1

i SECTION PAGE 3/4.4.2 SAFETY VALVES............................................

3/4 4-2 l

l 3/4.4.3 RELIEF VALVES............................................

3/4 4-3 l

l 3/4.4.4 PRESSURIZER..............................................

3/4 4-4 l

3/4.4.5 STEAM GENERATORS.........................................

3/4 4-5 r

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3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE........................... 3/4 4-8 i

Leakage Detection Systems................................ 3/4 4-8 i

Reactor Coolant System Leakage...........................

3/4 4-9 i

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3/4.4.7 C H EM I ST RY................................................

3/4 4 - 10

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l 3/4.4.8 SPECIFIC ACTIVITY........................................

3/4 4-13 i

3/4.4.9 PRESSURE /TEMPE RATURE LIMITS.............................. 3/4 4-17 i

Reac tor Cool a nt Sys tem................................... 3/4 4-17 j

Pressurizer..............................................

3/4 4-21 i

Overpressure Protection Systems..........................

3/4 4-21a 4

1 3/4.4.10 STRUCTURAL INTEGRITY.....................................

3/4 4-22 1

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

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3/4.5.1 SAFETY INJ ECTION TAN KS...................................

3/4 5-1, dr' 3/4.5.2 ECCS SUBSYSTEMS - T,yg >, 300* F........................... 3/4 5-3 j

3/4.5.3 ECCS SUBSYSTEMS - T,yg < 300'F........................... 3/4 5-7 l

1 3/4.5.4 REFUELING WATER STORAGE TANK............................. 3/4 5-8 1

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MILLSTONE - UNIT 2 VI Amendment No. 58.73,104 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

' PAGE SECTION i

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..................................

3/4 6-1 1

Contai nme n t I n te g ri ty................................

3/4 6-1 1

i Co n ta i nme nt Lea ka ge..................................

3/4 6-2 Co nta i nme n t Ai r Lock s................................

3/4 6-6 Internal Pressure....................................

3/4 6-8 A i r Te mpe ra t u re......................................

3/4 6-9 Containment Structural Integri ty.....................

3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.................

3/4 6-12 l

Contai nment Spray System.............................

3/4 6-12 Containment Ai r Reci rculation System.................

3/4 6-14 j

3/4.6.3 CONTAINMENT ISOLATION VALVES.........................

3/4 6-15 j

3/4.6.4 COMBUSTIBLE GAS CONTR0L..............................

3/4 6-20 Hyd roge n Analyze rs................................... 3/4 6-20 Electric Hydrogen Recombiners - W................... 3/4 6-21 Hydrogen Purge System................................

3/4 6-23 Post-Inci dent Reci rculation Sys tems..................

3/4 6-24 l

3/4.6.5 SECONDARY CONTAINMENT................................

3/4 6-25 Enclosu're Building Filtration System.................

3/4 6-25 i

i Enclosure Building Integri ty.........................

3/4 6-28 l

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MILLSTONE - UNIT 2 VII Amendment No.104 l

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INDEX LIMITIttG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

PAGE, 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.........................................

3/4 7-1 S a fe ty Va 1 ve s......................................... 3/ 4 7-1 Auxil iary Feedwater Pumps............................. 3/4 7-4 Condensa te S torage Tank............................... 3/4 7-6 Ac t i v i ty............................................... ' 3/ 4 7 - 7 Main Steam Line Isolation Va1ves......................

3/4 7-9 i

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 3/4.7.5 FLOOD LEVEL........................................... 3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.............

3/4 7-16 3/4.'7. 7 SEALED SOURCE CONTAMINATION...........................

3/4 7-19 3/4.7.8 S N UB B E RS.............................................. 3/4 7-21 4

3/4.7.9 FIRE SUPPRESSION SYSTEMS..............................

3/4 7-33

)l Fi re Suppres sion Water System......................... 3/4 7-33

Spray and/or Sprinkler Sys tems........................ 3/4 7-37 Fire Hose Stations....................................

3/4 7-39

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3/4.7.10 PENETRATION FIRE BARRIERS.............................

3/4 7-41

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3/4.8 ELECTRICAf. POWER SYSTEMS l

3/4.8.1 A.C. SOURCES..........................................

3/4 8-1 Op e ra t i n g............................................. 3 /4 8-1 S h u t d ow n.............................................. 3 / 4 8-5 l

3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS.....................

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

3/4 8-6 A.C. Distribution - Shutdown.........................".5 3/4 8-7 D.C. Distribution - Opera ting......................... 3/4 8-8 D.C. Distribution - Shutdown..........................

3/4 8-10 4

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I MILLSTONE-UNIT 2 VI!!

Amendment No. U. M. $ N.104 I

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION

s. -

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONC ENTRAT ION......................................

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

3/4 9-2 3/4.9.3 C E C AY T I ME............................................... 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 3/4.9.9 CONTAINMENT RADIATION M0NITORING.........................

3/4 9-9 3/4.9.10 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.................

3/4 9-10 3/4.9.11 WATER LEVEL - REACTOR VESSEL.............................

3/4 9-11 3/4.9.12 STORAGE POOL WATER LEVEL.................................

3/4 9-12 3/4.9.13 STORAGE POOL RADIATION M0NITORIN'G........................

3/4 9-T3 3/4.9.14 STORAGE POOL AREA VENTILATION SYSTEM - FUEL MOVEMENT.....

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

3/4 9-1,6 3/4.9.16 S H I EL DE D C AS K............................................ 3/ 4 9-19 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 S H UT DOWN MARG I N.......................................... 3 / 4 10- 1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS........................

3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR CRITICALITY.... 3/4 10-3 3/4.10.4 PHYSICS TESTS....................................... 7..

3/4 10-4 3/4.10.5 CENTER CEA MISALIGNMENT..................................

3/4 10-5 MILLSTONE - UNIT 2

!X Amendment No. 9,104 l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE e-3/4.11 RA010 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................

3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS........................................

3/4 11-3 3/4.11.3 TOTAL D0 S E...............................................

3/ 4 1 1 - 6 55

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au MILLSTONE - UNIT 2 X

Amendment No. 104

4 INDEX 4

BASES 4

i SECTIO'4 PAGE 3/4.0 APPLICABILITY..........................................

B 3/4 0-1 I

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.....................................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS.....................................

B 3/4 1-2 l

3/4.1.3 MOVABLE CONTROL ASSEM8 LIES...........................

B 3/4 1-3 2

i 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE.....................................

B 3/4 2-1 T

3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - F B 3/4 2-1 l

xy.............

T 3/4.2.3 TOTAL INTEGRATED RADIAL PEAFING FACTOR - F........... B 3/4 2-1 7

4 3/4.2.4 AZIMUTHAL POWER TILT.................................

D 3/4 2-1 3/4.2.5 Deleted l

j 3/4.2.6 DNB MARGIN...........................................

B 3/4 2-2 j

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3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION...........................

B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE INSTR'JMENTATION............ B 3/4 3-1 a

j 3/4.3.3 MONITORING INSTRUMENTATION...........................

