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Proposed Tech Specs 3/4.4.6.2 Re Reactor Coolant Sys Operational Leakage & Bases
	ML20113G838
Person / Time
Site:	Davis Besse
Issue date:	05/01/1992
From:	; CENTERIOR ENERGY
To:	;
Shared Package
ML20113G827	List: ML20113G826; ML20113G832; ML20113G838;
References
	NUDOCS 9205120289
	Download: ML20113G838 (9)
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Docket Number 50-346 License Number NPF-3

= Serial Number 2023 At tac'hment 1 Page 7 l!

{,!REACTORCOOLANTSYSTEM

OPERATIONAL LEAKAGE I

I l

!! LIMITING CONDITION FOR OPERATION

' 3.4.6.2 Reactor Coolant Systes laakage shall be limited tot a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED t nrar:n, 1 GPM total primary-to-secondary leakage through steam generators, c.

l-d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant Systaa,.

I ij e.

10 GPM CONTROLLED LEAKAGE, and ll f.

5 GPM leakage from any Reactor Coolant Systaa Pressure Isolation Valve as specified in Table 3.4-2.

APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

l

.a.

With any PRESSURE BOUNDART LEAKAGE, be in at least HOT STANDBY vithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUIDOVN vithin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

Vith any Reactor Coolant Systen leakage greater than any one of the ll above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least BOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SRttfD0VN vithin the following 30 l

hours except as permitted by paragraph c below.

In the event that integrity of any pressure isolation valve specified c.

in Table 3.4-2 cannot be demonstrated, POVER OPERATION any continue.

l provided that at least two valves in each high pressure line having a non-functional valve are in and remain in, the mode corresponding to the isolated condition.(a)

P The provisions.of SectioK3.0.4Cand 4.0.4]sre not applicable for entry l d.

into MODES 3 and 4 for the purpose of testirig the isolation valves in Table 3.A-2.

I i

i

(*) Motor operated valves shall be placed in the closed position and power supplies deenergized.

9205120289 920501 PDR ADOCK 05000346 P

PDR DAVIS-BESSE, UNIT 1 3/4 bl5 Otidt did. 4/10/81.

Amencment No, MI l

~.

Docket Number 50-346

-License Number NPP-3 Serial Number 2023

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Page 8 REACTOR COOLANT SYSTEM i

SURVEILLANCE REQUIREMEM S 4.4.6.2.1 Reactor Coolant Systen leakages shall be demonstrated to be within each of the soove limits by:

gaseood or Monitoring the containment atmosphere particulate radioactivity 6nito[ \\

a.

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

g A cA; hon b.

Monitoring the containment sump (inventory)and 81scharge)at least once l

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

Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump c.

seals to the makeup system when the Reactor Coolant Systen pressurr is 2185 :t 20 psig at least once per 31 days.

d.'

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during steady state operation.

4.4.6.2.2 Each Reactor Coolant Systen Pressure Isolation Valve specified in Table 3.4-2 shall be individually demonstrated OPERABLE by verifying leakage testing (or the equivalent) to be within its limit prior to entering MODE 2 a.

After each refueling outage, b.

Whenever the plant has been in COLD SHWDOVN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or more, and if leakage testing has not been performed in the previous 9 eenths, and Prior to returning the valve to service following maintenance, repair c.

or replacement vork on the valve.

d.

hmment er SectAcerten 4.oA are nd opbbic {g cey mio t@ Des a nd 4.

_4.4.6.2.V Vhenever integrity of a pressure isolation valve listed in TableN 3.4-2 cannot be demonstrated, the integrity of the remaining pressure isolation valve or_ the integrity of the remaining pressure isolation valve in series with the actor-operated containaant isolation valve in each high pressure line havin y

a leaking valve shall be determined and recorded daily./In addition.gthe l

(

position of the closee actor-operated containaant isolation valve located in the}

high pressure piping (hall be recordedJ11aily l

$5

%2 9-s

Whenever the integrity of a pressure isolation valve listed in Table 3.4-2 cannot be demonstrated. determine and record the integrity of the high aressure flowcath on a daily basis.

Integrity shall be determined bv i

performinc either a leakage test of the remaintne pressure is;1ation valve, l

or a combined leakage test of the remaininc pressure isolation valve in series with the closed motor operated containment isolation valve.

