ML20217C377
| ML20217C377 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/26/1997 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20217C365 | List: |
| References | |
| NUDOCS 9710010371 | |
| Download: ML20217C377 (51) | |
Text
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ATTACHMENT B 1 i l l LASALLE COUNTY NUCLEAR POWER STATION l
] UNITS 1 AND 2
) MARKED UP ANNOTATED COPY OF AFFECTED PAGES FOR PROPOSED CHANGES TO s
FACILITY OPERATING LICENSES NPF-11 AND NPF 18 4
- APPENDIX A TECHNICAL SPECIFICATIONS VENTILATION FILTER TESTING PROGRAM i
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- ju ABMA 7583ljp
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ATTACHMENT B PROPOSED AMENDMENTS TO THE i LICENSE / TECHNICAL SPECIFICATIONS i
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i 3/4 6 15 3/4618
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1 3/4641 3/4644
- insert A Insert A
! Insert B Insert B j 3/4642 3/4645
- Insert C Insert C l 3/4 7 4 3/47-4 Insert D insert D 3/4 7 5 3/4 7 5
- insert E Insert E '
- Insert F Insert F 3/4 7 6 3/4 7-6 Insert G insert G l Insert H Insert H l B 3/4 6 2 B 3/4 6 2a !
Insert I insert i B 3/4 7-1 B 3/4 7 1 Insett J Insert J j 6 20s 6 20s l
4 Insert K Insert K
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- j. i i There are no changes on these pages. They are only included for continuity.
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CONTAINMENT $YSTEMS DRYWELL AND SUPPRES$10N CHAMBER PURGE $YSTEN LIMITING CONDITION FOR OPERATION 3.5.1.8 The d nd suppression chamber purge systaa may be in operation with the drywel r suppression chamber ~ purge supply and exhaust butterfly isolation valves open for inerting, de-inerting and pressure controit Purging throegh the Standby Gas Treatment system shall be restricted to less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days.
APPLICABILITY: OPERATIONAL C0fe!TIONS 1, 2 and 3.
ACTION; yy .
Wi
/ drywell r suppression chamber pur exhaust butterfl isolation valve n for other than inerting,ge supplyde inert ng or pressure control,y close the butterfly valve (s) within one hour or be in at least NOT $HLTf00WN 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 />.
- 4
$URVEILLANCE REQUIREMENTS 4.6.1.8.1 The cumulative time that the drywell and suppression chamber purge system has been in operation purging through the Standby Gas Treatment System shall be verified to be lest than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days prior to use in this mode of operation.
/
LA SALLE - UNIT 1 3/4 6-15 Amendment No.
l COWTAINMENT $YSTEMS STAN0tY GAS TREATMENT SYSTEM .
LIMITING CONDITION FOR OPERATIDW 3.6.5.3 Two independent standby pas treatment subsystems shall be OPERABLE.#
APPLICA31LTTY: OPERATIONAL CONDITIONS 1, 2,* 3, and *. l Mt .
- a. With one stantiby gas treatment subsystem inoperable, restore the inoperable subsystas to OPERABLE status within 7 dtys, or:
- 1. In OPERABLE CONDITION 1, 2, or 3, be in at leset NOT SHLITDOWN l 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 *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and opera-tions with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.
- b. With both standby gas treatment subsystems inoperable in Operational Condition ", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel. The provisions of Speclfication 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.6.5.3 Each standby gas treatment subsystem shall be demonstrated OPERABLE:
- a. At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heatars OPERABLE.
"When irradiatec fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the isector vessel.
The normal or emergency power ' source may be inoperable in Operatfonal Condition 8 LA SALLE - UNIT 1 3/4 6-40 Anemteent No. 18
. . _ __O
CONTAINMENT SYSTfMS
$URVE!LLANCE REQUIREMEKT5 (Continued)
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings or(2)following
- painting, fire,orchemicalreleaseinanyventilationzone communicating with the subsysten by:
nu' 1. Verifying that the subsystem satisfies the in-place testing T N gT ff M acceptance criteria and uses the test procedures of Regulatory Positions C.S.a. C.5.c and C.5.d of Regulatory Guide 1.52 Revision 2. March 1978, and the system flow rate is 4000 cfm 110%.
- 2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.12. Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52 Revision 2, March 1978.
- 3. Verifying a subsystem flow rate of 4000 cfm + 10% during system operation when tested in accordance with ANSI M510-1975.