B 3/4 3-2 1

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MILLSTONE - UNIT 2 XI Amendment No. JA.49.104 I

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INDEX BASES 1

4 SECTION I_

PAGE 3/4.4 REACTOR COOLANT SYSTEM i

3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION..................... B 3/4 4-1 I

3/4.4.2 SAFETY VALVES............................................. B 3/4 4-1 3/4.4.3 RELIEF VALVES............................................. B 3/4 4-2 i

3/4.4.4 PRESSURIZER............................................... B 3/4 4-2 3/4.4.5 STEAM GENERATORS.......................................... 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 CHEMISTRY................................................. B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY......................................... B 3/4 4-4 5

3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................... B 3/4 4-5 1

3/4.4.10 STRUCTURAL INTEGRITY...................................... B 3/4 4 7 l

i 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

,1 3/4.5.1 SAFETY INJECT ION TAN KS.................................... B 3/4 4-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS................................

B 3/4 5-1 3/4.5.4 REFUECING WATER STORAGE TANK (RWST)....................... B 3/4 5-2 3

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3/4.6 CONTAINMENT SYSTEMS l

3/4.6.1 PRIMARY CONTAINMENT.......................................

B 3/4 6-1 i

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS......................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES.............................. B 3/4 6-3 i

l 3/4.6.4 COMBUSTIBLE GAS CONTR0L................................... B 3/4 6-4 3/4.5.5 SECONDARY CONTAINMENT.....................................

B 3/4 6-5 1

l MILLSTONE - UNIT 2 XII Amendment No.88,89,72,104 i

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INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS i

3/4.7.1 TURBINE CYCLE......................................... B 3/4 7-1 l

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.................................. B 3/4 7-4 1

3/4.7.5 FLOO D L EVEL........................................... B 3/4 7-4 I

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 3/4.7.8 S NUBB E RS.............................................. B 3/ 4 7-5 3/4.7.9 FI RE SUPPRESSION SYSTEMS.............................. B 3/4 7-6 l

3/4.7.10 P EN ET RATION FIRE BARRI E RS............................. B 3/4 7-7 3/4.8 EL ECTRI CAL POWER SYSTEMS................................. B 3/4 8-1 i

I 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRAT ION................................... B 3/4 9-l '

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3/4.9.2 INSTRUMENTATION.......................................

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

-o 3/4.9.4 CONTAINMENT PENETRATIONS............................. 8 3/4 9-1 4

3/4.9.5 COMMUNICATIONS........................................

B 3/4 9-1 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING.............. B 3/4 9-2 i

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............ B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLING CIRCULATION.............

8 3/4 9-2

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l MILLSTONE-UNIT 2 XI!!

Amendment No. JJ,35,$p,pf,IO4 l

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BASES l

6 i

g-t SECTION PAGE l

l 3/4.9.9 and 3/4.9.10 CONTAINMENT AND RADIATION MONITORING AND i

i CONTAINMENT PURGE VALVE ISOLATION SYSTEM.................... B 3/4 9-2 l

3/4.9.11 and 3/4.9.12 WATER LEVEL - REACTOR VESSEL AND STORAGE P0OL WATER LEVEL.................................... 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 STORAGE POOL AREA VENTILATION SYSTEM... B 3/4 9-3 i

3/4.9.16 S H I E L D E D C AS K....................................... B 3/4 9-3 i

3/4.10 SPECIAL TEST EXCEPTIONS j

3/4.10.1 SHUTOOWN MARGIN..................................... B 3/410-1 i

l 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS................... B 3/410-1 I

3/4.10.3 PRESSURE / TEMPERATURE LIMITATION - REACTOR l

CRITI'CALITY......................................... B 3/410-1 1

j 3/4.10.4 PHYSICS TESTS....................................... B 3/410-1 j

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

3/4.11 RADI0 ACTIVE EFFLUENTS

~

j 3/4.11.1 LIQUID EFFLUENTS.....................................

B 3/4 11-1 i

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3/4.11.2 GASEOUS EFFLUENTS....................................

B 3/4 11-2 I

j 3/4.11.3 TOTAL 00SE...........................................

B 3/4 11-4 t

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i MILLSTONE - UNIT 2 XIV Amendment No. W.104 i

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INDEX 3

i DESIGN FEATURES s

SECTION PAGE 5.1 SITE t

i Exclusion Area............................................

5-1 5-1

)

Low Population Zone.......................................

Flood Contro1.............................................

5-1 5.2 CONTAINMENT 5-1 1

Configuration.............................................

5-4 1

Design Pressure and Temperature...........................

i 5-4 j

Pe ne t ra ti on s..............................................

4 l.

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

5-4 Control Element As sembl ies................................

5-4 2

J 5.4 REACTOR COOLANT SYSTEri Design Pressure and Temperature...........................

5-4 Vo1ume....................................................

5-5

]

j 5.5 EMERGENCY CORE COOLING SYSTEMS............................

5-5 I

l 5.6 FUEL STORAGE i

Criticality...............................................

5-5 5-5 I

D r a i na ge..................................................

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

5-5 r

i 5.8 METEOROLOGICAL TOWER LOCAT!0N.............................

5-5 i

MILLSTONE - UNIT 2 XV Amendment No. 104 l

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4 INDEX ADMINISTRATIVE CONTROLS PAGE SECTION 1

6.1 RESPONSIBILITY............................................

6-1 6.2 ORGANIZATION 0ffsite...................................................

6-1 Facility Staff............................................

5-1 i

6.3 FACILITY STAFF QUALIFICATIONS.............................

6-1 1

[

6.4 TRAINING..................................................

6-5 1

6.5 REVIEW AND AUDIT i

6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

Function................................................

6-5 Composition.............................................

6-5 Alternates..............................................

6-5 Meeting Frequency.......................................

6-6 l

Quorum..................................................

6-6 Responsibilities........................................

6-6 Authority...............................................

6-7 Records.................................................

6-7 6.5.2 SITEOPERATIONSREVIEWCOMMITTEE(SORC)

Function................................................

6-7 j

Composition.............................................

6-7 q

Alternates..............................................

6-8

}

Meeting Frequency.......................................

6-8 3

Quorum..................................................

6-8 j

Responsibilities........................................

6-8

]

Authority...............................................

6-9 Records.................................................

6-9

=

i t

MILLSTONE - UNIT 2 XVI Amendment No.104 l

1 I

INDEX ADMINISTRATIVE CONTROLS

{

SECTION PAGE 6.5.3 NUCLEARREVIEWBOARD(NRB)

Function................................................

6-9 Composition.............................................

6-10 C o n s ul ta n t s............................................. 6-10 Meeting Frequency.......................................

6-10 Quorum..................................................

6-10 Review..................................................

6-11 Audits..................................................

6-11 Authority...............................................

6-12 Records.................................................

6-12 i

6.5.4 SITE NUCLEAR REVIEW BOARD (SNRB)

Function................................................

6-13 j

C ompo s i t i o n............................................. 6-13 I

1 Consultants.............................................

6-13 Meeting Frequency.......................................

