Text

Forwards Westinghouse,C-E & B&W Owners Groups Draft Use & Application Chapters of Proposed New STS
	ML20206L588
Person / Time
Issue date:	11/23/1988
From:	Rossi C; Office of Nuclear Reactor Regulation
To:	Holahan G, Shao L, Varga S; Office of Nuclear Reactor Regulation
Shared Package
ML20206L595	List: ML20206L588;
References
	NUDOCS 8811300101
	Download: ML20206L588 (31)
	v • d • e

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# 'o UNITED $TATES [

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.8 o NUCLEAR REGULATORY COMMISSION

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MEMORANDUM FOR: ' Steven A. Varga. Director Division of Reactor Projects - 1/11. NRR r Gary M. Holahan. Acting Director Division of Reactor Frojects 111. IV. V i and Special Projects. NRR t Lawrence Shao. Director Division of Engineering and Systems Technology. NRR ,

1 Brian K. Grimes. Director Division of Reactor inspection and Safeguards. NRR Frank J. Congel. Director Division of Radiation Protection and Emergency i Preparedness. NRR Jack W. Roe. Director Division of Licensee Performance and Quality Evaluation. NRR

! FROM: Charles F., Rossi. Director Division of Oparational Events Assessment, hRR

SUBJECT:

REVIEW 0F NEW STANDARD TEL.,NICAL SPECIFICATIONS (STS)

The PWR owners groups (WOG. CEOG. B&WOG) have submitted, as cart of the Technical

! Specifications Improvevent Program (TSIP). draf t copies of their respective Use and Application Chapters of the propoteo new STS (Enclosure 1. 2 and 3).

j CONTACT: Millard Wohl x21181 I

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l 49 P' Ten gbmst PDC

Multiple M dressees ;

Please review the enclosed Use and Application Chapters and provide .orcents to OTSB by Decerber 22, 1988. Several other chapter submittals are tc, .Jilow.

Enclosure 4 is a matrix to correlate review responsibility with each of the owners groups draft chapters. ,

~

Charles L Charles E. Rossi Director Division of Operational Events Assessment, hRR

Enclosures:

As stated cc w/ enclosure

L. Engle t

D. Hickman I

H. Silver L. Crncker L. Kintner DISTRIBUTION: w/o enclosure DTIE R/F 00EA R/F TEMurley Central Files CERossi EJButcher, RI

JHSniezek CHBerlinger FJtiiraglia WDLanning i DMCrutchfield WKennedy

JGPartlow Regional Administrators

JLieberman OTSB Members SDRichardson PDR OCFischer itWohl

( FHReinhart i

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TSS 00EA:NRR k

C:TS-:00EA:NRR MLWoh Y)tR DCFischer EJButcher E os i

, 11/t3/88 11/Z'/88 11/13/88 11/%988 l

Multiple Addressees Please review the enclosed Use and Application Chapters and provide coments to OTSB by December 22. 1988. Several other chapter submittals are to follow.

Enclosure 4 is a matrix to correlatu Jeview responsibility with each of the owners groups draft chapters-s'uv L%f k+nt Charles E. Rossi Director Division of Operational Events Assessment. NRR

Enclosures:

As stated cc w/ enclosure

L. Engle

! 0. Hickman H. Silver L. Crocker j L. Kintrer 1

Eutrum 1

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). The Front Matter, consisting of Prefaca, Table of Contents. List of Tables.

List of Figures, and List of Effective Pages is not considered a part of technical specifications. As such, the page footer contains the word Revision instead of Amenda nt with a revision date. It is the intent to allow the Licensee to change these sections without a license amendment. l

2. Vertical bars have been placed in the right margin of the Definition Section to identify changes from the Comanche Peak "Desk Version". Some r changes are just a new arrangement and some are significant.

3. The list of tables, figures, and the Table of Contents is submitted only to demon drate their locktion and the page format. As the actual writin l the specifica*,1ons continues, these sections are expected to change. g !

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4. The pages of this document have been stamped DEAEI to indicate that this chapter is still subject to change. The final version will be submitted i with the Owners Group Topical Report. i l

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. . PREFACE i i f

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Technical Specifications are explicit restrict on a I

( comercial nuclear power plant. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the )

required conditions bounded by the analysis, and with the operable equipment '

that is assumed to mitigate the consequences of an accident. Technical Specifications preserve the primary success path relied upon to detect and respond to accidents. They also complement the concept of defense in depth.

Section 182a of the Atomic Energy Act of 1954, as amended (the Act), 47 U.S.C.

2011, at 2232, provides the legislative framework within which technical specifications are required. Section 182a of the Act requires in pertinent part:

"In connection with application for Itcenses to operate production or utilization facilities. the applicant shall state such technical specifications, including information on the amount, kind, and source of s)ecial nuclear material required, the place of use, the specific ciaracteristics of the facility, and such other information as the Comission may, by rule or regulation, deem necessary in order to enable it to find that the utilization or production of special nuclear material will

...srovide adequate protection to the health and safety of the public.

Suci technical specificatiens shall be a part of any license issued."