- c. fAfter every no nours of charcoal adiorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2. March 1978 Y ' neets the laboratory testing criteria of Regulatory Position C.E.a QfRegulatoryGuide1.52. Revision 2, March 1978,
- d. At least once per 18 months by:
i l 1. herifying that the pressure dro across the combined HEPA filte fg and charcoal adsorber banks is ess than or equal to 8 inches I "J)$8 ' $ Water Gauge while operating the filter train at a flow rate of (4000cfma105.
- 2. Verifying that the filter train starts and isolation dampers open on each of the following test signals:
- a. Reactor Building exhaust plenum radiation - high,
- b. Drywell pressure - high,
- c. Reactor vessel water level - low low, level 2, and
- d. Fuel pool vent exhaust radiation - high.
~
3.
.N Verifying that the heaters dissipate 23 1 2.0 kw when tested in 7 ~
accordance with ANSI N510-1975. This reading shall include the l gropriatecorrectionforvariationsfrom480voltsattheb LA SALLE - UNIT 1 3/4 6-41 Amendment No. 1
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT A Perform required standby gas treatment filter testing in accordance with, and at the frequency specified by, the Ventilation Filter Testing Program.
INSERT B 1
Deleted.
B-2
~ . _ . .... ...- ' . _ . ., . . . . ... . :.~ . .
CONTAINMENT 5YSTEMS 5UWEILLANCE REQUIREMENTS (Continued) e, fAfter each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to lo$er C ga of we 00P wnen sney are tested in.,iace in ace.edanc with AN52 (N5101975 whileoperatingthesystemataflowrateof4000cfmalog
- f. fAfter each complete or partial replacement of a charcoal adsorberM bank by verifying that the charcoal adsorbers remove greater than or equal to pH of a halogenated hydrocarbon refrigerant test pas when they are tested in place in accordance with ANSI N510-1975 while (operating the system at a flow rate of 4000 cfm 115.
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LA SALLE - UNIT 1 3/4 5-42
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ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEITECHNICAL SPECIFICATIONS INSERT C Deleted.
i B-3
PLANT SYSTEMS .
3/4.7. l! CONTROL 200N AND AUXILIARY ELECTRIC E00!PNENT R00N ENERGENCY FILTRA ' ION 5 W tM ,,
LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room and'euxiliary electric equipment room emergency filtratten system trains shall be-0*ERABLE.8
- . g APPLICABILITY: AliOPERATIONALCONDITIONSand*.
ACTION: '
- a. With one energency filtration system train inoperable, restore the inoperable train to OPERABLE status within 7 days or:
- 1. In OPERATIONAL CONDITIONS 1, 2, 3, be in at least HOT 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 *, initiate and maintain operation cf the OPERABLE emergenc pressurization mooe of operation. y filtration system in the
- 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 Condition a.
SURVEILLANCE REQUIREMENTS 4.7.2 Each control room and auxiliary electric equipment room emergency filtration system train shall be demonstrated OPERABLE:
gD a. Atleastonceper31daysonr.STAGGEREDTESTBASISbyinitikin, l
i from the control room, flow through the HEPA filters and charcoa D adsorbers and verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters OPERABLE. -
When irraatated fuel is being handled in the secondary containment.
ThenormaloremergencypowersourcemaybeinoperableinOPERATIONAL CONDITION 4, 5 or LA SALLE - UNIT 1 3/4 7-4 .
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEITECHNICAL SPECIFICATIONS i
(RSERT D
- a. "At least once per 31 days on a STAGGERED TEST BASIS:
- 1. By initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters OPERABLE, and
- 2. Manually Initiating flow through the control room and auxillary 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 />.
B-4
4 PLAWTSYSTEMJ, *
$URVEILLANCE REQUlttMEwis (Continued)
- b. kt least once per la months" or (1) after any structural maintenanc on the NEPA filter er charcoal adsorber housings, or (2) following painting, fire er chemical release in any ventilation zone ceamunicating with the train by:
- 1. Verifying that the train satisfies the in place testing MS6[, ' acceptance criteria and uses the test procedures of R 1 Positions C.5.a. C.5.c and C.S.d of Regulatory Guide 1% story ,
Revision 2. March 1978, and the train flow rate is 4000 cfm i 10K. ,
- 2. Verifying within 31 days after removal that a laboratory analysis of s representative ca son sample obtained in ,
accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2. March 1978 meets the laboratory testing criteria of Regulatory Position C.E.a of Regulatory Guide 1.52. Revision 2, March 1978.