6-13 Q u o ru m.................................................. 6-13 Review..................................................

6-14 Audits..................................................

6-14 1

Authority...............................................

6-15 Records.................................................

6-15 I

6.6 REPORTABLE OCCURRENCE ACTI0N.................................

6-15 6.7 SAFETY LIMIT VIOLATION.......................................

6-15 l

6.8 PROCEDURES...................................................

6-16 i

t t

I I

e MILLSTONE - UNIT 2 XVII Amendment No. 45 104 l

t INDEX ADMINISTRATIVE CONTROLS SECTION PAGE s.

6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES...............

6-17 6.9.2 SPECIAL REP 0RTS..........................................

6-22 6.10 RECO RD R ET E NT I ON............................................. 6 - 2 3 1

I 6.11 RADI ATION PROTECTION PR0 GRAM.................................

6-24 6.12 H I GH RAD I AT ION AREA.........................................

6-24 6.13 SYSTEMS INTEGRITY............................................

6-25 6.14 IOD I N E M0N ITOR I NG............................................

6-2 5 1

I 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)................................

6-26 6.16 RADIOACTIVE WASTE TREATMENT..................................

6-26 i

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1 i

~

MILLSTONE - UNIT 2 XVIII Amendment No. 79.36.83.66.J93.104 l i

DEFINITIONS I.-

CORE ALTERATION 1.12 CORE ALTERATION shall be the movement or manipulation of any com-ponent within the reactor pressure vessel with the vessel head removed and fuel in the vessel.

SHUTDOWN MARGIN 1.13 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a.

Leakage into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

UNIDENTIFIED LEhKAGE 1.15 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

l PRESSURE BOUNDARY LEAKAGE 1.16 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vtssel wall.

CONTROLLED LEAKAGE 1.17 CONTROLLED LEAKAGE shall te the water flow from the reactor coolant pump seals.

MILLSTONE - UNIT 2 1-3 Amendment No. 38

DEFINITIONS AZIMUTHAL POWER TILT - Tn 1.18' AZIMUTHAL POWER TILT shall be the maximum difference betben the i

power generated in any core quadrant (upper or lower) and the average power of all quadrants in that half (upper or lower) of the core divided by the average power of all quadrants in that half (upper or lower) of the core.

Power in any core quadrant (upper or lower)

,)

AZIMUTHAL POWER TILT =axAverage power of all quadrants (upper or lower) m

.)

DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (micro-1 curie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Regulatory Guide 1.109 Rev.1. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I."

E-AVERAGE DISINTEGRATION ENERGY 1.20 E shall be the average sum of the beta and gama energies per dis-integration (in MEV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

~

STAGGERED TEST BASIS 1.21 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subinterval, and b.

The testing of one system, subsystem, train or other -

designated component at the beginning of each subinterval.

FREQUENCY NOTATION 1.22 The FREQUENCY NOTATION specified for the perfomance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

MILLSTONE - UNIT 2 1-4 Amendment No. 35,104 l

l

1 DEFINITIONS AXIAL SHAPE INDEX 1.23 The AXIAL SHAPE INDEX (Y ) used for normal control and indication l

E is the power level detected by the lower excore nuclear instrument detectors (L) less the power level detected by the upper excore nuclear instrument detectors (U) divided by the sum of these power levels. The AXIAL SHAPE INDEX (Y ) used for the trip and pretrip signals in the 7

reactor protection sfstem is the above value (Y ) modified by an appropriate r

4 multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel.

YE=

Yy = AYE+B UNRODDED PLANAR RADIAL PEAKING FACTOR - Fg 1.24 The UNRODDED PLANAR RADIAL PEAKING FACTOR is the maximum ratio of the peak to average power density of the individual fuel rods in any of the unrodded horizontal planes, excluding tilt.

ENCLOSURE BUILDING INTEGRITY 1.25 ENCLOSURE BUILDING INTEGRITY shall exist when:

1.25.1 Each door in each access opening is closed except when the access opening is being used for normal transit entry *.

and exit, and 1.25.2 The enclosure building filtration system is OPERABLE.

~

REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval I

from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

i ENGINEERED SAFETY FEATURE RESPONSE TIME, 1.27 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time I

interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of i

MILLSTONE - UNIT 2 1-5 Amendment No. 38 w

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_ DEFINITIONS ENGINEERED SAFETY FEATURE RESPONSE TIME (Continued)

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performing its safety function (i.e., the valves travel to thifr required l

positions, pump discharge pressures reach their required values, etc.).

Times shall include diesel generator starting and sequence loading delays i

where applicable.

PHYSICS TESTS I

j 1.28 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core 'and related instrumentation and 4

1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions l

of 10 CFR S0.59, or 3) otherwise approved by the Comission.

UNRODDED INTEGRATED RADIAL; PEAKING FACTOR - Fr 1

1.29 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the pea.k pin power to the average pin power in an unrodded core, excluding tilt.

l SOURCE CHECK i

1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.

4 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCU 1.31 A RADIOLOGICAL EFFLUENT MONITORING MANUAL shall be a manual containin the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those

{

radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An OFFSITE DOSE CALCULATION MANUAL shall 4

be a manual containing the methodology and parameters to'be used in the cal-culation of offsite doses due to radioactive gaseous and liquid effluents and in the calculatiron of gaseous and liquid effluent monitoring instrumentation.

alam/ trip setpoints.

tion 6.16.

Requirements of the REMODCM are provided in Specifica-RADIOACTIVE WASTE TREATMENT SYSTEMS 1.33 RADI0 ACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over radioactive material in order to meet the LCOs set forth in these specifications.

PURGE - PURGING 1.34 PURGE or PURGING is the controlled process of discharging tir or gas i

from a confinement to maintain temperature, pressure, humidity, concentration i

or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

\\

MILLSTONE - UNIT 2 1-6 i

Amendment No. M,104

TABLE 1.1 OPERATIONAL MODES.

REACTIVITY

% RATED AVERAGE COOLANT MODE CONDITION, K THERMAL POWER

TEMPERATURE ff

-1.

POWER OPERATION

> 0.99

> 5%

> 300 F 2.

STARTUP

> 0.99 1 5%

> 300 F 3.

HOT STANDBY

< 0.99 0

> 300 F 4.

HOT SHUTDOWN

< 0.99 0

300*F> T

> 200 F avg t

5.

COLD SHUTDOWN

< 0 98 0

1 200*F i

6.

REFUELING **

< 0.95 0

140 F

Excluding decay heat.

Fuel'in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

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i l

MILLSTONE - UNIT 2 1-7 Amendment No. 61,7 2 4

r

DEFINITIONS i

VENTING 1.35 VENTING is the controlled process of discharging air or das from a confinement to maintain _ temperature, pressure, humidity, concestration or other operatir.g 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.

MEMBER (S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

The term "REAL MEMBER OF THE PUBLIC" means an individual who is exposed to existing dose pathways at one particular location.

SITE B0UNDARY 1.37 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.

UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any '

area within the site boundary used for residential quarters or industrial, commercial institutional and/or recreational purposes.

1 em MILLSTONE - UNIT 2 1-8 Amendment No. 104 4

i m

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I l

TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W At least once per 7 days.

-M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 6 months.

R At least once per 18 months.

1 S/U Prior to each reactor startup.

N.A.

Not applicable.

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MILLSTONE - UNIT 2 1-9 Amendment No.104 l

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25 TABLE 4.3-7 q

F

!O ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

'4 E

Q l.

Pressurizer Water Level M

R ro 2.

Auxiliary Feedwater Flow Rate li R

3.

Reactor Coolant System Subcooling Margin Monitor M

R

)

4.

PORY Position Indicator (Acoustic Monitor)

M R

5.

PORY Block Valve Position Indicator N.A.

R R

6.

Safety Valve Position Indicator (Acoustic Monitor)

M R

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INSTRUMENTATION RADI0 ACTIVE LIQUID ~ EFFLUENT; MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION I,

3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels

~

shown in Table 3.3-12 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The setpoints shall be determined in accordance with methods and parameters as described in the ODCM.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the i

setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels operable requirement, take the ACTION shown in Table 3.3-12.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the'next Semiannual Effluent Report why the inoperability was not corrected in a timely manner. Releases need not be terminated after 30 days provided the specified actions are continued.

TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicabfe.

c.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by oerformance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CRANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

z=

MILLSTONE - UNIT 2 3/4 3-50 Amendment No.104 i

1

I' i

TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION FG ALARM U

MINIMUM #

SETPOINT 5

INSTRUMENT OPERABLE REQUIRED APPLICABILITY ACTION e

c 1.

Gross Radioactivity Monitors Providing 3

Automatic Tennination of Relea,se

a. Clean LiquM Radwaste Effluent Line 1

Yes 1

b. Aerated Liquid Radwaste Effluent Line 1

Yes 1

c. Steam Generator Blowdown Monitor or Condenser Air Ejector Monitor 1**

Yes-2 w

A

d. Condensate Polishing Facility Waste Neut Sump 1

Yes 1

w 2.

Gross Radioactivity Monitors Not Providing Automatic Tennination of Release

a. Reactor Building Closed Cooling g

Water Monitor #

1 Yes 3

a 3.

Flow Rate Measurements 5

'a. Clean Liquid Radwaste Effluent Line 1

No 4

2 P

b. Aerated Liquid Radwaste Effluent rn y

Lihe 1

No 4

c. Condensate Polishing Facility Waste Neut Sump Discharge Line 1

No 4

d. Dilution Water Flow

, No NA i

e. Steam Generator Blowdown Line No NA

I,I, i

TABLE 3.3-12 (Continued) y RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION N

[

Table Notes z

M

- At all times - which means that channels shall be OPERABLE and in service on a continuous, uninterrupted basis, e'x' cept that outages are permitted, within the time frame of the specified m

ACTION statement, for the purpose of maintenance and performance of required tests, checks and calibrations.

- - Although both monitors are normally operable, only one is necessary as the activity measured by each can be related to the other, and both monitors are capable of automatically isolating the steam generation blowdown.

- - - Modes 1-5 and Mode 6 when pathway is being used except that outages are permitted within the y

time frame of the specified ACTION statement for the purpose of maintenance and performance of g

required tests, checks and calibrations.

Since the only source of service water contamination is the reactor building closed cooling water, monitoring of the closed cooling water and conservative leakage assumptions will provide adequate control of service water effluents.

1. - The dilution water flow is determined by the use of condenser cooling water and service water k

pump status. Only those pumps actually discharging to the quarry at the time of release are g

included. Pump status is only reviewed for purposes of determining flows.

3

1. 1. - Detennined by the use of valve curves and/or make up water flow rates for the purpose of determining flows only.

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NA q Not applicable.

r'. r -

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TABLE 3.3-12 (Continued)

ACTION STATEMENTS ACTION 1: With the number of channels OPERABLE less than requfr'ed by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that best efforts are made to repair the instrument and that prior to initiating a release:

1.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1; and 2.

The original release rate calculations and discharge valving are independently verified by a second individual.

ACTION 2: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that activity (beta or gamma) grab samples are analyzed for gross radio ;

at a lower limit of detection of at least 3 x 10-/ uCf/ml; l.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is > ~ 0.01 uti/gm DOSE EQUIVALENT I-131.

2.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is 10.01 uCi/gm DOSE EQUIVALENT I-131.

ACTION 3: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months grab samples of the service water effluent are collected and analyzed for gross radio-activity (Ci/ml.

beta or gamma) at a lower limit of detection of at least 3 x 18-i u ACTION 4: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves may be used to estimate flow.

~

=

MILLSTONE - UNIT 2 3/4~3-53 Amendment No.104

TABLE 4.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

.b CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AUTOMATIC TERMINATION OF RELEASE a.

Clean Liquid Radwaste Effluent Line D*

P R(1)

Q(2) b.

Aerated Liquid Radwaste Effluent Line D*

P R(1)

Q(2) c.

Steam Generator Blowdown Monitor D*

M R(1)

Q(2) d.

Condenser Air Ejector Monitor D*

M R(3)

Q(2) e.

Condensate Polishing Facility -

Waste Neut-Sump D*

P R(1)

Q(2) 2.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.

Reactor Building Closed Cooling Water D*

M R(1)

Q(2) 3.

FLOWRATEMEASijREMENTDEVICES a.

Clean Liquid Radwaste Line D*

NA R

Q b.

Aerated Liquid Radwaste Line D*

NA R

Q c.

Condensate Polishing Facility -

Waste Neut Sump Line D*

NA R

Q d.

Dilution Water Flow D(4)

NA NA NA e.

Steam Generator Blowdown Line D(4)

NA NA==

NA MILLSTONE - UNIT 2 3/4 3-54 Amendment No.104

TABLE 4.3-12 (Continued)

TABLE NOTATIONS

-Duringreleasesviathispathwayandwhenthemonitoris$bquired OPERABLE per Table 3.3-12.

The CHANNEL CHECK should be done when the discharge is in progress.

NA - Not Applicable.

(1) - Calibration shall include the use of a known radioactive liquid or solid source whicii is traceable to an NBS source.

(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following exist:

a.

Instrument indicates measured levels above the alarm / trip setpoint.

b.

Instrument indicates a downscale or circuit failure.

Automatic isolation of the discharge stream shall also be demonstrated for this case for each monitor except the reactor building closed cooling water monitor.

For the condenser air ejector monitor it is the isolation of the steam generator blowdown that shall be demonstrated.

(3) - Calibration shall be performed using a known source whose strength is determined by a detector which has been calibrated to an NBS source.

The source shall be in a known reproducible geometry.

(4) - Pump or valve status, as appropriate, shall be checked daily'for the purposes of determining flow rates.

s

+

s_:.

MILLSTONE - UNIT 2 3/4 3-55 Amendment No.

