ML20063F238

Proposed Tech Specs 3/4.1.1.2, Reactivity Control Sys-Boron Dilution, 3/4.9.8.1, Refueling Operations - DHR & Coolant Circulation, 3/4.9.8.2, Refueling Operations - Low Water Level & Bases 3/4.1.1.2 & 3/4.9.8

ML20063F238
Person / Time
Site:	Davis Besse
Issue date:	01/31/1994
From:	CENTERIOR ENERGY
To:
Shared Package
ML20063F232	List: ML20063F230 ML20063F234 ML20063F238
References
NUDOCS 9402140196
Download: ML20063F238 (10)

Text

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Docket Number 50-346 .

' License Number NPF-3 Serial Number 2175 Attachment Paga 8 THIS PAGE PROVIDED-3/4.1 REACTIVfTY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTOOWN MARGIN ..

LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be > 1% ak/k.

APPLICABILITY: MODES 1, 2*, 3, 4 and 5.

ACTION:

With the SHUTDOWN MARGIN < 1% ak/k, immediately initiate and continue boration at > 18 gpm of 7875 ppm boron or its equivalent, until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be > 1% ak/k:

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a. Within one hour after detection of an inoperable control '

rod (s) and at least once per 12. hours therbaf ter while the rod (s) is inoperable. If the inoperable control rod is imovable "

or untrippable, the above required SHUTDOWN MARGIN shall be l increased by an amount at least equal to the withdrawn worth l of the immovable or untrippable control rod (s).

b. When in MODES 1 or# 2 , at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, by verifying that regulating rod groups withdrawal is within the limits of  ;

Specification 3.1.3.6.

0 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criti-

c. When in MODE 2  :

cality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6.

d. Prior to initial operation above 5%' RATED THERMAL POWER af ter each fuel loading by consideration of the. factors of e. below, with the regulating rod groups at the maximum insertion limit of Specification 3.1.3.6.

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'With Keff > 1.0.

With K eff e 1.0.

See Special Test Exception 3.10.4.  :

DAVIS-BESSE, UNIT 1 3/4 1-1 9402140196 940131 ,

PDR ADOCK 05000346 PDR n P

. Docket fiumber 50-346 License fiumber fiPP-3 Serial fiumber 2175 i Attachment Page 9 TH S PAGE PROVIDED I FORINFORMATION DNlY REACTIVITY CONTROL SYSTEMS t SURVEILLANCE REQUIREMENTS (Continued)

e. When in MODES 3, 4 or 5, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

1. Reactor coolant system boron concentration,

2. Control rod position,

3. Reactor coolant system average temperature,

4. Fuel burnup based on gross thermal energy generation,

5. Xenon concentration, and

6. Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 17, ak/k at least once .

per 31 Effective Full Power Days (EFPD). This comparison shall consider 1 at least those factors stated in Specification 4.1.1.1.1.e. above.

The predicted reactivity values shall be adjusted (normalized) to '

correspond to the actual core conditions prior to exceeding a fuel .,

burnup of 60 Effective Full Power Days af ter each fuel loading. l

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l DAVIS-BESSE, UNIT 1 3/4 1-2

D'cket o 11 umber 50-346

,' License fiumber 11PF-3 Serial fiumber 2175 Attachment Page 10 REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATIOW 3.1.1.2 The flow rate of reactor coolant through the Reactor Coolant System shall be > 2800 gpm whenever a reduction in Reactor Coolant System baron concentratton is being made.*

APPLICABILITY: All N0 DES.

ACTION:

With the flow rate of reactor coolant through the Reactor toolant System

< 2800 gpm. innediately suspend all operations involving a reduction in boron >ncentration of the Reactor Coolant System.

SURVEILtANCE REQUIREMENTS 4.1.1.2 The flow rate of reactor coolant through the Reactor Coolant System shall be determined to be > 2800 gpm within one hour prior to..the start of .

and at least once per hour ~during a reduction in the Reactor Coolant System baron concentration by either:

a. Verifying at least one reactor coolant pug is in operation, of

b. Verifying that at least one DHR pug is in operation and g> 2800 gpm to the Reactor Coolant System. _

___e-in f10DE or greater 5 the boron concentration of the water to be added is equal to MARGIN than the boron requirement concentration of Specification associated with the SliUTDOWN 3.1.1.1, or in MODE 6 ODE 5 or

• In/ MODE 6 the Reactor Coolant System (RCS) bomn concentration may be greater than the boron concentration of water available for addition. If the flowrate of reactor coolant through the RCS is less than 2800 gpm.

water of lower boron concentration than the_existino RCLcegentration may) be added to the RCS provided thatffhe boron concentration of the water to be added is equal to or greater than the boron concentratien corresponding to the more restrictive reactivity condition specified in Specification ~

3.9.1.