DAVIS-BESSE, UNIT 1 3/4 4-16 ArAar Aci. y,Mi Amendment No. /A l#

I m

Docket Number 50-346

License Number NPF-3 Serial Number 2023 7A3LE 3.1-2

,Page;9 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES FOR INFORMATiON CNLY SYSTEM VALVE NUMBERS (b)

MAXIE4 ALLOWABLE LEAXAGE (a)(c) 1.

Decay Heat Removal CF-30 1 5.0 gpm 2.

Cecay Heat Removal CF-31 3 5.0 gpm 3.

Cecay Heat Removal m-76 1 5.0 gpm 4

Cecay Heat Removal CH-77 1 5.0 gpm Notes:

(a) 1.'

Leakage rates less than or equal to 1.0 gpa are considered acceptable.

2.

Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gps are consitend acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an anzaunt that reduces the margin between measured leakage rate and the maximta permissible rate of 5.0 gpm by 50% or greater.

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3.

Leakage rates greater than 1.0 gpa out less than or ocual to 5.0 gpa are considend unacceptable if the latest measured rate exceeded the rate determined by the previcus' test by an amount -

I that reduces the mergin between measured leakage rate and the maximum permissible rate of 5.0 gpa by 50% or greater, i

4 Leakage rates greater than 5.0 gpr: are considerec unacceptable.

(b)

Valves CF-30 and CF-31 will b's tested with the Reactor Coolant system pressure >l200 psig.

Valves OH-76 and DH-77 will be tested with noneal Core Flooding Tank pressure which is >575 psig. Mi ni-met differential test pressure across each valve shall not be less than 150 psid.

(c)

To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if ace::tolished in accordancs with approved procedures and supported by c moutations showing that the method is capable of demonstrating valve ecmpliance with the leakage criteria.

I CAVIS-BESSE, UNIT 1 3/4 ?-16a Order etc.

4/20/81

Docket Number 50-346 i

License Number NPF-3 Serial Number 2023 i

Page 10 REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to detect and monitor leakage from the Reactor Coolant Pressure Boundary. Tnese detection systems are consistent with the recommendations of Regulatory Guide 1.45. " Reactor Coolant Pressure Boundary Leakage Detection Systems,! May 1973.

3/4.4.6.2 OPERATIONAL LEAKAGE PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHtJTDOWN.

f Industry experience has shown that, while a limited amount of leakage is expected from the RCS, the UNIDENTIFIED LEAKAGE portion of this can be reduced to a threshold value of less than 1 GPM. This threshold value is sufficiently low to ensure early detection of additional leakage.

The total steam generator tube leakage limit of 1 GPM for all steam generators ensures that the dosage contribution from tube leakage will be limited to a small fraction ofA art 100 limits in the evant of either l

P a steam generator tube rupture or steam line break. The i GPM limit is]

consistent with the assumptions used in the analysis of these accidents, gg The 10 GPM IDENTIFIED LEAKAGE limitation provides ellowance for a limited amount of leakage fror, known sources whose presence will not interfere with the detection of UNIDENTIFILS LEAKAGE by the leakage detection systems.

The CONTROLLED LEAKAGE limit of 10 GPM restricts operation with a total RCS leakage from all RC pump seals in excess of 10 GPM.

insert-M The surveillance requirements for RCS Pressure Isolation Valves NPh provide added assurance of valve integrity thereby reducing the here. -b probability of gross valve failure and consequent intersystem LOCA.

Leakage from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and vill be considered as a portion of the allowed limit.

DAVIS-BESSE, UNIT 1 B 3/4 4-4

Docket Nosber 50-346 License Number NPF-3 Serial Number 2023 Page 11

>3/4 ' MITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS m.0 uPuCi>Iu" FOR INFORMAT'CN ONLY LIMIIING CONDITION FOR OPERATION

! L O.1 Limiting Conditions f or Operation and ACTION requirements shall be applicaole during the OPERATIONAL MODES or other conditions specified for each jspecification.

i3.0.2 Adherence to the requirements of the Limiting Condition for Operation l and/or associated ACION vithin the specified time interval shall constitute compliance with the specification.

In the event the Limiting Condition for iloperation is restored prior to expiration of the specified time interval, i: completion of the ACTION statement is not required.