- 3. Verifyingatrainflowrateof4000cfm+105duringsubsystem/
operation when tested in accordance with' ANSI N510-1975. /
- c. /After every 720** hours of charcoal adsorber operation by verifyM f within 31 days after removal that a laboratory analysis of a Ar/ representative carbon sample obtained in accordance with Re_gulatory gg(v F Positon C.G.b of Regglatory Guide 1.52. Revision 2. March 1978, s ..
keetsthelaboratorytestingcriteriaofRegulatoryPositionC.6.a f Regulatory Guide 1.52 Revision 2, Narch 1978._
- d. At least once per 18 months by:
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- 1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorter banks is less than 8 inches Water Ga while operating the train at a flow rate of 4000 cfm r
"Tih s surveillance shall include the recirculating charcoal filter, " ado in the normal control room supply filter train using ANSI N510-1975 as a guide '
to verify g 70K efficiency in removing freon test pas.
- Except that recirculating charcoal filter samples shall be removed and analyzed at least once per 18 months.
LA SALLE - UNIT 1 3/4 7-5 Amendment No.
9 9
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ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT E Perform required control room and auxiliary electric equipment room filter testing in accordance with, and at the frequency specified by, tho Ventilation Filter Testing Program.
INSERT F Deleted.,
B-5
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__ m PLAl.7 SYSTEMS j ] g tC;
- $URVEILLANCE REQUIREMENTS (Continued) ~ - -'-
- 2. Verifyi L test si Is, the emergency trei automatically switches to the p p D that en each of the below pressurizatten mode actuation pressur zation mode of operati nf W n:t d E z ie maintained at a positive press of 1/8 inch W.G. relative to the adjacent areas during emergency rain operation _at a t
' flew rata less than er equal *te 4000 fs: - ^
?
a) Outside air seeke detection, and 7;d ee un\% r'bk 0T~
b) Air intake radiation monitors.
D
- 3. krifying that the heaters dissipate 2012.0 Kw when tested in
')
accordance with ANSI N510-1975. This reading shall include the g rapriate correction for variations from 480 volts at the busy l
g n. fAiter each completa er partial replacement of a HEPA filter bank by%
,., verifying that the HEPA filter banks remove greater than er equal to 1
,pg6 iI 995 of the DDP when they are tested in-place in accordance with ANSI /
, i N510-1975 1 15. while operating the system at a flew rate of 4000 cfm j l l f. iifte each complete er partial replacement of a charcoal adsoser - bank by verifying that the charcoal adsorbers remove 99K of a 1 halogenated hydroca sen refrigerant test pas when they are tested l i in place in accordance with ANSI N510-1975 while operating the stem at a flow rate of 4000 cfs a 10K. , 2 ) i l 4 This surveillance shall include the recirculating charcoal filter. "edor eater," ' in the nomal centrol reos supply filter train using ANSI N510-1975 as a
; guide to verify 1 70K efficiency in removing freon test pas.
4 g T i f LA SALLE - UNIT 1 3/4 7-6 Amendment No. i s
l l ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS ; INSERT G Manually initiate flow through the control room and auxillcry electric equipment room recirculation filters line and then verify that the control room and auxillany electric equipment rooms are INSERT H Deleted. B-6
CONTAlletENT SYSTEks nr.SE5 3/4.6.1 PRIMARY CONTAllt(ENT l 3/4.5.1.4 nrtrTED 3/4.s.l.s ortrTED h 3/4.6.1.5 DAYWELb Als SUPPRESSION CHAMBER INTERNAL PRESSUSf l The limitation on drywell and suppression chamber internal pressure ensure that the containment peak pressure of 39.6 psig does not excoed the design pressure of 45 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of 5 psid. The limit of 2.0 psig for initial positive primary containment pressure will limit the total pressure to 39.6 psig whics is less I than the design pressure and is consistent with the accident analysis. 3/4.5.1.7 DAYWELL AVERAGE AIR TEMPERATURE The limitation op drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340*F during LOCA conditions and is consistent with the accident ant. lysis. 3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, de-inerting.and pressure control. hose valves have been demonstrated capable of closing during a LOCA or steamline break accident from the full open position. ly1$&Y LA SALLE - UNIT 1 B 3/4 6-2 Amendment No. 2
ATTACHMENT B i PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT l During operations involving inerting, de inerting and pressure control,
- only the drywell or suppression chamber purge supply and eyhaust
- Isolation valves may be open to prevent the creation of a bypass path
- between the drywell and suppression chamber. Creation of a bypass path between the drywell and the suppression chamber air space through the i vent and purge lines would allow steam and gases from a LOCA to