AVIS-BESSE UNIT 1 3/4 1-3 AmendmentNo.///

Docket Number 50-346 Licensee Fumber NPF-3 Serial Number 2175 Attachment Page 11 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 SHtJTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactoi can be made subcritical from all operating conditions. 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

During Modes 1 and 2 the SHUTDOWN MARGIN is known to be within limits if all control rods are OPERABLE and withdrawn to or beyond the insertion limit.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion. RCS boron concentration and RCS Tavg. The most restrictive condition occurs at EOL. with Taya at no load operating temperature. The SHUTDOWN MARGIN required is cons 11 tent with FSAR safety analysis assumptions.

3/4.1.1.2 BORON DILLITION A minimum flow rate of at least 2800 gpm provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual through the Reactor Coolant System in the core during boron concentration reductions in the Reactor Coolant System. A flow rate of. at least 2800 gpm will circulate an. equivalent Reactor Coolant System volume of 12.110 cubic-feet in approximately 30 minutes. The reactivity change rate associated with boron concentration reduction will be within the apability fopp_erator _ _

recognition and control.

-4GT'@u QM b a

f.- In MODE 6, the RCS boron concentration is typically somewhat higher than the minimum boron concentration required by Specification 3.9.1, and.coul,d be higher than the boren concentration of nonnal sources of. water-addTtion. At reduced inventory conditions in the RCS. in order ,tA veduce the possibility-of vortexing, the flowrate through the de IIt systenrmay be procedurally restricted to somewhat less Gen 2 pm. In this situation, if water with a boren concentration equal'to or greater than the boron concentration required by Specificatio,3.9.'i'is n added to the RCS. the RCS is assured to remain above j the Sp cation 3.9.1 requirement, and a flowrate of less than 2800 gpm is /

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Concern. j 3/4.1.1. 3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assunptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirement for' measurement of the MTC each fuel cycle are adequate to confinn the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confimation that '

the measured MTC value is within its limit provides assurance that the coefficient will be maintained within acceptable values throughout each fuel cycle.

CAYIS-BESSE. UNIT 1 8 3/4 1-1 Amendment ta.h

' Docket' Number'50-346 -

Licensee Number NPF-3 Serial. Number 2175-Attachment 'i Page 12 4

INSERT (New Paragraph, Bases 3/4.1.1.2)

In H0DE 5 or H0DE 6, the RCS boron concentration is typically somewhat higher than the boron concentration required by Specification 3.1.1.1 (HODE 5) or Specification 3.9.1 (HODE 6), and could be higher than the boron concentration of normal sources of water addition. At reduced inventory conditions in the RCS, in order to reduce the possibility of vortexing, the flovrate through the decay heat system may be procedurally restricted to somewhat less than 2800 gpm. In-this situation, if water with a boron ,

concentration equal to or greater than the boron concentration associated with the SHUTD0VN MARGIN requirement of Specification '

3.1.1.1 (MODE 5), or the boron concentration corresponding to the more restrictive reactivity condition specified in Specification 3.9.1 (MODE 6), is added to the RCS, the RCS boron concentration.is assured to remain above the minimum boron concentration' associated with the Specification 3.1.1.1 or Specification 3.9.1 requirement, and a flovrate of less than 2800 gpm is not of concern.-

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s . . l Docket ' Number 50-346 Ltcerisce Number NPF-3 Serial Number 2175 Attachmen;  ;

Page 13 THIS PAGE PROVIDED l 3/4.9 REFUELING OPERATIONS BORON CONCENTRATION l

LIMIT:NG CONDITION FOR OPERATION i 3.9.1 The boron concentration of all filled portions of the Reactor Coolant Syste and the refueling canal shall be maintained unifom and sufficient to l ensure that the more restrictive of the following reactivity conditions is met:

a. Either a K of 0.95 or less, which includes a'1% ak/k ,

conservatiNfallowance for uncertainties, or  ;

. A boron concentration of 1 1800 ppm, which includes a 50 ppm conservative allowance for uncertainties.

APPL:: ABILITY: ".00E 6.

l ACT!:';

With Me reauirements of the above specification not satisfied, i"1 mediately ,

suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at > 10 gpm of 8750 ppm boric acid solution or its equivalent until K,ff is reduced to ,< 0.95 or the boron concentration is restored to > 1800 pom, whichever is the more restrictive. [

Tne crovisions of Specification 3.0.3 are not applicable.

SU WE:'. LANCE REQUIREMENTS

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4.9.~.1 The more restrictive of the above two reactivity conditions shall be deter ined prior to:

a. Removing or unbolting the reactor vessel head,.and

5. Withdrawal of any safety or regulating rod in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4. 9.1. 2 The boron concentration of the reactor pressure vessel and the refueling canal shall be deterriined by chemical analysis at least once eacn 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3/4 9-1 Amendment No. 143 DAV:5-5E55E. UNIT 1

4 .

Docket Number 50-346 '

Licensee Number,NPF-3 Serial Number 2175 -

Attachment ,

Page 14 REFUELING OPERATIONS 3/4.9.8 DECAY HEAT RE!10 VAL AND COOLANT CIRCULATION ALL W'ATER LEVELS.