104

,y-y

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INSTRUMENTATION RADI0 ACTIVE GASE0US EFFLUENT MONI.TORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION

.I 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The setpoints shall be determined in accordance with methods and parameters as described in the ODCM.

APPLICABILITY: As shown in-Table 3.3-13.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With the number of channels less than the minimum channels OPERABLE requirement, take the ACTION shown in Table 3.3-13.

Exert best efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Effluent Report why the inoperability was not corrected in a timely manner.

Releases need not be terminated after 30 days provided the specified actions are cordinued.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS s 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

MILLSTONE - UNIT 2 3/4 3-56 Amendment No. IO4 l

TABLE 3.3-13 RADIOACTIVE GASE0US-fFFLUENT INSTRUMENTATION MINIMUM ALARM E

CHANNELS SETPOINTS INSTRLl MENT OPERABLE REQUIRED APPLICABILITY ACTION 1.

MP2 STACK a.

Noble Gas Activity Monitor 1

Yes***

1 b.

Iodine Sampler 1

No 2

c.

Particulate Sampler 1

No 2

d.

Stack Flow Rate Monitor 1

No 3

e.

Sampler Flow Rate Monitor 1

No 3

2.

MP1 MAIN STACK a.

Noble Gas Activity Monitor 1

Yes***

5 b.

Iodine Sampler 1

No 2

c.

Particulate Sampler 1

No 2

-d.

Stack Flow Rate Monitor 1

No 3

e.

Sampler Flow Rate ar :

Monitor 1

No 3

3.

WASTE GAS HOLDUP SYSTEM -

N0BLE GAS MONITOR PROVIDING AUTOMATIC TERMINATION OF RELEASE 1

Yes 4

- During waste gas holdup system discharge.

- - At all times which means that chan'nels shall be OPERABLE and in service on a. continuous, uninterrupted basis, except that outages arm; permitted, a

within the time frame of the specified action statement, for the purpose of maintenance and performance of required tests, checks and calibrations.

- - - No automatic isolation features.

I MILLSTONE - UNIT 2 3/4 3-57 Amendment No. 104

TABLE 3.3-13 (Continued)

ACTION STATEMENTS l

ACTION 1: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that grab samples are taken once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 2: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment for periods of seven (7) days and analyzed for principle gamma emitters with half lives greater than 8 days within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION 3: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that the best efforts are made to repair the instrument and that the flow rate is estimated once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 4: With the number of channels OPERABLE less than required'by the Minimum Channels OPERABLE requirement:

Releases from the Millstone Unit 2 waste gas system may continue provided that best efforts are made to repair the instrument and that prior to initiating the release:

(a) At least two independent samples of the tank's contents are* analyzed; and (b) The original release rate. calculations and discharge valve lineups are independently verified by a second individual.

Otherwise, suspend releases from the waste gas holdup system.

ACTION 5: With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, Millstone Unit 2 releases via the Millstone Unit 1 stack may continue provided that best efforts are made to repair the instrument and that grab samples are taken once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ind these samples are analyzed for

, gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l '

MILLSTONE - UNIT 2 3/4 3-58 Amendment No.104

TABLE 4.3-13 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS r

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.

MP2 STACK

a. Noble Gas Activity Monitor D

M R(1)

Q(2)

b. Iodine S. ampler W

NA NA NA

c. Particulate Sampler W

NA NA NA

d. Stack Flow Rate Monitor D

NA R

Q-

e. Sampler Flow Rate Monitor D

NA R

NA.

2.

MP1 MAIN STACK 4

a. Noble Gas Activity Monitor D

M R(1)

Q(2)

b. Iodine Sampler W

NA NA NA

c. Particulate Sampler W

NA NA NA

d. Stack Flow Rate Monitor D

NA R

Q(2)

e. Sampler Flow Rate Monitor D

NA R

NA.

3.

WASTE GAS SYSTEM NOBLE GAS MONITOR D*

P R(1)

Q(2) o NA = Not Appricable.

- During releases via this pathway and when the monitor is required OPERABLE per Table 3.3-13.

The CHANNEL CHE K should be performed when the discharge is in progress.

MILLSTONE - UNIT 2 3/4 3-59 Amendment No.104

TABLE 4.3-13 (Continued)

..=

TABLE NOTATION l

(1) Calibration shall include the use of a known source whose strength is l

determined by a detector which has been calibrated to an NBS source.

These sources shall be in a known, reproducible geometry.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation

occurs if any of the following conditions exist:

a.

Instrument indicates measured levels above the alarm / trip setpoint.

I b.

Instrument indicates a downscale failure.

1 Also demonstrate automatic isolation for the waste gas system noble gas monitor.

B

=::

(

)

, =.

MILLSTONE - UNIT 2 3/4 3-60 Amendment No. 104 l'

we

,ne,

3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.1-1) shall not exceed the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.the concentration shall not exceed 2 x 10 jssolved or en For d pCi/ml total activity.

APPLICABILITY: At all times.

ACTION:

1 With the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits within 15 minutes.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Section I of the REM 0DCM.

~

4.11.1.1.2 The results of radioactive analysis shall be used in accordance with the methods of Section II of the REMODCM to assure that concentrations at the point of. release are maintained within the limits of Specification 3.11.1.1.

~

t Y

=

\\

l MILLSTONE - UNIT 2 3/4 11-1 Amendment No.104

\\

1 RADI0 ACTIVE EFFLUENTS

.t DOSE, LIQUIDS LIMITING CONDITION FOR OPERATION

[-

3.11.1.2 The dose or dose commitment to any REAL MEMBER OF THE PUBLIC from radioactive materials in liquid effluents from Unit 2 released from the site (see Figure 5.1-1) shall be limited:

I a.

During any calendar quarter to 1 1.5 mrem to the total body and to 1 5 mrem to any organ, and b.

During any calendar year to 13 mrem to the total body and to 1 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification i

6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents i

during the remainder of the current calendar quarter and during the remaindar of.the calendar year so that the cumulative dose or dose commitrent to any REAL MEMBER OF THE PUBLIC from such releases during the calendar year is within 3 mrem to the total body and 10 mrem to any organ.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

4 j

SURVEILLANCE REQUIREMENTS' 4.11.1[2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with.Section II of the REM 0DCM.

4.11.1.2.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the'REMODCM.

4 MILLSTONE - UNIT 2 3/4 11-2 Amendment No.104 O 9 a

l I

RADI0 ACTIVE EFFLUENTS l

[

3/4.11.2 GASE0US EFFLUENTS DOSE RATE 2

j I

I LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate, at any time, offsite (see Figure 5.1-1) due to radio-i active materials released in gaseous effluents from the site shall be limited

]

to the following values:

i a.

The dose rate limit for noble gases shall be < 500 mrem /yr to j

the total body and 1 3000 mrem /yrtotheskin7and b.

The dose rate limit due to inhalation for iodine-131, iodine-133, l

tritium and for all radioactive materials in particulate form j

with half lives greater than 8 days shall be 11500 mrem /yr to any organ.