- bypass the downcomers to the suppression poolin excess of design j
bypass leakage. 4 I a l I l 4 f J 4 B-7
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3/4.7 PLANT SYEYDtt Ratti 3/4.7.1 ener IT_AwaY ran81Mc EYSTDI - rautpHENT rnns the WATER SYSTDtt The OPERABILITY of the core standby cooling system - equipment cooling water systems and the ultimate heat sink ensure that sufficient cooling capacity is available for continued operation of safety-related equipment d;; ring normal and accident conditions. The mdundant cooling capacity of these systems, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits. 314.7.n FILTRA" lot"nuYant'ene SYSTDI Aun Aur1LIARY rtrcThic rautpurNT n- imucracy gg[! 4 I, The OPERABILITY of the0 control rees and auxiliary electric equipment room emergency filtration system ensures that the rooms will remain habitable for operations personnel durinp and following all design basis accident conditions. The OPERA 81L1 Y of this sysnes in conjunction with room design provisions is based on limiting the radiation exposure to personnel occupying the rooms to 5 ren or less who e body,-ar its equivalent. This , imitation is consistent with the requirements of General Desien Criteria lg of Appendix 'A',10 CFR Part 50. Cumulative operation of the system with the heaters OPERABLE for 10 hours over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. 314.7.3 REAcTDn enar tent ATimi enniIMC SYSTEM l The reactor core isolation cooling system is provided to assure i i adequate core cooling th the event ctor of rea(RCIC) 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 sede of the the residual heat removal (RHR) system provides adequate core cooling up to 350 psig. The RCIC system specifications arv applicable during 0PERATIONAL 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 mactor is pressurized. With the RCIC system inoperable, adequate core cooling is assured by the OPERASILITY of the HPCs system and justifies the specified 14 day out-of-service period. The surveillance requirements provide adequate assurance that RCICS will be OPERABLE when required. Althougi all v.tive components are testable and full flow can be demonstrated by recirculation durin complete functional test requires reactor shutdown. gInitial reactorstartup operation, testa program data may be used to detemine equivalent turbine / pump capabilities atween test flow path and the vessel injection flew ,ath. The pump discharge-piping is maintainei full to prevent water hammer damage and to start cooling at the.earitest 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 tte pump discharge and the system high point vent, ( LA SALLE - UNIT i B 3/4 7-1 Amendment No. 1 E
l ATTACHMENT B PROPOSED AMEN 0MENTS TO THE LICENSE / TECHNICAL. SPECIFICATIONS INSERT J l
, which includes the control room and auxillary electric equipment rcom recirculation filters,
)
i i e B-8 ,f
,. - ,, ,- . _ . . - . . , . . _ . - - - - , . . , r - . , . . . , . -
_ . _ _ _ . . _ , _ _ - - - - - - - - - - - ~ ~ ~ ~ ~ ~ ~ ~ ^ ~ ' 1 i ~ Aty'INISTRA VE CONTRotS l i ptANTGPdtATINGPROCEDURESANDPROGRANS(Continued) I II-1.F. m i==rv ra=*=i----' l uhaa 82+= Tutha praarm o__ w.n - -
- i A progrM sha'l be established to implement the leakage rate testi of the
-4 o and 10 CFR 50 pendix J, i
Option B, 66 modifi6d by approved exemptions. primary cent in 41nnent as N req i accordance with the guidelines contained in Regulatory Guide 1.163, ;
' Performance-Ease (CentainmentLeak-TestingProgram,'datedSeptember1995.
/
l. T'ne lose af peak calculateh coelast eccNent, primary containment in~ternal pressure for the design basis P., is ag.6 psig. ! The mim j primary co!e Dewable nte '3sent primaht per day. containment ieakage air wei rate, L,,ofat P,, is 0.635% h Leakage rate acceptancc criteria are: l s. j Primary containment overall leakaoe rate acceptance criterion is sl.0 L i During the first unit startup following testing in accordance with this,. procran, the leakage rate acceptance criteria are s 0.60 L for the ! combined Type B and Type C tests, and 5 0.75 L, for Type A, tests. 1
- b. Air lock testing acceptance criteria are: \
j 1) Overall air sock leakage rate is 50.05 L, when tested at 2 P,. I 2) i For each door the seal leakage rate is s 5 scf per hour when the gap 4 between the do,or seals is pressurized to 2 10 psig. i a 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 applicable to the Primary Containment Leakage Rate Testing Program. k .36 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION , The following actions shall be taken for REPORTA8LE EVENTS:
- 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 EVENT shall be reviewed by the Onsite Review and Investigative Function.