The regulatory framework implementing Section 182a of the Act is the NRC's regulation Title 10 Code of Federal Regulations Part 50, Section 50.36,

. "Technical Specifications". This regulation provides in part that each operating license:

"will include technical specifications...(to) be derived from the analysis and evaluation included in the safety analysis report, and amendments thereto...and may also include such additional technical specifications as the Comission finds appropriate.'

The Comission has issued an interim "Proposed Policy Statement on Technical Specification Improvements for Nuclear Power Reactors," 52 FR 3788. February 6,

! 1987. This Interim Polley Statement sets out specific criteria for the i

content of technical specifications. The interim policy statement specifically l recognizes that:

l "The purpose of Technical Specifications is to impose conditions or ,

limitations upon reactor operation necessary to obviate the soseibility of an abnormal situation or event giving rise to an imediate tireat to the public health and safety by establishing those conditions of operation which cannot be changed without prior Comission approval and by identifying those features which are of controlling importance to safety."

This set of Restructured Technical Specifications establish these conditions and limitations for the Westinghouse Owner's Group. These specifications are intended to be used to develop improved plant specific sets of technical specifications.

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( TABLE OF C0NTENTS.............................................

LIST OF TABLES............................. ..................

LIST OF FIGURES...............................................

LIST OF EFFECTIVE PAGES........................... ...........

1.0 USE AND APPLICAT10ti 1.1 D E F I N I T ! 0,*4 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1.2 LOGICAL CONNECTORS............................................

1.3 COMPLETION TIMES..............................................

1.4 LEGAL CONSIDERATIONS..........................................

2.0 SAFETY LIMITS 2.1 REACTod CORE SAFETY LIMITS....................................

3.0 tiMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS.................................

3.0 APPLICABILITY.................................................

. 3.1 REACT 0R.......................................................

3.1.1 Shutdown Margin........................................

3.1.2 Moderator Temperature Coefficient......................

I 3.1.3 Rod Group Alignment Limits.............................

.. 3.1.4 Shutdown Rod Insertion L1mit...........................

3.1. 5 Cont rol Rod In s erti on L1mi t s . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.1.6 Heat Flux Hot Channel Factor...........................

3.1.7 Enthalpy Rise Hot Channel Factor.......................

3.1.8 Axial Flux Difference..................................

3.1.9 Quadrant Power Tilt Ratio..............................

3.1.10 Core Reactivity........................................

3.1.11 Mode 1 Physics Tests Exceptions........................

3.1.12 Mode 2 Physics Tests Exceptions........................

3.2 INSTRUNENTATION...............................................

3.2.1 Reactor Protection System..............................

3.2.2 Engineered Safety Feature Actuation System.............

3.2.3 Radiation Monitoring...................................

3.2.4 Accident Monitoring Instrumentation....................

3.2.5 Remote Shutdown Instrumentation........................

3.2.6 RCS Leakage Detection Instrumentation..................

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3.3 REACTOR COOLANT SYSTEM................. J . .;.J....

3.3.1 RCS Loops - MODES 1 And 2..............................

3.3.2 RCS Loops - MODE 3.....................................

3.3.3 R C S L o o p s - MOD E 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.3.4 RCS Loops - MODE 5 Loops F111ed........................

3.3.5 RCS Loops - MODE 5 Loops Not F111ed....................

3.3.6 RCS In lated Loop (0ptional)...........................

3.3.7 RCC T w14ted Loop Startup (0ptional) . . . . . . . . . . . . . . . . . . .

3.3.8 Pressurtzer............................................

3.3.9 RCS Sa f>ty Val ve s Operating. . . . . . . . . . . . . . . . . . . . . . . . . . . .

3 . 3.10 Rel i e f V a 1 v e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.3.11 RCS Oparational Lenkage. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.s.12 RCS Specific Activity............................. ....

3.3.13 RCS Pressure / Temperature Limits........................

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

3.3.15 Special Test Exceptions Reactor Coolant Loops... ......

3.4 EMERGENCY CORE COOLING SYSTEMS................................

3.4.1 Ac c umul a t o r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.4.2 ECCS Su'asystems - TAVE Greater Than or E q u a l To 3 5 0 F . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.4.3 ECCS Subsystems TAVE Less Than 350 F.................

3.4.4 Boron Injection 1ank...................................

3.4.5 Refueling Water Storage Tank........................... i

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3.5 CONTAINMENT SYSTEhS...........................................

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3.5.1 Containment Integrity..................................

3.5.2 Containment Air Locks..................................

3.5.3 Containment Isolation Valve And Channel Weld PressurizationSystems(0ptional)......................

3.5.4 Internal Pressure...................................... l 3.5.5 Air Temperature........................................

3.5.6 Containment Ventilation Systes......................... 1 3.5.7 Containment Spray System...............................

3.5.8 Spray Addi tive System (0ptional ) . . . . . . . . . . . . . . . . . . . . . . . l 3.5.9 Containment f ooling System (0ptional) . . . . . . . . . . . . . . . . . . ;

3.5.10 Iodine Clean 9 Sys t 64 (@ ti onal ) . . . . . . . . . . . . . . . . . . . . . . . '

3. 5.11 Containment l'. al ation Va1ve s. . . . . . . . . . . . . . . . . . . . . . . . . . .