APPLICABILITY: At all times, j

ACTION:

With the dose rate (s) exceeding the above limits, decrease the release rate i

within 15 minutes to comply with the limit (s) given in Specification 3.11.2.1.

j SURVEILLANCE REQUIREMENTS i

4.11.2.1.1 The release rate, at any time, of noble gases in gaseous efflu6nts l

shall be controlled by the offsite dose rate as established above in Specifi-I cation 3.11.2.1.

The corresponding release rate shall be detemined in i

l accordance with the methodology of Section II of the REMODCM.

l 4.11.2.1.2 The noble gas effluent monitors of Specification 3.3.3.10 shall.

be used to control release rates to limit offsite doses within the values 4

established in Specification 3.11.2.1.

i 4.11.2.1.3 The release rate of radioactive materials in gaseous effluents i

shall be detemined by obtaining representative samples and perfoming analyses in accordance with the sampling and analysis program, specified in Section I of the REMODCM. The corresponding dose rate shall be detemined using the methodology given in Section II of the REMODCM.

4, t

i 1

I MILLSTONE - UNIT 2 3/4 11-3 Amendment No.104

RADI0 ACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose offsite (see Figure 5.1-1) due to noble gases released from Unit 2 in gaseous effluents shall be limited to the following:

a.

During any calendar quarter, to 1 5 mrad for gamma radiation and 1 10 mrad for beta radiation; b.

During any calendar year, to 1 10 mrad for gamma radiation and 1 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicabJe.

SURVEILLANCE REQUIREMENTS

~

4.11.2.2.1 Dose Calculations. Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II of the REMODCM once every 31 days.

4.11.2.2.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I of the REMODCM.

6 MILLSTONE - UNIT 2 3/4 11-4 Amendment No. 104 O d l

RADI0 ACTIVE EFFLUENTS O

RT E kS LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to any REAL MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents from Unit 2 released offsite (see Figure 5.1-1) shall be limited to the following:

a.

During any calendar quarter to 1 7.5 mrem to any organ; b.

During any calendar year to 1 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radiciodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Consnission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumuiative dose or dose commitment to any REAL MEMBER OF THE

~

PUBLIC from such releases during the calendar year is within 15 mrem to any organ.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations. Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II of the REM 0DCM once every 31 days.

4.11.2.3.2 Relative accuracy or conservatism of the calculations shall be confirmed by perfomance of the Radiological Environmental Monitoring Program as detailed in Section I of the REM 0DCM.

C MILLSTONE - UNIT 2 3/4 11-5 Amendment No. 104

RADIOACTIVE EFFLUENTS 3/4.11.3 TOTAL DOSE r

LIMITING CONDITION FOR OPERATION 3.11.3 The dose or dose commitment to a REAL MEMBER OF THE PUBLIC from the Millstone Site is limited to 1 25 mrem to the total body or any organ (except the thyroid, which is limited to 1 75 mrem) over a period of 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2, 3.11.2.2, or 3.11.2.3, prepare and submit a Special Resort to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose connitment to any REAL MEMBER OF THE PUBLIC from the Millstone J

Site is limited to 125 mrem to the total body or any organ (except thyroid, which is limited to < 75 mrem) over 12 consecutive months.

This Special Report shall incTude an analysis which demonstrates that radiation exposures to any REAL MEMBER OF THE PUBLIC from the Millstone Site (including all effluent pathways and direct radia-tion) are less than the 40 CFR Part 190 Standard.

If the estimated doses exceed the above limits, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request and a variance is granted until staff action on the request is

=

complete.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

E SURVEILLANCE REQUIREMENTS 4.11.3 Dose Calculations. - Cumulative dose contributions from liquid and gaseous effluents and direct radiation from the Millstone Site shall be determined in Specifications 4.11.1.2.1, 4.11.2.2.1 and 4.11.2.3.1 and in accordance with Section II of the REM 0DCM once per 31 days.

I MILLSTONE - UNIT 2 3/4 11-6 Amendment No.

104 1

1

INSTRUMENTATION BASES 3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluerts during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. Monitoring of the turbine building sumps and condensate polishing facility floor drains is not required due to relatively low concentrations of radioactivity possible.

1 3/4.3.3.10 RADI0 ACTIVE GASE0US EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alann/ trip setpoints for these instruments shall be calculated in accordance with approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

There are a number of gaseous release points which could exhibit very low concentrations of radioactivity.

For all of these release paths, calculations prove that any dose consequences would be insignificant due to the inter-mittent nature of the release and/or the extremely low concentrations of radioactivity. -Since it is not cost-beneficial (nor in many cases practical due to the nature of the release (steam) or the impossibility of detecting,

such low levels), to monitor these pathways, it has been determined that these release paths require no monitoring nor sampling.

For example, these release paths include:

Turbine building ventilation, atmospheric steam dumps, steam generator safety valves, condensate surge tank vent, refueling water storage tank vent, warehouse #5 ventilation, steam generator blowdown steam vent, and Terry turbine exhaust.

MILLSTONE - UNIT 2 B 3/4 3-5 Amendment No.

104

3/4.11 RADI0 ACTIVE EFFLUENTS BASES L.

3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Table II. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Comission on Radiological Protection (ICRP) Publication 2.

3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A. III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation-implements the guides set forth in Section II.A.of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conform-ance with the guides of Appendix I is to be shown by calculational procedures based on modelstand data such that the actual exposure of an individual

=:

through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive material in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113 " Estimating Aquatic Dispersion.of Effluents from Accidental and Routine Reactor' Releases for the Purpose of Implementing Appendix I," April 1977.

C MILLSTONE - UNIT 2 B 3/4 11-1 Amendment No.104

1 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 DOSE RATE l

This specification is provided to ensure that the dose rate at anytime from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for all areas offsite. The annual dose limits j

are the doses associated with the concentrations of 10 CFR Part 20, Appendix l

B, Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual offsite to annual average concentrations exceeding the limits

+

specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. ' The.

]

specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to i 500 arem/ year to the total body or to < 3000 mrem / year to the skin. These release rate limits also restrict, at alt times, the 4

j corresponding-thyroid dose rate above background to an infant via the cow-milk-infant pathway to 1 1500 mrem / year for the nearest cow to the plant.

i l

3/4.11.2.2 DOSE, N0BLE GASES i

This specification is provided to implement the requirements of Sections t

II.B. III.A and IV.A of Appendix I,10.CFR Part 50. The Limiting Condition-for Operation implements the guides set forth in Section II.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the i

same time implement the guides set forth in Section IV.A of Appendix I to l

assure that the releases of radioactive material in gaseous effluents will be kept "as low as-is reasonably achievable." The Surveillance Requirements.

implement the requirements in Section III.A of Appendix I that conform with~

the guides of Appendix I to be shown by calculational procedures based on t

models and data such that the actual exposure of an individual through the i

appropriate pathways is unlikely to be substantially underestimated. The j

dose calculations established in the ODCM for calculating the doses due to i

the actual release rates of radioactive ~ noble gases in gaseous effluents will be consistent with.the methodology provided in Regulatory Guide 1.109,-

i

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

i Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases j

from Light-Water-Cooled-Reactors,"- Revision 1, July 1977.