.i

'.3.0.3

" hen a Limiting Condition for Operation is not met, except as provided in

. : the associated ACTION regt.irements, action shall be initiated within i hour to

': place tne unit in a MODE in r*ich the Specification does not apply y placing i

!it, as applicable, in:

1.

At least HOT STANDBT vithin the nexe 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

}

l' 2.

At least HOT SEE DOVN vithin the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , a d 3.

At least COLD SHW DOVN vithin the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

, Vhere corrective measures are completed that permit operation under the ACTION 1l requirements, the ACTION may be taken in accordance with the specified time l l limits as measured f rom the time of f ailure to meet the Limiting Condition for iiOperation. Exceptions to these requirements are stated in the individual l{ Specifications.

3.0.4 Entry into an OPERATIONAL hu sr other specified applicability condition

shall

..,t ce made unless the condi ns of the Limiting Condition for Operation

are met,ithout reliance on provis. is contained in the ACTION statements unless

,otnervise excepted. This provision shall not prevent passage tnrougn

0PERATIONAL MODES as required to comply with ACTION statements.

,5

' hen a system, subsystem, train, component or device is determined to be

l 3.0.5

', inoperable solely because its emergency power source is inoperable, or solely

!because its normal power source is inoperable, it may be considered OPERABLE for

! the purpose of satisfying the requirements of its applicable Limiting Condition ll for Operation, providadt (1) its corresponding normal or emergency povar source

1 is OPERABLE: and (2) all of its redundant system (s), subsystem (s), train (s),

,! component (s) and device (s) are OPERABLE, or likewise satisfy tne requirements of

lthis specification. Unless both conditions (1) and (2) are satisfied, within 2

) hours action shall be initiated to place the unit in a MODE in which tne

,l applicaole Limiting Condition for Operation does not apply by placing it as

,iapplicable in:

l.

At least HOT STANDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , i

j 2.

At least HOT SHUTDOVN vithin the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and j

jj 3.

At least COLD SHUIDOVN vithin the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This Specification is not rpplicable in MODES 5 or 6.

t 0 AVIS-BESSE. UNIT 1 3/4 0-1 Amenament No.

'.T.

,t A6,1ca

Docket Number 50-346 License Number HPF-3 Serial Number 2L23 Page 12 m muCABlug FOR INFORMATION ONLY i'5ES Se specifications of this secti:n provide the general reoutrements a::11:stle to eacn of the Liutting C:nditions for Operation ana surveillance

e:utrements within Section 3/4.

3.3.1 This scacification cefines the appli; ability of eacn s ecification a terms of defined OPEPATIONAL MODES er otner specified canaitiens ano is provided

:elineate specifically wnen eacn specification is applicable.

3.0.2 This specification oefines those conditions necessary to c nstitute cealiance with the tenns of an individual Limiting Condition for 0:eration and assectata ACTION requirement.

3.0.3 This specification delineates the ACTION to be taken fer circumstances not cirectly provided for in the ACTION statements and wnose occurr:nce would violate tre intent of the specification. For example. Specification 3.5.1 recutres each Reactor Coolant System core flooding tank to be OPERABLE and

rovices explicit ACTION requirements if one tank is inoperable. Under the tems

f the Scecificattun 3.0.3, if more tnan one tank is inopersble, witnin one hour measures must be initiated to place the unit in at least HOT STAN0BY within the next 6 rgrs, and in at least HOT SHUTDOWN within the'fol'.owing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a further exmple. Specification 3.6.2.1 requires two Containment Soray Systems to oe OPERABLE and provides excelicit ACTION requirements if one scray system is inoperable. Unde the tems of Specification 3.0.3, if both cf the required Conta'nment Soray O stems ar9 inoperable, within one hour measures must Le initirtert to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in at least COLD SHUTDOWN in the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

It is assumed that the unit is trougnt to ne rea;. red MODE within the recuired times by promptly initiating ano carrying ut the apprupriate ACTION statement.

3.0.4 This specificacion orovices tnat entry into an OPERATIONAL MODE Or otner specified appiicability condition must be made with (a) tne full c:molement of required systems, equipment or components OPERABLE and (b) all other carameters as specified in the Limiting Conditions for Operation ceing met witt.Lut regard for allowable oeviations and out of service provisions contained ir :ne ACTION statements.

