ML20217M667

Proposed Tech Specs Adding Ventilation Filter Testing Program

ML20217M667
Person / Time
Site:	LaSalle
Issue date:	05/01/1998
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20217M645	List: ML20217M638 ML20217M661 ML20217M667
References
NUDOCS 9805050079
Download: ML20217M667 (13)

Text

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ATTACHMENT D REVISED TECHNICAL SPECIFICATION PAGES NPF- 11 NPF-18 3/4 7-4 3/4 7-4 INSERT D INSERT D B 3/4 7-1 B 3/4 7-1 6-20a 6-20a INSERT K INSERT K

• a' iMJ 3Ess7a P PDR

d PLANT SYSTDtS '

3/4.7.2 CONTROL ROOM AND AUXILIARY ELECTRIC EQUIPMENT 200M EMERGENCY FILTRATIDN 5Y5itM ,,

LIMIT!as CONDITION FOR OPERATION 3.7.2 Two independent control room and' auxiliary electric equipment room emergency filtration system trains shall be OPERA 8LE.#  !

r APPLICA81LITY: All DPERATIONAL CONDITIONS and *.

ACTION: '

a. With one emergency filtration system train inoperable, restore the inoperable train to OPERA 8LE status within 7 days or:

1. In OPERATIONAL CONDITIONS 1, 2, 2, be in at least NOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. In OPERATIONAL CONDITION 4, 5 or 8, initiate and maintain operation of the OFIRABLE emergency filtration system in the pressurization moos of operation.

b. With both emergency filtration system trains inoperable, in '

OPERATIONAL CONDITION 4, 5 or ", suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with ,*

a potential for draining the reactor vessel. '

c. The provisions of Specification 3.0.3 are'not applicable in Operational Conditior. 8 i SURVEILLANCE REQUIREMENTS 4.7.2 Each control room and auxiliary electric souipment room emergency filtration system train'shall be demonstrated OPERABLE:

T1- gy D a. At least once per 31 days on a STAGGERED TEST BASIS by initiating.

f from the control room, flow through the HEFA filters and charcoal Q adsorbers and verifying that the train operatas for at least j 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters OPERABLE. -

)

"Wnen irraoisted fuel is being handled in the secondary containment.

The normal or emergency power source may be inoperable in OPERATIDML CONDITION 4, 5 or

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LA SALLE - UNIT 1 3/4 7-4 .

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l MSERT D

a. "At least once per 31 days on a STAGGERED TEST BASIS:

1. Operate each Control Room and Auxiliary Electric Equipment Room Emergency Filter System for greater than or equal to 10 continuous hours with the heaters operating, and

2. Manually initiating flow through the control room and auxiliary electric equipment room recirculation filters for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

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F 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 CORE STANDBY C00 LING SYSTEM - EDUIPMENT CODLING WATER SYmris The OPERABILITY of the core standby cooling system - equipment cooling I water systems and the ultimate heat sink ensure that sufficient cooling j capacity is available for continued operation of safety-related equipment

.during nonmal and accident conditions. The redundant cooling capacity of these systems, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits. 3 3FILTRATION

/4. 7. 2 CONTROL SYSTEM to0M AND AUIILIARY EtFETIIC EQUIPMENT ROOM EMERGENCY g [

The OPERABILITY of the control room and auxiliary electric equipment room emergency filtration- system ensures that the rooms will remain habitable for operations personnel during and following all design basis accident conditions. The OPERABILITY of this system in conjunction with room design  ;

provisions is based on limiting the radiation exposure to personnel occupying i the rooms to 5 rem or less whole body, or its equivalent. .This limitation is l consistent with the requirements f.Gener sign Criteria 19 of A'ppendix 'A' 1 hGFR Part 50. ati operation of the system with the heaters ERABL7 for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over 1 riod is sufficient to reduce the buildup @oTmoisture on the adsorbers 11ters. and '

oPeWi%  % m uous 3/4.7.3 REACTOR CORE IsDLATION COOLING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from fts primary heat sink and the lou of feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling System equipment. The RCIC system is conservatively required to be OPERABLE whenever reactor pressure j ev.eeds 150 psig even though the LPCI mode of the the residual heat removal i (WHR) system provides adequate core cooling up to 350 psig.

The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2 and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary non-ECCS sourcs of core cooling when the reactor.is pressurized.

With the RCIC system inoperable, adequate com cooling is assured by the OPERABILITY of the' HPCS system and justifies the specified 14 day out-of-service' period.