< 3. 5.12 Hy d rogen Moni t or s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.5.13 Electric Hydrogen Recombiners..........................

3.5.14 Combustible Gas Control - Hydrogen Mixing System

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3.5.1 Containment Integrity..................................

3.5.2 Containment Air Locks.................................. .

3.5.3 Containment Isolation Valve And Channel Weld Pressurization Systems (0ptional) . . . . . . . . . . . . . . . . . . . . . .

3.5.4 I n t e rn al Pre s s u re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.5.5 Air Temperature........................................

3.5.6 Shield Building Air Cleanup System.....................

3.5.7 Containment Vantilation System.........................

3.5.8 Containment Spray System...............................

3.5.9 Spray Additive System (0ptional).......................

3. 5.10 Containment Cooling System (0ptional) . . . . . . . . . . . . . . . . . .

3.5.11 lodine Cl e anup System (0ptional) . . . . . . . . . . . . . . . . . . . . . . .

3.5.12 Containment Isolation Va1ves...........................

3.5.13 Hydrogen Monitors......................................

3.5.14 Electric Hydrogen Recombiners..........................

3.5.15 Hydrogen Control Distributed Ignition System...........

3. 5.16 Hydrogen Mixing System (0ptional) . . . . . . . . . . . . . . . . . . . . . .

3.5.17 Ice Bed................................................

3.5.18 Ice Condenser Door 4....................................

3.5.19 Divider Barrier Personnel Access Doors And Equipment Hatches..................................

3.5.20 Containment Air Recirculation Systems......,........... O 3.5.21 Floor Drains...........................................

3.5. 2 2 Re fueling Canal Drai n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

C"r 3.5.23 D.vider Barrier Sea 1...................................

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3.5 CONTAINMENT 5VSTEMS...........................................

3.5.1 Containment Integrity..................................

3.5.2 Containeent Air 1.ocks..................................

3.5.3 Containment Isolation Valve And Channel Weld Pressurization Systems (0ptional)......................

3.5.4 Internal Pressure......................................

3.5.5 Air Temperature........................................

3.5.6 Contai nment Ventil ation 5ystem. . . . . . . . . . . . . . . . . . . . . . . . .

3.5.7 Containment Quen:h 3 pray 5ystem........................

3.5.8 Recirculation Spray 5ystem.............................

3.5.9 5 pray Additive System (0ptional).......................

3.5.10 Containment Isolation Vt1ves...........................

3.5.11 Hydrogen Monitors......................................

3.5.12 Electric Hydrogen Recombiners..........................

3.5.13 Combustible Gas Control - Hydrogen Mixing System (0ptional).............................................

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, 3.5 CONTAINMENTSYSTEMS..................c;f.N..M.t. ..

3.5.1 Containment Integrity..................................

3.5.2 Containment Air '.ocks..................................

3.5.3 Containment Isolation Valve And Channel Weld PressurizationSyrtems(0ptional)......................

3.5.4 I nt e rn al Pre s s u re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.5.5 Air Temperature........................................

3.5.6 Containment Ventilation System.........................

3.5.7 Containment Spray System...............................

3.5.3 Spray Additive Syste.n (0pt ional) . . . . . . . . . . . . . . . . . . . . . . .

3.5.9 Containment Cooling System (0ptional)..................

3. 5.10 lodine Cleanup System (0ptional) . . . . . . . . . . . . . . . . . . . . . . .

3.5.11 Conta t eent Isol ation Va1ves. . . . . . . . . . . . . . . . . . . . . . . . . . .

3.5.12 Hydrogen Monitors......................................

3.5.13 Electric Hydrogen Recombiners..........................

3.5.14 Combustible Gas Control - Hydrogen Mixing System (0ptional).............................................

3.5.15 shield Building Air Cleanup System.....................

3.5.16 Shield Building Integrity..............................

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Afd SYSTEMS....................

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3.6 PLANT .. .. .

3.6.1 Main Steam Safety Va1ves...............................

3.6.2 Main Steam Line Isolation Va1ves.......................

3.6.3 Auxiliary Feedwater System.............................

3.6.4 Condensate Storage Tank................................

3.6.5 Secondary Specific Activity............................

3.6.6 Component Cooling Water System.........................

3.6.7 Service Water System...................................

3.6.8 Ultimate Heat Sink.....................................

3.6.9 Control Room Emergency Air Cleanup System. . . . . . . . . . . . . .

3.6.10 ECCS Pump Room Exhaust Air Cleanup System..............

3.6.11 Water Level Storage Poo1...............................

3. 6.12 Storage Pool Air Cl eanup System. . . . . . . . . . . . . . . . . . . . . . . .

3.7 ELECTRICAL SYSTEMS............................................

3.7.1 AC Sources - Operating.................................

3.7.2 AC Sources - Shutdown..................................

3.7.3 DC Sources - 0)erating.................................

3.7.4 DC Sources - $1utdown..................................

3.7.5 Onsite Power Distribution 0)erating..................

3.7.6 Onsite Power Distribution 51utdown...................

3.8 REFUELING OPERAT10NS..........................................

3.8.1 Boron Concentration....................................

" 3.8.2 Instrumentation........................................