Inse#k' LA SALLE - UNIT 1 6-20a - Amendment No.
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT K
- 8. V3Riijation Filter Testina Pronram (VFTP)
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 conducted in general conformance with ASME N5101989. l The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the VFTP test frequencies,
- n. 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 general conformance with Regulatory Guide 1.52, Revision 2, and ASME N5101989, at the system flowrate specified below:
ESF Ventilation Flowrate (cfm) System SBG1 Syttem a 3600 and s 4400 CREF System > 3600 and s 4400 B-9
1 ATTACHMENT B PROPOSED AMENDMENTS TO THE ! LICENSE / TECHNICAL SPECIFICATIONS i
- INSERT K (Continued) i i
- 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 general conformance with Regulatory Guide 1.52, j Revision 2, and ASME N5101989, at the system flowrate specified below: 1 l ESF Ventilation Penetration and Flowrate (cfm) System System Bypass ) SBGT System 0.05 % > 3600 and s 4400 ) CREF System 0.05% a 3600 and s 4400 [ CRRF System 2.0 % a 18000 and s 28900 ! AEERRF System 2.0 % a 14000 and s 19900 } c. Demonstrate for each of the ESF systems that a laboratory i test of a sample of the charcoal adsorber, when obtained as } described in Regulatory Guide 1.52, Revision 2, shows the j methyl lodido penetration less than the value specified below when tested at a temperature of 30'C, a relative humidity of - l 70 % and a face velocity as specified below in general j conformance with ASME D38031989. j - ESF Ventilation Penetration Face
- System Velocity (fpm)
SBGT System 0.5 % 40
- CREF System 2.5 % 40
[ CRRF System 15.0 % 80 i AEERRF System 15.0 % 80 i ) B-10 i,
. _ - . _ , _ _ _ _ , . _ . ,,,.__...,...--..,.,,.--m.._ . . , . . , . _ _ , _ _ _ - . _ - _ , _ _ _ . _ _ _ . , . _ . . . _ . , ,
ATTACHMENT B 1 PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS i l@ERT K (Continued) )
- 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 i the value specified below when tested at the system flowrate specified below
l ESF Ventilation Delta P Flowrate (cfm) System (Inches wg)
- - SBGT System 8 2 3600 and s 4400 CREF System 8 a 3600 and s 4400 l e. Demonstrate that the heaters for each of the ESF systems dissipate the electrical power specified below when tested in j general conformance with ASME N5101989. These readings 3 shall include appropriate corrections for variations from 480 4 Volts at the bus.
- ESF Ventilation Wattage (kw) j System
- SBGT System a 21 and s 25 t
CREF System a 18 and s 22 4 B-11 f ; l
. . _ , _ _ . . . . -. _ _ _ _ _ _ , _ _ _ _ . . - - . . . _ _ _ ._ - - . _ - ___ ._ ,_m. .. .- - ,_ _ - - _ _
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CONTA!899ff SYITBE DRYWELL A m IUPPt h (Im CIW ell Pu ut t#3TD4 LIMmMG Cole! TIM POR estRAT10N 1 3.6.1.8 The' suppression eb purge systs any be in operation with the tryuel sup,Aressten theater purge supply and exhaust butterfly isolation va)ves for inerting, esinertins and pressure control.
- through the Staney See Treetaaet Syste shall,be restricted te less then erPurging g equal to M hours per MB days.
WPLICABILITY: OpthATIONAL Cos!TIONS 1, 2, and 3. l : M With[eryuell agpression chanter pur isoletion va) fer other then inerting,ge supply er ashaust esimerti butterf y sure centre), within I hour er he in et close in the nestthe32butterf y velve(s) hours and in COLD SMUTD0l01 within the following M hours.SW
$URVE!LLANCE REDufRDeffl
~
4.6.1.8.1 The cumulative #timethatthedryw11andsuppressionchamberpurge' systes hus been in operetten purging through the Stoney See Treatment lysten shal) he verified te he )ess then er equal te 30 hours per M5 days prior to une in this ande of operetten. -. 4 e ( , 4 a 9 4 e = eum e LA SALLI - tal!T 2 3/4 6 3 Amendeont he. A
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a
.f. .
l i h - . l . Conransurr nyms. j . . stains ans matierr 'st:7m i ! Iwrfwa w paaD e . I - i l . 8 , ! 3.8.5.3 Tuo independent steney pas treatmast sesystems shall he OPERABLL# i ~
- APPLICARILITY: OPERAT10lt4L ComiT!aIIB 1,1, 3, and *.