The surveillance requirements provide adequ;1te assurance that RCICS will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown. Initial startup test program data may be used to determine equivalent turbine / pump capabilities between test flow path and the vessel injection flow path. The pump discharge piping is maintained full to prevent water hammer damage and to start cooling '

at the. earliest possible moment. The low pressure setpoint allowable value for the discharge line " keep-filled" alars is based on the head of water (~-

between the centerline of the' pump discharge and the system high point vent.  :

LA SALLE - UNIT 1 B 3/4 7-1 Amendment No. 1 m._

ADMTNISTRA VE CONTROLS PLANT GPdtATING PROCEDURES AND PROGRAMS (Continued) 1 1

n=+= T etine M aram r L. 6.2.F.k**i=="v a- rant 4-nt 1.nba= o j l

~

' A progr5 shall be established to implement the leakage rate testi of the

' primary containment as required by 10 CFR SC.54Fo? and 10 CFR 50 pendix J.

Option B, as codified by approved exemptions. Th9s program shall in i accordance with the guidelines contained in Regulatory Guide 1.163,  !

• Performance-Based, Containment Leak-Testing Program," dated September 1995.

The peak calculateh prima loss of coolant accident, containment internal pressure for the design basis

, is 3g.6 psig.

The maximum primary allowable containment primaryper air weight containment day. leakage rate, L , at P., is 0.635% of

\

Leakage rate acceptance criteria are:

a.

Primary containment overall leakage rate acceptance criterion is $1.0 L During the first unit startup following testing in accordance with this,.

program, the leakage rate acceptance criteria are s 0.60 L for the combined Type 8 and Type C tests, and s 0.75 L, for Type A, tests, b .' Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is 50.05 L, when tested at 2 P,.

l

2) l between the door seals is pressurized to 2 10 psig.For each doo i The provisions of specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leskage Rate Testing Program.

)

The provisions Leakage of specification Rate Testing Program. 4.0.3 are applicable to the Primary Containment 6.3 t ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN P The following actions shall be taken for REPORTABLE EVENTS: I i

a.

The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE Investigative EVENT sha'11 be reviewed by the Onsite Review and Function.

_LnsecI-\N!

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l INGERT K i

8. Ventilation Filter Testina Proaram NFTPl A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies l specified in Regulatory Guide 1.52, Revision 2, dated March 1978, and in l

accordance with ASME N510-1989.

)

!- The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the VFTP test

! frequer cles.

a. Demonstrate for each of the ESF systems that an inplt e test of the high efficiency particulate air (HEPA) filters shows a penetra..lon and system l l bypass < 0.05 % when tested in accordance with ASME N510-1989, at the system flowrate specified below:

ESF Ventilation System Flowrate (cfm) i SBGT System a 3600 and s 4400 l CREF System a 3600 and s 4400 t .

b. Demonstrate for each of the ESF system filter units that an inplace test of the charcoal adsorber shows a penetration and system bypass less than the value specified below, when tested in accordance with ASME N510-1989, at the system flowrate specified below:

ESF Ventilation Penetration and Flowrate (cfm)  ;

System System Bypass  !

l SBGT System 0.05 % a 3600 and s 4400 l

CREF System . 0.05 % a 3600 and s 4400  ;

CRRF System 2.0 % 218000 and s 28900 j l

AEERRF System 2.0 % a 14000 and s 22800 1

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INSERT K (Continued) '

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory I Guide 1.52, Revision 2, shows the methyl lodido penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at .

a temperature of 30*C, a relative humidity of 70 % and a face velocity as specified below.

ESF Ventilation Penetration Face Velocity ,

System (fpm)

SBGT System 0.5 % 40 CREF System 2.5 % 40 CRRF System 15.0 % 80 AEERRF System 15.0 % 80

d. Demonstrate for each of the ESF systems that the pressure drop across the combined moisture separator, heater, profilter, HEPA filters and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below:

ESF Ventilation Delta P (inches wg) Flowrate (cfm)

System SBGT System 8 a 3600 and s 4400 CREF System 8 a 3600 and s 4400 CRRF System 3.0 i 18000 and s 28900 AEERRF System 3.0 a 14000 and s 22800

e. Demonstrate that the heaters for each of the ESF systems dissipate the electrical power specified below when tested in accordance with ASME N5101989. These readings shall include appropriate corrections for variations from 480 */olts at the bus.