~

The ODCM equations provided for determining the air doses at~the site boundary are based upon utilizing successively more realistic dose l'

calculational methodologies. More realistic dose calculational methods are l

MILLSTONE - UNIT 2 B 3/4 11-2 Amendment No.104 I

1 i

RADI0 ACTIVE EFFLUENTS BASES i

usedwheneversimplifiedcalculationsindicateadoseapproachIngasubstan-tial portion of the regulatory limits. The methods used, in order, are previously determined air dose per released activity ratio', historical meteorological data and actual radionuclide mix released, or real time meteorological and actual radionuclides released.

3/4.11.2.3 DOSE, RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN N0BLE GASES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I,10 CFR P. art 50. The Limiting Conditions for Operation are the guides set forth in Section II.C. of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I-to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods speci-fled in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I-be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be i

substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials will be consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. The release rate i

specifications for radioiodines, radioactive material in particulate form and

~

radionuclides other than noble gases are dependent on the existing radionuclide pathways to man.' The pathways which are examined in the development of these

,~

calculations are:

1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

~

ii.

MILLSTONE - UNIT 2 B 3/4 11-3 Amendment No. 104 l

I RADI0 ACTIVE EFFLUENTS BASES

.I[.

3/4.11.3 TOTAL DOSE This specification is provided to meet the reporting requirements of 40 CFR 190. For the purpose of the Special Report, it may be assumed that the dose commitment to any REAL MEMBER OF THE PUBLIC from other fuel cycle sources. is negligible, with the exception that dose contributions "from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered.

b i

~

s..:.

MILLSTONE - UNIT 2 B 3/4 11-4

.hnendment No.104 i

ADMINISTRATIVE CONTROLS 6.5.4 SITE NUCLEAR REVIEW BOARD (SNRB) b FUNCTION 6.5.4.1 The SNRB shall function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations b.

Administration c.

Chemistry and radiochemistry d.

Quality Assurance practices e.

Radiological safety COMPOSITION 6.5.4.2 The SNRB shall consist of no less than six, nor more than nine members including the individual Millstone NRB Chairman and the Station Superintendent. The Chainnan and members of the SNRS shall be appointed in writing by the Senior Vice President Nuclear Engineering and Operations, and shall have an academic degree in engineering or physical science field or hold a senior management position.

In addition, they shall have a minimum of five years technical experience, of which a minimum of three years shall be in their respective field of expertise.

I CONSULTANTS 6.5.4.3 Consultants shall be utilized as determined by the SNRB Chairman

,I to provide expert advice to the SNRB.

MEETING FREQUENCY 6.5.4.4 The SNRB shall meet at least once per calendar year.

l QUORUM 6.5.4.5 A quorum of SNRB shall consist of the Chairman or hisdesignated l

alternate and four SNRB members. No more than a minority of the quorum shall have line responsibility for operation of the Station.

i

l MILLSTONE - UNIT 2 6-13 Amendment No. 93

ADMINISTRATIVE CONTROLS REVIEW 6.5.4.6 The SNRB shall review:

i Proposed changes in Section 6.0 of these Technical Specifications a.

or Licenses comon to all units.

b.

Any indication of-an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components common to all units.

c.

Reports and meeting minutes of the SORC.

AUDITS 6.5.4.7 Audits of site activities shall be perfonned under the cognizance of the SNRB. These audits shall encompass:

The performance of activities required by the Quality Assurance a.

Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

b.

The Site Emergency Plan and implementing procedures at least once per 24 months.*

The Site Security Plan and implementing procedures at least once c.

per 24 months.*

d.

The Fire Protection Program and implementing procedures at least once per 24 months.

An inspection and audit of the fire protection and loss prevention e.

progrant shall be performed at least or.ce per 12 months by an outside firm experienced in fire protection and loss prevention.

f.

The performance of activities in accordance with the RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL at least once per 24 months.

g.

The performance of activities " required by the quality controls section of Regulatory Guides 1.21, Rev.1, June 1974 and 4.1, Rev.1, April 1975, at least once per 12 months.

Annual audits of the Emergency Plan and the Security Plan are also performed to satisfy the additional requirements of 10 CFR 50.54(t) and 10 CFR 73.40(d),

respectively. These annual audits may be used to satisfy the requirements contained in the Technical Specifications.

MILLSTONE - UNIT 2 6-14 Amendment No. 35,93, 104

ADMINISTRATIVE CONTROLS AUTHORITY

~

r 6.5.4.8 The SNRB reports to and advises the Senior Vice President Nuclear i

Engineering and Operations on those areas of responsibility specified in Sections 6.5.4.6 and 6.5.4.7.

Meeting minutes may be used for this purpose.

I RECORDS 6.5.4.9 Records of SNRB activities shall be prepared, approved, and I

distributed as indicated below:

a.

Minutes of each SNRB meeting shall be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following each meeting.

~

b.

Reports of reviews encompassed by Section 6.5.4.6 above shall I

be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.4.7 above shall be i

forwarded to the Senior Vice President Nuclear Engineering and Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The~following actions shall be taken for REPORTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuadt to the requirements of Specification 6.9.

a b.

Each REPORTABLE OCCURRENCE Report requiring 24-hour notification to the Commission shall be reviewed by the PORC and submitted to the NRB and the Vice President Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

< The Unit shall be placed in at least HOT STANDBY withia cne hour.

MILLSTONE - UNIT 2 6-15 Amendment No. JP, (5, pp, 75, 93

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) b.

TheNRCOperationsCentershallbenotifiedbytelephbeassoon as possible and in all cases within one hour. The Vice President Nuclear Operations and the NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice President Nuclear Operations within 14 days of the violations.

6.8 PROCEDURES

~

6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

The applicable procedures recomandad in Appendix "A" of Regulatory a.

Guide 1.33, February 1978.

b.

Refueling operations.

Surveillance activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Pr,otection Program implementation.

g.

Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev.1 June 1974.

h.

Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM) implementation except for Section I.E, Radiological Environmental Monitoring.

6.8.2 Each proceddre and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC/SORC, as applicable, and approved by the Unit Superintendent / Station Superintendent prior to implementation and reviewed periodically as set forth in each document.

MILLSTONE - UNIT 2 6-16 Amendment No. 28,35,45,78,92, 104 Wr

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be ma,de provided:

The intent of the original procedure is not altered. [.

a.

b.

The change is approved by two members of the plant management staff, at least one of-whom holds a Senior Reactor Operator's License on the unit affected.

c.

The change is documented, reviewed by the PORC/50RC, as applicable, and approved by the Unit Superintendent / Station Superintendent within 14 days of implementation.

6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.

6.8.5 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of 6.8.4 above shall be reviewed by an l

individual (other than the author) from the Radiological Assessment Branch -

l or the Production Operation Services Laboratory (POSL) and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original proce-i dure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, 4

within 14 days of implementation.