3.8.3 Decay Time.............................................

3.8.4 Containment Building Penetrations (Includes Containment Purge And Exhaust Isolation System)........

3.8.5 Residual Heat Removal And Coolant Circulation -

High Water Leve1.......................................

3.8.6 Residual Heat Removal And Coolar,t Circulation -

low Water level........................................

3.8.7 Water Level - Reactor Yesse1...........................

4.0 DESIGN FEATURES 4.1 CONTAINMENT...................................................

4.2 REACTORC0RE..................................................

4.3 REACTOR COOLANT SYSTEM........................................

4.4 FUEL ST0 RAGE..................................................

t 5.0 ADMINISTRATIVE CONTROLS 5.1 RESPONSIBILITY................................................

5.2 ORGANIZATION..................................................

5.2.1 Offsite......... ...................................

, 5.2.2 Unit Staff.............................................

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5.3 UNIT STAFF QUALIFICAT!0Nh.....................................

5.4 TRAINING......................................................

5.5 REVIEW AND AUDIT..............................................

5.6 REPORTABLE EVENT ACT!0N.......................................

5.7 SAFETY LIMIT VIOLAT!0N........................................

5.8 PROCEDURE 5 AND PR0 GRAMS.......................................

5.8.1 Establishment, Implementation, and Maintenance.........

5.8.2 Review and Approva1....................................

5.8.3 Temporary Changes......................................

5.8.4 Primary Coolant Sources outside Containment............

5.8.5 In Plant R2diation Monitoring..........................

5.8.6 Secondary Water Chemistry..............................

5.8.7 Backup Me,thod for Determining Subcooling Margin........

5.8.8 Post Accident S ampl ing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

5.8.9 Radiation Protection Program...........................

5.8.3 0 Proce s s Control Program PCP)..........................

(Manual (00CM) . . . . . . . . . . . . . . . . .

5.8.11 Offsite Dose Calculation 5.8.12 Major Changes to Radioactive Waste Treatment Systems...

5.9 REPORTING REQUIREMENTS........................................

5.9.1 Routine Reports........................................ (

5.9.2 Startup R yorts........................................

0 5.9.3 An n u al Re p o r t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

5.9.4 Semiannual Reports.....................................

5.9.5 Monthly Operating Reports..............................

5.9.6 S p e c i al Re p o r t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

5.9.7 Core Operating Limits Report ................

5.10 RECORD RETENTION 5.10.1 5 Year Records.........................................

5.10.2 Duration af Unit Records...............................

5.10.3 Ouality As surance Activities Records. . . . . . . . . . . . . . . . . . .

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

1-2 Operational Modes.....................................

3.1-1 DN8 Parameters........................................

3.1 2 Accident Analysis Requiring Re Evaluation In The Event of An Inoperabl e Full Length Rod. . . . . . . . . . . . . . . . . . . . . .

3.2.1 1 Reactor Trip System Instrumentation...................

3.2.2 1 Engineered Safety Features Actuation System...........

3.2.3 1 Radiation Konitoring Actuation........................

3.2.4 1 Accident Monitoring Instrumentation...................

3.2.5 1 Remote Shutdown Monitoring Instrumentation............

. 3.2.6-1 Leak Detection Instrumentation........................

3.3 1 Reactor Coolant System Pressure Isolation Valves......

3.3 2 Reactor Coolant Specific Activity Sample And Analysis Frogram...............................................

3.51 Cont ainment I s ol ation Va1 ve s. . . . . . . . . . . . . . . . . . . . . . . . . .

3.6 1 Maximum A11ovable Power Range Neutron Flux High Setpoint With Inoperable Steam Line Safety Valves.....

3.6-2 Steam Line Safety Valves Per Loop.....................

3.6.3 Secondary Coolant System Specific Activity Sample a nd An al y s i s Prog ram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.7-1 Diesel Generator Test Schedule........................

3.7 2 Battery Surve ill ance Requi rement s . . . . . . . . . . . . . . . . . . . . .

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2.1 1 Reactor Core Safety L1mit...........................

3.1-1 Axial Flux Difference Limits As A Function of Rated T h e rmal Powe r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.1-2 Rod Bank Insertion Limits Vs. Thermal Power........

3.3-1 Dose Equivlient 1131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power With The Reactor Coolant specific Activity

>I microcurle/ gram Dose Equivilent 1-131...........

3.4 1 Maximum Allowable Primary Containment Air Pressure Versus River Water Temperature and RWST Water Temperature (Subatmospieric Type Containment)......

3.4 2 Minimum Allowable Primary Containment Average Air Temperature Versus River Water Temperature (SubatrosphericTypeContainment)..................

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f]L 1.1 DEFINIT 10llS jf'

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....................................... NOTE....................................

The defined *.orsas of this section appear in capitalized type and are applicable throt,ghout thasa Technical Sp2cifications and Bases Igmg Definition ACTIONS ACTIONS shall be that part of a Technical Specification which prescribes Required Actions under designated Conditions which shall be completed within specified Completion Times.