M: ! a. tetth one steney Jos treatment sesystes inoperable, resters the l insporele sesysten to OPERABLE states'within 7 days, or: i L Ia OPmAOLE CIRWITIgli 1, 2, or 3 h
'rltarin the most 31 meurs and SG in Ne in at.least m MR81 within the NT SRmRhel i .
fellesing M heers. ' i ! L Ia OPERAT10114L CIRSITIBII *, suspend handline of irradiated i fuel in tem secondary eastoimment, COM ALTSRAT!aII5 and escre-l tiens with a potential for dreising the reenter vessel. The 3 provisieme of Spesifiestian 8.0.3 are not applisele. i N
- l h. iftth hoe stoney gas treatment sesystems insparels in OPERAT10lI4L '
l CIBSIT!BII *, seepend handitas of irradisted fuel in the secondary i
- enstaissent, CDE ALTER 4710pIB and operations with a posential for dreising the reester veneel. The pewisions of Specifiamtion 3.0.3 are not applis ele. ,
i } greyrrii m 's - --1__ _.is I 4.6.L3, Emeh stamey gas treatment sesystem ehell he demonstrated OPERABLE: , ,,
- s. At least enen 31 days hy initiating, from the control room, flew
. tirespi time filters and cheresol asserters and verifying that the l .sesystes operates for at least 30 hours with the heaters w-ABEL yy 3 .
'9 sten irradiated fuel to being handled in the secondary sentainment and during GNIE ALTER 4710 LIB and operations with a potentini for draining the mester vessel.
Mhe namel or amargensy power eeures any be insparele in OPWIAT10ll4L COM IT!all 8 O LA SALLI - WIT 2 3/4 6-43 t
1 . .. . 4 CMffAINNT fYSTD5 l * ' i SURYnLLANCE nemisserfs (Cantinued) i
- h. /ft least once per 18 months er'(1) after a g structural meintenance s en the NEPA filter er cherceal adsorter housines er(2)following i
f painting, fire, or chemical release in av ventilatian sene commugicating with the subsystem by: .
- r s
, L Verifying that the sesyste satisfies the in place ting
,_r A 6 6 f 9'g
=ce,t.c. criteria w == the test pr=. ores .f neguistory l Pu itions C.5.a. C.5.c and C.5.d of hogulatory Guide 1.52, .
l Revisten 7, March 1978, and the system fles rate is 4000 cfm 2 105.- , 2. Verifying within 31 days after removal that a laboretary analysis i i of i representative certon sample attained in accordance with Regul posi, tion C.6.b of Reguistory evide 1.51, hovision 2 i 1 ; March , meets the laboratory testing cH teH a of Angulatory j Position C.6.a of Regulatory Guide L52, Revision 2 March 1974. *j i ! 3. Verifying a subsystem fles reta of 4000 cfm + 115 during syntas , operation ehen tested in accordance with ANET 510-1975. i c. I i {within 31 days after removal that a laboratory analysis of aAft i representative carton sample obtained in accordance with beculatory Positten C.S.h of Regulatory Guide L52 Revision 2. March 1978 ( meetsthelaboratorytastingcHteriaofRegulatoryPositionC.d.a) ,~
- hoguistory Guide L82, hovision 2 March 1978. _ ,,./
i d. At least once per 38 months by: g i [, - 4 1 [ileri ng that the pre'sure drog er.ress the esubined EPA filters e 1 s }/ _ and g I adserter henks is sees then er equal to 8 inches le operating the filter train at a fles reta of
- 2. Vedfying that tne filter train starts and isolation dampers '
i apen en each of the fellowing test signals:'
- a. Reacter Building exhaust plane radiation - high, i
- b. Dryuell pressum - high,
- c.
Reacter vessel unter level - les leu, level 2, and" *
- d. Fuel peel vent exhaust radiation - high.
I 4 l 3. { Verifying that the heaters dissipate 23
- 2.0 W uhen tested accordance with ANSI M510-1975.
4 i appropriate correction for vaHations free 480 volts at the th-Thisreadingshallinclud -
}
i . i l LA SALLE
- 1811T 2 3/4 6-44 Amenment No.
I - n s. . i
,- . . . - - . . , . . . . . . . . . . _ _ .- _ _ . . . , . _ . _ . ~ , , _ , _ _ _ _ _ . . . _ _ _ . _ - . . , , _ . _ _ . _ _ . - . _ . . _ . _ .