6.9 REPORTING REQUIREMENTS 1

ROUTINE REPORTS AND REPORTABLE OCCURRENCES I

i-6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to Regional Administrator, Region I, U.S. Nuclear Regulatory Comiss_fon, unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall besubmittedfollowing(1)receiptofanoperatinglicense,(2)amendmentto 4

the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and-(4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.

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i 6.9.1.2 The startup report shall address each of the tests identified in the~-

FSAR and-shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a compari-l son of these values with design predictions and specifications. Any addi-l tional specific details required in license conditions based on other comit-ments shall be iricluded in this report.

t MILLSTONE - UNIT 2 6-17 Amendment No. 79,28,35, 6,93, 104

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ADMINISTRATIVE CONTROLS l

6.9.1.3 Startup reports shall-be submitted within (1) 90 days f611owing completion of the startup test program, (2) 90 days following reiumption or commencement of commercial power operation, or (3) 9 months following l

initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS 1/

I 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 l

of each year. The initial report shall be submitted prior to March 1 of i

the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

l a.

A tabulation on an annual basis of the number of station, utility i

and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their a according to work and job functions,gociated man-rem exposure e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing and i

refualing. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD or film badge measure-ments. Small exposures totalling less than 20% of the individual total dose 'need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generator tube inservice inspec-i tions performed during the report period (reference Specifica-tion 4.4.5.5.b).

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1/

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are comon to all units i

at the station.

2/

This tabulation' supplements the requirements of 520.407 of 10 CFR Part 20.

l i

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MILLSTONE - UNIT 2 6-18 Amendment No. 36

ADMINISTRATIVE CONTROLS THIRTY-DAY WRITTEN REPORTS (Continued) r Information provided on the licensee event report form Miall be supple-i form.

mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a.

Reactor protection system or engineered safety features instrument settings wilich are found to be less conservative than those estab-lished by the technica.1 specifications but which do not prevent'the fulfillment of the functional requirements of affected systems.

b.

Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a l

limiting condition for operation.

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of:

redundancy provided in reactor protection systems or engineered safety features systems.

d.

Abnormal degradation of systems other than those specified in j

6.9.1.8.c, above, designed to contain radioactive material resulting from the fission process.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1

6.9.1'.10 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

The Annual Radiological Environmental Operating Reports shall include that information delineated in the REM 0DCM.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.11 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted l

within 60 days after January 1 and July 1 of each year.

A supplemental report containing dose assessments for the previous year shall be submitted annually within 90 days of January 1.

The report shall include that informa, tion delineated in the REMODCM.

Any changes to the REM 0DCM shall be submitted in the Seniannual. Radioactive Effluent Release Report.

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MILLSTONE - UNIT 2 6-21 Amendment No.7%,52 p3, 104

ADMINISTRATIVE CONTROLS SPECIAL REPORTS

.I[.

6.9.2 Special reports shall be submitted to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

b.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

c.

Safety Class 1 Inservice Inspection Program Review, Specification 4.4.10.1.

d.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

e.

Fire Detection Instrumentati:n, Specification 3.3.3.7.

f.

Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.

g.

RCS Overpressure Mitigation, Specification 3.4.9.3.

h.

Radiological Effluent Reports required by Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3 and 3.11.4.

s MILLSTONE - UNIT 2 6-22 Amendment No. 36,59,73, 104 l

ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTI0ft 6.10.1 The following records shall be retained for at least five~ years:

a.

Records and logs of facility operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

I c.

All REPORTABLE OCCURRENCES submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e.

Records of reactor tests and experiments.

f.

Records of changes made to operating procedures.

g.

Records of radioactive shipments.

h.

Records of sealed source leak tests and results.

1.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the facility operating license:

a.

Records and drawing changes reflecting facility design modifica-tions made to systems and equipment described in the Final Safety hnalysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of facility radiation and contamination surveys.

d.

Records of radiation exposure 'for all individuals entering radiation control areas, e.

Records of gaseous and liquip radioactive material released to the environs.

~~

f.

Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

MILLSTONE - UNIT 2 6-23 Amendment No. J. /)7,104 l

ADMINISTRATIVE CONTROLS g.

Records of training and qualification for current members of the plant staff.

._e h.

Records of inservice inspections performed pursuant to these Technical Specifications,

i. Records of quality assurance activities required by the QA Manual.

J.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR Part 50.59.

k.

Records of meetings of the PORC, the NRB, the SORC and the SNRB.

1.

Records of Environmental Qualification, 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted to enter such areas shall be provided with or

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accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowl--

edgeable of them.

Health Physics personnel or personnel escorted by Health PhysiN per-sonnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided l

they comply with approved radiation protection procedures for entry into high radiation areas.

MILLSTONE - UNIT 2 6-24

fMg9tg187$9t p//8//}?$

l

/

Amendment No. MA,104

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ADMINISTRATIVE CONTROLS c.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device., This individual shall be responsible for providing positife control over the activities within the area and shall perfom periodic radiation surveillance at the frequency specified in the Radiation Work Permit. The surveillance frequency shall be established by the Health Physics Supervisor.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 4

1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control-of the Shift Supervisor on duty and/or the Health Physics Supervisor.

6.13 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

1.

Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.

Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

6.14 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1.

Training of personnel, 2.

Procedure:; for monitoring, and 3.

Provisions'for maintenance of sampling and analysis equipment.

as:

MILLSTONE - UNIT 2 6-25 pfddf difdd Jp/N/pp, l

Amendment No. $$. /WI,104

1 i

ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (BEM0DCM) t

4. -

Section I, Radiological Effluents Monitoring Manual, shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation.

It shall also specify operating guidelines for radio-Octive waste treatment systems and report content.

Changes to Section I shall be submitted to the Commission for approval prior to implementation.

Section II, the Offsite Dose Calculation Manual (0DCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints-consistent with the applicable LCOs contained in these technical specifica-tions. Changes to Section II need not be submitted to the Commission for approval prior to implementation, but shall be included in the next Semi-Annual Radioactive Effluent Release Report.

6.16 RADI0 ACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the unit shall be prepared, approved, naintained and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REM 0DCM.

The Solid Radioactive Waste Treatment System shall be operated in accordance withzthe Process Control Program to process wet radioactive 7J wastes to meet shipping and burial ground requirements.

MILLSTONE - UNIT 2 6-26 Amendment No.104

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,e--

,

v t e Letter Sequence Other
TAC:49588, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval, Approval Other: B11575, Forwards Rev 1 to Radiological Effluent Monitoring & Offsite Dose Calculation Manual. Process Control Program Also Encl.Info Responds to Unit 3 SER Confirmatory Items 59 & 60, B11645, Forwards Revs to Pages B-1,C-2,C-3 & E-9 of Radiological Effluent Monitoring Manual to Incorporate Comments Made During Review, ML20023A493, ML20023B695, ML20125D427, ML20128K691, ML20132A841, ML20132A855
MONTHYEAR1985-06-19 [Table View]

ML20132A841

Text

Attachment:

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