ACTUATION LOGIC An ACTUATION LOGIC TEST shall be the application of TEST various simulated input combinations in conjunction with each possible interlock Ic ic state and verification of the required lo ic output. The ACTUATION LOGIC TEST shall inc1 de a continuity check of output devices, as a minimum.

ANALOG CHANNEL An ANALOG CHANNEL OPERAT!0 MAL TEST shall be ti e OPERATIONAL TEST injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alam, interlock and/or trip functions.

The ANAL.0G CHANNEL OPERATIONAL TEST shall include l

. adjustments, as necessary, of the alars, interlock and/or trip setpoints such that t.i setpoints are within the required range and accuracy.

AX1AL FLUi AXIAL FLUX DIFFERENCE shall be the difference in DIFFERENCE normalized flux signals between the top and bottom halves of a (two) section txcore neutron detector.

CHANNEL A CHANNEL CAI.!BRATION shall be the adjustment, as CALIBRATION necessary, of the channel such that it responds within the required range and accuracy to known input. The CHANNEL CAllBRATION shall encompass the en'. ire channel including the sensor and alams, interloct and/or trip :

functions. It may be performed by any series of i sequential, overlapping calibrations, or total channel steps such that the entire channel is calibrated.

1 I CHANNEL CHECK A CHANNEL CHECK shell be the. qualitative asu .rment of channel behavior during cperation by observation. This detemination shall include, where possible, comparison of the chantiel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

l (continued)

(

Unit Name 11 Amendment Draft 10/1/88 ,

WOG l

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r 1 ! ( u, Definitions

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1.1

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1.1 DEFINITIONS (continued) .

(. .

CONTAINMENT CONTAINMENT INTEGRITY shall exist when:

INTEGRITY

a. All penetrations required to be closed during accident conditions are either:

1. Capable of being closed by an 0PERABLE containment automatic isolation system, or

2. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in LC0

[ ).

b. All equipment hatches are closed and sealed,

c. Each air lock is OPERABLE pursuant to LC0

(_ ],

d. The containment leakage rates are within the

. limits of LCO [ ._ ) .

e. The o nling mechantsu associated with each penetri, tion (e.g., welds, bellows or 0 rings) is OPERABLE, CONTROLLED. LEAKAGE See LEAKAGr. CONT M. LED.

CORE ALTERATION CORE ALT! RATION sh011 be the movement or manipulation of any fuel, sources or reactivity control components within the reactor pressuro vessel, with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe conservative posit. ion.

CORE OPERATING The CORE OPERATING LINIis MPORT is the unit specific LIMITS REPORT document that provides core operating limits for the current operating reload cy4 e. These cycle specific core operating Ilmits shall W determined for each reload cycle 'n accordance with specificatica 5.9.7.

Plant operation within these operating Italts is addressed in individual spectftcations.

DIGITAL CHANNEL A DIGITAL CHANNEL OPERATIONAL TEST shall consist of OPERATIONAL TES1 injecting simulated process data where available or exercising the digital computer hardware using database manipulation to verify OPERA 81LITY of alam, interlock and/or trip function..

o (continued)

( Unit Name )*2 Amendunt Oraft 10/1/88 WOG

Definitions Q

m 1.1 DEFINITIONS (continued) J-m. w - .

DOSE EQUIVALENT I 131 DOSE EQUIVALENT I-131 shall be that concentration of I 131 (microcuries/ gram) which alone would roduce the same thyroid dose as the quantity and isoto ic atxture of I-131, ! 132,1 133,1-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those 11ste1 in Table !!! of TID 14844, ' Calculation of Distance Factors for Power snd fest Reactor $1tes".

Y AVERAGE E shall be the average (weighted in proportion to the DISINTIGRATION con'.:entration of each radionuclide in tie sample) of ENERGY the sum of the average beta and gama energies per disintegration in MeV) for isotopes, other than todinks, with h if lives greater than 15 winutes, making up at least 95% of the total non iodine activity in the coolant.

ENGINEERED SAFETY The ENGINEERED SAFETY FEATURE RESPONSE TIME FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensoi until the ESF equipment is capable of perfor1ning its safety function (i.e., the valves travel to their required posittens, pump discharge pressures reachtheirrequiredvalues,etc.). Times shall include diesel generator starting and sequance loading (

delays where applicable. The response time may be measured by any se:tes of overlapping or total steps such that the entire re:ponse time is measured.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1 1.

IDENTIFIED LEAKAGE See LEAKAGE-IDENTIFIED.

LEAKAGE-CONTROLLED CONTROLLED LEAXAGE shall be the seal water flow supplied to the reactor coolant pump seals.

LEAKAGE-!DENTIFIED IDENTIFIED LEAXAGE shall bet

a. Leakage (except CONTROLLED LEAKAGE) into closed syste:as, such as pump seal or valve packing leaks that are captured and conducted to a sump or collta. ting tank, or

b. Leakage into the containment atmosphere from

' sources that are both specifica11 located and known either not to interfe.e wit the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or Unit Name 13 Amendment Draft 10/1/88 WOG

. m__ _ __,__m,_.s_ _ _ _ ___m _

Q, .(

' a Definitions

} ,

1.1 1.1 DEFINITIONS (continued) O _ . _ _

LEAKAGE IDENTIFIED c. Reactor Coolant System leakage through a steam (continued) generator to the secondary system.