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT A Perform required standby gas treatment filter testing in accordance with, and at the frequency specified by, the Vontilation Filter Testing Program. INSERT B Deleted. B-12
..u . V. ,
a .-2: > .m pq',Q .M2x. .. .A.gk.4 lc ,_ t , hw* ?P.e s l .-
+
, . --. - mawnu E - 1_ _. .. t*- -1 _ __ _
e
, s. I ensk seglete er portfa') rolesammet of a MPA ft1ter boek by fyiss met the m filter beste remove greater tade or aquel to 1\ j 95 et the BOP tese tiny are tested impiese is esserdamse with AII5!
ggfD b
'~
p1875 ul:11e apersties the erstes et a fler rete of 4000 cfm a
- f. [After eseh soglete er partial replassenet of a sheroes) asserher T haak by verifying that the el:erses) adsorters remove greater them er l egnal to 95 ef a helegensted hydreesttee refri test pas when th w are tested teryleen is essordamse with 1830 1975 wet 11e tag the systes at a flee rate of 4000 sta a 15.
1 .
- s. * *
.e * *
- anc
'.CL t *
- LA SALLI - Et!T 2. 3/4 6-48 4
ATTACHMENT B PROPOSED AMENDMENTS TO THE
- LICENSE / TECHNICAL SPECIFICATIONS INSERT C Deleted.
1 4 i B-13
- s ~~ .; - [ . Q .~ . .
.- ,. . 9. L - . .~ .
m, m m . 0,E,m0,, _ =._.... =.. . . 1 3.7.2 Two independent control room and asui11ary electric equipment rwas emergency filtration system trains shall be OPERAtlI # - -' APM.ICARPE: All OPERATIONAL CON 0m0Its and 8 i ! g:
- a. With one energency filtration systas train inoperable, restere the
- inoperabis train to OPERABLE status within 7 days er:
- 1. In OPERATICIIAL CDISITIOf51, 2. 3, be in at least NOT SHLHDOW -
witkie the next 12 hours and in CotA SWTDOW within the following 24 hours.
. .~. . 2. In OPDATIONAL CONDITION 4, 5 or *, initiate and maintain
, aperstice of the OPERABLE energency filtration system in the pressurization sede of operation.
- k. With both emergency filtration systes trains inoperable, in OPERATIONAL C0fSITIOff 4, 5 or 8, suspend CORE ALTERATI0sts, handling. .
of irradiated fuel in the secondary containment and operations with a petantial for draining the reactor vessel. l c. The prwisione of Specification 3.0.3 are not applicable in 3 Operatium1 Candities *. ! 5UINEILLAfeCE ItEDUiRTi 4.7.2 Each costrel reos and auxiliary electric equipment rose emergency Itration system train shall be desenstrated OPERABLE: p (
/bgph ih, i
At least once per 31 days en a STAGGERED TEST SASIS by initiatino, from the contal room, flow through the IEPA filters and. charcoal adsorters and verifying that the train aperatas for at least
-l>
10 hours with the hosters OPDABLE. 4
%en irradiated fuel is being herAled in the secondary containment.
. 'The nomal or power sourca esy be insperable in OPERATIONAL COISITICII 4. 5 or . i l . 2 1 LA SALLE - UNIT 2 3/4 7-4
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS l lNSERT D
- a. "At least once per 31 days on a STAGGERED TEST BASIS:
- 1. By initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the train operates for at least 10 hours with the heaters OPERABLE, and .
- 2. Manually initiating flow through the control room and
, auxiliary electric equipment room recirculation filters for at least 10 hours. 6 4 1 I l ! B-14
4 W i
- ~
j , PUWff SYSTBE . ) SWWEILIANCE esmIRBeff5 (Continued) ! b. [Aten the leastMPAenen fi fter er sharcoal adsorber housings, or (2) fo l painting. fire or chemical release in any wantilation aans ! sam unicattag with the train ty: ' ! \ " t L yerifying that the train satisfies the in place testing j g asseptance criteria and uses the test precedures of tegulatory i r .-- g{i Positions C.5.a. C.5.c and C.5.8 of Angulatory Guide 1.52, l
/* p f Sovision 2. flersh 3378, and the train flew rete is 4000 cfm
- 35.