The intent of this provision is to insure that facility xeration is not initiated with either required equipment or systems inoperabit or otner scecified limits being exceeded.

Exceptions to this provision r M ':n provided for a limitea numeer of s:ecifications when startup with ineDaale equipment would no; iffect :lant safety. These exceptions are statec in the ACTION statements of the apprerriate sDeC1fications.

DAVIS-EESSE UNIT 1 B 3/4 0 1 Amenanent No. 71.153

m Cocket Number 50-346 License Nurnbt r NPP-3 I

Serial Number 2023 Page 13 UmuCxBnm FOR INFORMATION ONLY hjeAsts

!; ACTION reautrements, e.g., Specification 3.0.3, a 24-hour allwance is providtd to permit a celay in implementing tne ACTION recu1rements.

This provices an aceouate time limit to complete Surveillance Recu1rements tnat have not been perf omeo.

Tne purpose of this allowance is to pemit the completion of a surveillance before a shutdown is recuired to comply with ACTION reouirements or before otner remedial measures would be required that may preclude conple-tion of a surveillance. The basis-for this allowance includes consiceration for plant conditions, adequate planning, availabflity of personnel, the time recuired to perform the surveillance, and the safety significence of the delay in completing the reautred surveillance.

If a.urveillance is not completee within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is perfomed within the 24-hour allowance and the Surveillance Requirments are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is teminated.

Surveillance Requirements do not have to be perfomed on inoperable equip-ment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Pequirements hav? to be met to demonstrate that inoperable equipment has been restored h GM RABLE status.

4. C. 4 This specification ensure: + m t'te surveillance activities associated with a Limiting Conditior :c4 3peration have been perfomeo within the specified time interval prior to entry into an OPERATIONAL M00E or other applicable condition.

The iritent of this provision is to ensure that surveil-i lance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.

Under the 9ns of this specification, for example, during initial plant startuo or ~..

t ig extenced plant outages, the applicable surveillance activities c.t be perfomed within the stated surveillance interval prior to placing or returning the system or equipment into OPERABLE status.

4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice tasting of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with:a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenca as reouired by 10 CFR 50.55a.

Relief from any of the above requirements has been provided in writing by the Comusion and is not a part of these technical specifications.

This specification includes a clarification of the frequencies for perform-ing the inservice inspection and testing activities recuired by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals througneut tnase Technical Specifications and to ruove any ambiguities relative l

to tne frecuencies for perfoming tne recuired inservice inspection en: testing activities.

DAVIS-BESSE, UNIT 1 B 3/4 0-3 Amenoment No. 145

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Docket Number 50-146 License Number NPF-3 Serial Number 2023 At tachmerit 1 FOR INFORMATION ONLY reu u

REACTCR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYST!" LEAKAGE LEAKAGE OETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor C:olant System leakage cetect on systems shall be OPERABLE:

a.

The containment atnesonere particulate radioactivity monitor-ing cystem, b.,

The containment sumo level and flow monitoring system, and c.

The containment atmosonere gaseour, radioactivity monitoring system.

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

With only twc of the above recuired leakage detection systems OPERABLE, oreration.T.ay continue for up to 30 days provided grab samples are cotained i

and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous or particulate radioactivity monitoring system is inoperable; otnerwise be in at least FOT 5"NDBY witnin tne next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within tne following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I l

SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated CPERABLE by:

1 a.

Containmert atres;nere carticulate monitoring system.oerfernance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frecuencies specified in Table 4.3-3.

l DAVIS-BESSE, UNIT l-3/4 4-13

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Docket Number 50-346 1.icense Number NPF-3 Serial Number 2023

$$'U""

FOR.NFORMATION ONLY REACTCR CCOLANT SYSTEM SURVE!Lt.ANCE REOUIREMENTS (Continued) b.

Containtnent sumo level and flew monitoring system-cerfor.snee of CPANNEL CALIBRATION at least once per 18 montns, c.

Containment at.oschere gaseous monitoring systern oerfemance of CHANNEL CHECK CHANNEL CALIBRATION and CFANNEL UNCTIONAL TIIT at the frecuencies specified in Table 4.0 3.

f DAVIS BESSE, UNIT 1 3/4 4-14

ML20113G838

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