LEAKAGE PRESSURE PRESSURE 80VNCARY LEAKAGE shall be leakage (except i BOUNDARY steamgeneratortubeleakage)throughanonisolable fault ,n a Reactor Coolant System component body, pipe wall or vessel wall.

LEAKAGE UNIDENTIFIED UNIDENTIFl[D LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

MASTER RELAY TEST A MASTER RELAY TIST shall be the enargization of each master relay and verification of OPERA 81LITY of each relay. The MASTER RELAY TEST shall include a .

continuity check of each associated slave relay. !

MEMBER ($) 0F THE MEMBER (5) 0F THE PUBLIC shall include all people PUBLIC not occupationally associated with the plant. This

category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does i include ersons wh!, use porttias of the site for i recreati nal, occupational, or other purposes not

associated with the plant.

MODE A N00F shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in

! Table 1 2.

OFFSITE DOSE The OFFSITE DOSE CALCULATION MANUAL (00CM) shall i CALCULATION MANUAL contain the methodology and parameters used in the i l

calculation of offstte doses due to radioactive gaseous i and liquid effluents, in the calculation of gaseous and l

liquid effluent monitoring Alarm / Trip setpoints, and in

' the conduct of the Environmental Radiological Monitoring Program.

I OPERABLE OPERABILITY A systes, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls,

! electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that (continued) o

( Unit Name 14 Amendment Draft 10/1/86 WOG l

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OPERA 8LE 0PERABILITY are required for the system, subsystem, train, (continued) component or device to perform its function (s) are also capable of performing their related support function (s).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure '

the fundamental nuclear characteristics of the reactor i core hnd related instrumentation. These tests are 1) of the FSAR, 2) authorized described in Chapterof(14.0)CFR under the provisions 10 50.5g, or 3) otherwise ,

approved by the Commission.

4 PRES 5URE BOUNDARY 5ee LEAKAGE PRES 5URE SOUNDARY. l LEAKAGE PROCESS CONTROL The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and l PROGRAM

' determinations to be made to ensure that processing and packaging of solid radioactive wastes based on

] demonstrated processing of actual or simulated wet t solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirement *, ard other requirements governing the h PURGE-PURGING disposal of radtoactive maste.

PURGE or PURGlNG shall be any controlled process of C

i discharging air or gas from a confinement to maintain

! temperature, pressure, humidity, concentration or other

! operating conditions, in such a manner that replacement 3

air or gas is required to purify the confinement.

1

)

QUADRANT POWER TILT RATIO QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calit' rated output to the i average of the upper excore detecur calibrated j outputs, or the ratto of the maxiaum lower encore i

detector calibrated output to th> average of the lower i excore detector calibrated outputs, whichever is i greater. With one encore deter. tor inoperable, the l remaining three detuctors shall be used for computing i the average.

RATED THERMAL POWER RATED THERMAL POWER shs11 be a total reactor core heat 1

transferratetothereactorcoolantof( ]

MWt.

l (continued)

!(

l Unit Wame 15 Amendment

! Draft 10/1/88 WOG :

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Ih l h Definiti 9 I L

( 1.1 DEFINITIONS (continueM A{ w - .,

REACTOR TRIP SYSTEM The REACTOR TRIP SYSTEM RESPONSE TIME shall be the RESPONSE TIME time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by any series of sequential, overlapping or total steps such that the entire respons's time is measured.

REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.

SHIELD BUILDING SHIELD BUILDING INTEGRITY shall exist when:

INTEGRITY

a. Each door in each access opening is closed except when the access apaning is beir.g used for normal

'trar. sit entry and exit, then at least one duor shall be closed,

b. The Shield Building Filtration System is OPERABLE, and

c. The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0 rings) is OPERABLE.

SHUTDOWN MARGIN SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be suberttical from its present condition, assuming all shutdown and control rod cluster assemblies are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assum d to be fully ,

withdrawn.

SITE BOUNDARY The $1TE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nst otherwise controlled by the licensee.

SLAVE RELAY TEST A SLAVE RELAY TEST shall be the energiration of each slave relay and vertf tcation of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation i devices.

SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

(continued)

(

l Unit Name 16 Amendment Draft 10/1/88 WOG I

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I"g l 9 .; 7'%I,d I Q'l ( j Definitions t .. .i m'T } ) 1.1 9

11 DEFINITIONS (continued) ~- b- -

(

STAGGERED TEST SASIS A STAGGERED TFST 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 subintervals, and

b. The testing of one system, subsystem, train, or other desiganted component at the beginning of each subinterval.

THERMAL POWER THERMAL "ER shall be the total reactor core heat transfer rate to the reactor coolant.

.ilP ACTUATING DEVICE TRIP ACTUATING DEVICE OPDA1l0NAL TEST shall consist l OPERATIONAL TEST of operating the Trip Actuating Divice and verifying l

OPERABILITY of alarm, interlock and/or trip functions.

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating bevice such that it actuates at th:s required Setpoint within the required accuracy.