LIMIT'ING CONDITION FOR OPERATION

.3.9.8.1 At least one decay heat removal loop shall be in operation.

APPLICABILITY: WDE 6 When the water level above the top of th' irradiated fuel -

assenblies seated within the reactor pressure e. sel is > 23 feet.

ACTION: -r

a. With less than one decay heat removal loop in operation, except as provided in b below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from '

the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. The decay heat removal loop may be removed from operation for up to one hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the perfonmnce of CORE ALTERATIONS in the vicinity of the reactor pressure vessel (_ hot) legs.

c. The provisions of Specification 3.0.3 are not appitcable, e o

SURVEILLANCE REQUIREMENTS ,

'4.9.8.1 Surveillance at least once.per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shall verify at least one decay

heet removal loop to be in operation and circulating reactor coolant through the -

reactor core:

a. At a flow rate of > 2800 gpm, whenever a M' uction in Reactor Coolant System bomn conceiitration is being madeg l .

b. At a flow rate such that the core outlet' temperature is maintained'

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<l40'F, provided no reductio Reactor Coolant System boron concentration is being made. I l

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• Water'of a lower boron concentration than the existing RCS concentration may be added to the RCS, with the flowrate- .

of reactor coolant through the RCS less than 2800 gpm, -

provided that the boron concentration of the water to be-added is equal to or greater than the boron concentration corresponding to the more restrictive reactivity condition specified in Specification 3.9.1.

DAVIS-BESSE. UNIT 1 3/4 9-8 Amendnent' No. //

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6ocket Number 50-346.

Licensee Number NPF-3 Serial Number 2175 Attachment Page IS TH S PAGE PROVIDED f* REFUELING OPERAT10f5 FORINFORMAIl0N DNI.Y LOU 4ATER LEVEL Litt! TING CONDITION FOR OPEPATION s

3.9.8.2 Two independent DHR loops shall be OPERABLE.*

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

ACTION:

a. With less than the required DHR loeps OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

b. The provisions of Specification 3.0.3 are not applicable, SURVEILLANCE REQUIREMENTS 4.9.8.2 At least one DHR loop shall be detemined to be in' operation per Speci-l fication 4.9.8.1. The inactive loop shall be detemined to be OPERABLE per -

Speci fication 4.0.5.

I 4 The nomal or emergency power source may be inoperable for each DHR loop.

3/4 9 8a Amendment No. 38 DAVIS-BESSE. UNIT 1

1 1

Docket Number 50-346 I Licensee Number NPF-3  :

Serial Number 2175 Attachment Page 16 RETUELING OPERATIONS BASES 3/4.9.6 FUEL HANDLING BRIDGE OPERABILITY The OPERABILITY requirements of the hoist bridges used for movement of fuel assemblies ensures that: 1) fuel handling bridges vill be used for movement of control rods and fuel assemblies, 2) each hoist has sufficient load capacity to '

lift a fuel element, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal veight of a fuel assembly in a tailed fuel container over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release vill be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks vill no: result in a critical array. This assumption is consistent vith the activity release assumed in the accident analyses.

3/4.9.8 COOLANT CIRCULATION The requirement that at least one decay heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the vater in the reactor pressure vessel belov 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is naintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.

7 The requirement to have two DHR loops OPERABLE vhen there is less than 23 feet E of water above the core ensures that a single f ailure of the operating DHR loop D. vill not result in a complete loss of decay heat removal capability. Vith the 9 reactor vessel head removed and 23 feet of water above the core, a large heat 1

E sink is available for core cooling. Thus, in the event of a failure of the di operating DER loop, adequate time is provided to initiate emergency procedures to cool the core.

- 37 to 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM U

The OPERABILITY of this system ensures that the containment purge and exhaust penetrations vill be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITT of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 VATER LEVEL - REACTOR VESSEL AND ST0FAGE POOL The restrictions on minimum water level ensure that sufficient vater depth is available to remove 99I of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum vater depth is consistent with the assumptions of the safety analysis.

DAVIS-BESSE, UNIT 1 B 3/4 9-2 Amendment No. 38l /((

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. Docket flumber 50-346 License 14 umber 11PF-3

-Serial fiumber 2175 ,

' At tacliment- ,

Page'17

-Insert to Bases 3/4.9.8 (new paragraph)

In HODE 6, the RCS boron concentration is typically somewhat higher than the boron concentration required by Specification 3.9.1, and could be higher than the boron concentration of normal sources of water addition. The flovrate.  ;

through the decay heat system may.at times be reduced to somewhat-less than i 2800 gpm. In this situation, if water with a boron concentration equal' to or ~

greater than the boron concentration required by Specification 3.9.1 is added  ;

to the RCS, the RCS is assured to remain above the Specification 3.9.1~ '

_ requirement, and a flovrate of less-than 2800 gpm is not of concern.

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