ESF Ventilation System Wattage (kw)

SBGT System a 21 and s 25 CREF System a 18 and s 22

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3.7.2 he independast austrel team and and11ery elastric equipment room emorgmasy ffitratten system treias ses11 to OPEMBLE.*# - - -

APPL 2MEILITY: All GPBAT!WWE CWWm0118 seg a, M

a. tite ama amargesqr filtration system train tasperehle, restore the inspareMe trate as WERABLE status witMa 7 esys or:

L Im OPEATIBIAL CWSm0 LIE 1, 2. 3 he is at least IST SWT00lde withfe the must 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> and ta COLS SEmimel witarin the fsflestag 36 heers.

. .~..

• L la OPERATIB14L CBSm0N 4, 5 or 8, initiate and maintain aparaties of the OPERABLE emergensy flitraties system in the pressurismates ande of operation.

. ~'

k. ffitratten system treias tamperele, in WftIt heth '

GPERATISIAL 4, 5 or *, suspend CDB ALTRATImIE, handling .

of treadistad faml in the seconeary amata1 ament and operations with a potential for drainias me toecter vessel.

c. The provisiens of Specification 1.0.3 are met applicable in Operettenal Canditten 8 suRytILudect ----a _.J.

- 4.7.2 Each eestrel reas and mart 11ery electric equipment roes emergency 1trutten system trata shall he esmanstrated OPERABLE:

p M gph i C At least enes per 31 days en a STm T557 BASIS by initiating.

fre. e. trei r , fio. eres h me MPA filters and.esressi

\h, asserters and verifying that the train operates for at least ,

41 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> wie the hosters OPEMBLL

• l i

. y "Whed Irradiated fuel is being handled in the sessadery esatainment.

8

- The moraal er power source sur he insperable in OPRATIONAL -

C0181T30114. S er .

LA s4LLs - unri 2 3/4 7-4

I l INSERT D 1

a. "At least once per 31 days on a STAGGERED TEST BASIS:

1. Operate each Control Room and Auxiliary Electric Equipment Room l Emergency Filter System for greater than or equal to 10 continuous hours with the heaters operating, and 1

2. Manually initiating flow through the control room and auxiliary electric equipment room recirculation filters for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

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3/4.7 PLANT SYSTEMS BASES 3/4.7.1 CORE STANDBY COOLING SYSTEM sBHIPMENT C00 LING WATER SYSTEMS The OPERABILITY of the core standby cooling system - equipment cooling water systems and the ultimate heat stak ensure that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant. cooling capacity of these systems, assuming a single failure, is consistent with the assumptions-used in the accident conditions withis acceptable limits.

3/4.7.2 CONTROL ROOM AND AUXILIARY nsrTRIC EDUIpMENT R00M EERcENCY FILTRATION SYSTEM ggJ F

The OPERABILITY of the emergency filtration systeel,ensures control that roomtheand auxiliary electric equipment room rooms will remain habitable for operations personnel during and following all design basir accident conditions. The OPERABILITY of this system in conjunction with room design provisions is based on limiting the radiation exposure to personnel occupying the rooms to 5 ren or less whole body, or its equivalent. This limitation is consistent with the requirements of Genera Design Critaria 19 of Appendix lA" 10 CFR Part 50.Chlati operation of the system with the heatersCOPERABLDTor 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 riod is sufficient to reduce the buildup offmoisture on the adsorbers and filters.

%CfWQfi 3/4.7.3 REACTOR Cc8tE I@sDLATION [o/Pf//lVOUS Ctww INC SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling System equipment. The RCIC system is conservatively required to be OPERABLE whenever reactor pressure exceeds 150 psig even though the LPCI ande of the residual heat removal (RHR) system provides adequate core cooling up to 350 psig.

The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2.and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary non-ECCS source of core cooling when the reactor is pressurized.

With the RCIC system inoperable, adequate core cdoling is assured by the OPERABILITY of the HPCS system and justifies the specified 14 day out-of-service period.

The surveillance requirements nwide adequate assurance that RCICS will l

be OPERABLE when required. Althoug1 all active components are testable and .

full flow can be demonstrated by recirculation during reactor operation, a '

complete functional test requires reactor shutdown. Initial startup test program data may be used to detemine equivalent turbine / pump capabilities between test flow path and the vessel injection flow path. The pump discharge piping is maintained full to prevent water hammer damage and to start cooling at the' earliest possible moment. The low pressure setpoint allowable value for the discharge line " keep-filled" alam is based on the head of water between the centerline of the pump discharge and the system high point vent.