UNIDENTIFIED LEAKAGE See LEAKAGE-UNIDENT!FIED. ,

h UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY to which access is not controlled by the Itcensee 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 for industrial, coastercial, institutional, and/or recreational purposes.

VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentratton or other operating condition, in such a manaer that replacement air or gas is not provided or required during VENTING. Vent, used ,

in system names, does not imply a VENTING process.

( Unit Name I-7 Amndment Draft 10/1/88 WOG

L7 y .,

.o

, Definitions y

1.1 O L al) .

Table 1-1 -

k Frecuanev Notation TABLE NOTATION REQUIRED FREQUENCY

$ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . '

W 7 days.

M 31 days. ,

Q 92 days.

SA 184 days.

R [18] months.

. S/U Prior to each reactor startup.

NA Not &pplicable.

(This Table, and the FREQUENCY NOTATION definition, may be deleted if the Technical Specifications rewrite eliminates "Table Notations' and specifies frequen:les in every Surveillance Requirement.]

I l

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I Unit Name 18 Amendment ,

Draft 10/1/88 WOG 1

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% RATED [ AVERAGE]

THERMAL POWER REACi%

REACTIVITY EXCLUDING DECAY C00LAhT g ILM CONDITION. Kaff HEAT TEMPERAWRE. 'F 1 POWER OPERATION 1 0.99 >5 1(350) .

2 STARTUP 1 0.99 15 1(350) 3 H0i STAN0tY < 0.99 NA 1(350) 4 HOT SHUTDOWN < 0.99 NA (350)>Tave l >[200) 5 COLD SHUTDOW < 0.99 NA 1(200) 6 REFUELING

1 0.95 NA 1 (140)

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

1 l

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( 19 bendment Unit Name beaft10/1/88 w03 i

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Logical Connectors

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'" " L 1.2 LOGICAL CONNECTORS i PURPOSE Logical connectors are used in technical specifications to discriminate between, and yet connect discrete Conditions,RequiredActionsandSurveillance Requirements. The only logical connectors which appear !

in technical specifications are E and E. The physical arrangement of these connectors constitute logical conventions with specific meaning.

The intent of this section is to provide specific examples of logical connectors and explain the intended !

meaning.

EXAMPLES 'Osmple 1., provided below, demonstrates that, for Condition A, both Required Actions must be completed.

. In this case, the logical connector E is laft 4 justified and shuws that both Required Action A.1 and Required Action A.L dre required, and have equal weight.

Example 1.

CONDITION REQUIRED ACTION A A.1 Restore

= ;

A.2 Se in i Example 2., is a more complicated use of logical connectors. In this example. Required Action A.1, to restore, or Required Action A.2, to align, or Required Action A.3.1, to verify, are alternate choices. If t

A 3.1 is chosen, an additional rsquirement, indicated by the nested logical connector E , is imposed. This additional requirement is met by choosing A.3.2.1 or A.3.2.2. The nested position of the logical connector M indicates that A.3.2.1 and A.3.2.2 are alternate and equal choices, one, but not both of which have to be ,

performed. -

l In addition to the position of the logical connectors, l the alphanumeric system is also u;ed to provide the '

proper interpretation of Required Actions. In Example i 2., the letter A identiftes that all of these* Required i Actions apoly to Condition A. The first number after a

(continued) j k .

l Unit Name 1-10 Amendment Draft 10/1/88 '

WOG 1

D togica1 Connectors 1.2 t;0 -

1.2 LOGICAL CONNECT 0AS nui3)

(.

EXAMPLES the letter A Cin this case 1. or 2. or 3. indicates a (continued) group of equa'i alternate actions for Cond)ition A.In the same manner, A.3.1 and A.3.2 are two Required Actions in the same group connected by a logical '

connector.

Required Actions in the same grcup are indicated by the same first digit and sequential second digits. Using this logic, Required Actions A.3.t.1 and A.3.2.2 are in ,

the same group becauae they have the same second digit and sequential third ditlits. The fact that they also have the same first digLt as A.3.1 above indicates that these Required Actions are also a part of that group.

i Example 2.

CONDITION REQUIRED ACTION A. A.1 Restore 3

A.2 Align _ ,

O A.3.1 Verify i

AMD A.3.2.1 Reduce 2 l A.3.2.2 Reduce l

i l

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( Unit Name 1-11 Amendrent Draft 10/1/88 WOG i

! I i

~ _ ,___ __ _

J L.

D completioa Times 1.3 COMPLETION TIMES PURPOSE Whenwer a Limiting Condition for Operation is not met, technical s>ecifications identify Required Actions which 'must >e completed within specified times. An understanding of the correct interpretation of Completion Times is necessary for compliance with the requirements of the technical specifications.

The purpose of this section is to discuss the ute of these Compietion Times, and explain, by example, the proper interpretation.

COMPLETION The Completion Time is the amount of time allowed to

. TIME .

complete a Required Action and is referenced to the time it is discoverad thG m ACTIONS Condition has been entered, unless otherv ,e specified. Required Actions must be completed wathin the specified Completion Time unless otherwise specified.

CONDITION When the ACTIONS Condition changes, for example, from a single inoperable component to multiple inoperable f CHANGES components of.the same tyne i.e., two pumps inoperable instead of one), a new Coinp1 tion Time is established In this situation, the original Condition, one pump inoserable) still exists separately or each of tie two pumps. The Completion Time for the original inoperable pump continues and a separate Completion Time exists for the second pump as well as for the two pump inoperable Condition. Thus, if all but one pump is returned to OPERABLE status, the l

ariginal Completion Time for the particular inoperable l pemp is not reset, but continues from the time that its original ACTIONS Condition was entered.

l INCOMPLETE REQUIRED When a Required Action is not completed within its ACTION Completion Time, a new Condition is established. This new Condition has its own Completion Time. Thus, if one inoperable pump is not returned to OPERABLE status within the Completion Time, its new Condition would be: "Required Action not completed within the required Completion Time". A new Required Action would then be I given for this Condition, with a new completion Time.

(continued) ,

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( Unit Name 1-12 Amendment Draft 10/1/88 WOG l

j Completion Times i>

f t .l M I.

L 1.3 COMPLETION TIMES (con TMat[) I-k - b -

(

INCOMPLETE REQUIRED Wr.on a Requiroo Action is nr.t completed within its ACIION Completion Tine, and the ACTIONS do not address the new (continued) Condition, the provisions of LC0 3.0.3 shall apply.

COMPOUND REQUIRED When a Required Action is comsosed of two or more ACTIONS AND reqJirements they are linked sy logical connectors COMPLETION TIMES (i.e., E or 2 ) and each requirement has its own separate Completion Time. Each Completion Time is referenced to the time that the ACTIONS Condition was entered.

For example, the requirement to be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , E in MODE 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months means that a total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed to reach MODE 3 and a total of 36 hnurs (ngt 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed to reach MODE 5 from tbn time that the ACTIONS Condition was entered. In this case, the 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months includes 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to reach MODE 3, and an additional 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months to reach MODE 5.

Another example is that the requirement to restore a process variable to within its limits in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months E be in H0DE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months means that I hour is allowed to restore the parameter or that 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months laqi 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ) is hs allowed to reach MODE 3 from the time that the ACTIONS Condition was entered.

I ___

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l Unit Name 1-13 Amendment Draft 10/1/88 WOG

, L.Lig>1c:nsideratig 1.4 LEGAL CONSIDERATIONS b . , y A . _

l INTRODUCTION The Atomic Energy Act of 1954 requires that technical specifications be a part of operating licenses. As such, they are enforceable under federal statute as well as under Title 10 Code of Federal Regulations.

When an applicant receives a license from the Nucisar Regulatory Comission to operate a coanercial nuclear power plant, the technical specifications are included as Appendix A to the license. Consequently, whenever a change is made to a plant's to:hnical sr - 'ations, it requires an amendment to the opeat . ense.

There are, however, certain sections and additional items included with the technical specifications that are not legally a part of .the technical specifications or the operating license. This section identifies the legal parts (i.e.. the parts that require a license amendment to make a change) of technical specifications and those additional parts that do not require a license amendmut to make a change.

LEGAL PARTS Title 10 Code of Federal Regulations, Part 50. Section 50.36 delineates those items which are to be included in the technical specifications. Itass to be included for nuclear power plants are:

o Safety Limits o Limiting Safety System Settings o Limiting Conditions for Operation o Surveillance Requirements o Design Features o Administrative Controls In addition, the Use and Application section which is comprised of Definitions, Logical Connectors, Completion Times and Legal Considerations, is also a legal part of the Tec.hnical Specifications. Since the technical specifications are normally issued as Appendix A to the operating license, any change to the technical specifications constitutes a license amendment. As such, the requirements contained in 10 CFR Sections 50.90, 50.91 and 5C.92 apply.

(continued)

Unit Name 1-14 Amendment Draft 10/1/88 WOG

. 7 - .3 - - .j p g "- 4egal Considerations 1.4 f

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l 1.4 LEGAL CONSIDERATIONS Wohnted) fE, (, j

( Front matter is all the material in the front of the FRONT MATTER technical specifications used to identify and locate specific information. It may include:

o Preface o Title page o Table of Contents o List of Tables o List of Figures o List of Effective Pages None of this material is required by Title 10 Code of Federal Regulations, Part 50, Sec. tion 50.36, and it does not include any requirements on the safe operation of the plant. Therefore, this section is not a legal part of the technical specifications or the operating license.

I CRUSS Cross-references are included in the body of the REFERENCES technical specifications to assist the user in I determining all applicable requirements for a comon

! system or component. This section of technical specifications is not mandated by Title 10 Code of Federal Regulations, and cross references are included in the technt:a1 specifications at the discretion of the licensee. As such, they are not a legal part of l the technical specifications or the operating license.

l BASES Title 10 Code of Federal Regulations, Part 50, Section 50.36 includes the following statement, "A sumary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall be included in the application, but shall not become part of the technical specifications". Therefore, the bases sections are not a legal part of the technical specifications. They are written and controlled by the licensee, and a change to the bases shall not constitute a change to the license.

1-15 Amendment Unit Name Draft 10/1/88 WOG

.

ML20206L588

Text

SUBJECT:

Enclosures:

Enclosures:

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