(_)

LA SALLE - UNIT 2 8 3/4 7-1 Amendment No.

ADNINftTRATIVE CONTRDtt PLANT OPERATINc PRDemIRFK AND Penc8AMS (Continued) the Initial structural Integrity Tests were not within 2 years of 'each other. (

l The Onsite haview and Investigative Function shall be responsible for myiewing and approving chan .

for Post Tensioning Tendons.ges to the Inservice Inspection Program The provisions of 4.0.2 and 4.0.3 are applicable to the Tendon Survellignee Program insepetion frequencies.

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'L6.2.Fginary tantainment Leakane Rate Testino m,was -

.--+ A prograf shall be established to implement the leakage rate testing of the Option 8, as modified by approved exemptions. primary containment as accordance with the guidelines contained in RegulatorThis program shall be in "Perfomance-Based Containment Leak-Testing Program,"y Guide 1.163, dated September Igg 5.

The peak loss of calculated coolant primary accident, P,, iscontainment internal pressure for the design basis 3g.6 psig. {

primary containment air weight per day.TheL,,maximum allowable at P,, is 0.635% of priml l l

Leakage rate acceptance criteria are:

a.

Primary containment overall leakage rate acceptance criterion is $1.0 L During p the first unit startup following testing in accordance with this., \

A forarethe s 0.60 c

ram, ined Typethe5 and leakage Type C rate acceptance tests, and criteria s 0.75 L, for Type ests, L,t

b. Air leck testing acceptance criteria are:

1)

Overall air lock leakage rate is 50.05 L, when tested at 2 P,.

2) between the door seals is pressurized to 2 10 psig.For eac The provisions of specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of specification 4.0.3 are applicab Leakage Rate Testing Program.

6' 3 ACTf0N TO BE TAKEN IN THE EVENT OF A RfKmidBLE EV&iT '

The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a Licensee Event Report '

submitted 10 CFR Part pursuant 50, and to the requirements of Section 50.73 to b.

Each REPORTA8LE EVENT shall be reviewed pursuant to Specification 6.1.G.2.c(1).

1hf56N Y LA sattE - unrT 2 6-20a Amendmentno./

9 c

INSERT K

8. - Ventilation Filter Testino Proaram WFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2, dated March 1978, and in accordance with ASME N5101989.

The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the VFTP test frequencies.

a. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < 0.05 % when tested in accordance with ASME N5101989, at the system flowrate specified below:

ESF Ventilation System Flowrate (cfm)'

SBGT System a 3600 and s 4400 CREF System a 3600 and s 4400

b. Demonstrate for each of the ESF system filter units that an inplace test of the charcoal adsorber shows a penetration and system bypass less than the value specified below, when tested in accordance with ASME N510-1989, at the system flowrate specified below:

ESF Ventilation Penetration and Flowrate (cfm)

System System Bypass SBGT System 0.05 % a 3600 and s 4400 CREF System 0.05 % 2 3600 and s 4400 L CRRF System 2.0 % 218000 and s 28900 AEERRF System 2.0 % = 14000 and s 22800

r 1

INSERT 'K (Continued) '

c. Demonstrate for each of the ESF systems that a laboratory test of a sample (

of the charcoal adsorber, when obtained as described in Regulatory L Guide 1.52, Revision 2, shows the methyl lodido penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30*C, a relative humidity of 70 % and a face velocity as specified below.

ESF Ventilation Penetration Face Velocity System (fpm)

SBGT System 0.5 % 40 l CREF System 2.5 % 40 CRRF System 15.0 % 80 AEERRF System 15.0 % 80

d. Demonstrate for each of the ESF systems that the pressure drop across the I

combined moisture separator, heater, profilter, HEPA filters and the charcoal adsorbers is less than the value specified below when tested at the system flowrate spe:lfied below:

ESF Ventilation Delta P (inches wg) Flowrate (cfm)

System q

SBGT System 8 a 3600 and s 4400 l CREF System 8 a 3600 and s 4400 CRRF System 3.0 a 18000 and s 28900 AEERRF System 3.0 a 14000 and s 22800

e. Demonstrate that the heaters for each of the ESF systems dissipate the electrical power specified below when tested in accordance with j ASME N5101989. These readings shall include appropriate corrections for j variations from 480 Volts at the bus.

ESF Ventilation System Wattage (kw) i i

SBGT System a 21 and s 25

' CREF System a 18 and s 22 l