- 2. Verifying within 31 days after removal that a laboratory I
analysis of a representative carben sample obtaines in accordenes with Angulatory Positten,C.S.D of Regulatory 0 i Guide L52, hovision 2. fierch 197s, meets the laboratory. I testing critoria of Reguistory Positten C.S.a of Regulatory
- evide 1.52. Asvisten 2, fierch 2378.
Verifying a train flow rete of 4000 cfm + 25 during sesystem i (3. - eperation when tested in asserdance with~AIISI M10-1975.
-- \
- c. fwithin 31 days after removal that a laboretary analysis of a .
\
~~_nge P' representative so P.mne.8.hof,rtensampleehtainedin,accordensewith,%1
,,we,, 8,m 1.ss, ,m . ,,c story l
meets the lahoratory testing criteria of Regulatory Position C.S.a l Regulatory Guide LSt. Revision 2. narch 3S78. ' l d. At laest once per 38 months by: A ! 1. fVerifying that the pressure ihp across the esshined MPA j filters and cherceal adsetter banks is less than 8 inches tieter
, while aperating the train at a flew rete of 4000 cfe
{ -
~
i - i
-S.
i l
.1
.. .)-
~
f i p _ ! "This surveillance shall include the recirculating chorosal filter. "eder enter," i . in the nereal control fees sagiply filter train using Alt $1 E30-3875 as a guide j to verify 175 efficiency in removing freon test pas. - i ""Eacept that rectreulating charcoal filter samples shall he removed and
; analyzed at least ease per 38 months.
f LA SALLE - UllIT 2 3/4 7-5 Amesulment fle.
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT E Perform required control room and auxiliary electric equipment room filter testing in accordance with, and at the frequency specified by, the f Ventilation Filter Testing Program. i LN_ SERT F Deleted. B-15
i f mm - r ! i 3sesC SURyt1Raamm ammisselfs (Castinued) : 1 i s i
- 2. Worifying that en each of the below pressurisation made actue-tien test signals, the emergency train automatically switches te )
the pressurisatten ande of sporettepc f *' -- M n O d
. maintained at a positive pressure inch W.S. relative to
! g the adjacent areas during emergoney in operation at a f_ low _. trata 1 ass then er equal to 4000 smo: i
- 4) Detside air emote detection, and hgWbCI ec ucd Nb -
b) Air intake radiation annitors. l
- 3. [5erifying that the hosters dissipate 20 e 2.0 ihr when tasted in C, accordance with 1251 11530-3875. This reading shall include the j
_7 ;Wata cornetien for variations fue 400 volta at the bu i
- a. (After cash eenplete er partial replacement of a MPA filter henk by j ', \
verifying that the MPA filter banks remove greater then er agual to , 7gp hri 35 of the 90P when they are testad in place in aceerdance with ANSI i { y(1830-1975 ukila operating the system at a flow rete Sf 4000 11 5 . m-j cfm i
- f. f esoplete or partial rep 1rmaant of a cheress1*adsortierl <
' by verifying that tke charassi asserhers rumsve SE of a helegenstad lydr:earken refrigerant test gas when they are testad ~ in-place in accor10ance with AIISI 1810-1975 uhile operating'the (system at a flew reta of 4000 cfm a 15. I , . l i i i l i f "This surveillarae shall teclude the recirculating cherenel ffiter "eder ester," in the normal sentrol room sagsply filter train aning MISI 1530-1975 as a guide te verify },715 efficiency in removine freon tant gas. i , ! .c wa
- u. men ' \ a:W.
ncu. .- . ) :. ht-LA SALLE - Lat!T 2 3/4 7-6 Amendment Nr,. i ! SA! '.F - 1 - k I
7 ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS
- [NSERTC l
' Manually initiate flow through the control room and auxiliary electric equipment room recirculation filters and then verify that the control room and auxiliary electric equipment rooms are INSERT H
- Deleted.
4 l I j B-16 4
_________r.__ _ _ . _ _ _ - l
)
! l
- i. CONTAll# TENT SYSTIH1 4
i BASES ! 3 /4. 6.1 PRIMARY CONTAlletENT
<)_.
3/4.6.1.5 nrtrTED l ! 3/4.6.1.6 DRYWftt Als SUPPRESSION CHAMBER INTERNAL PRESSURE a i,. . The limitation on drywell and suppressi'on chamber internal presture ensure that the containment p6ak pressure of 3g.6 psig'does not exceed the
- design pressure of 45 psig during LOCA conditions or that the external i pressure differential does not exceed the design maximum external pressure
} differential of 5 psid. The limit of 2.0 psig for initial positive primary 1 containment pressure will limit the total pressure to 3g.6 psig which is less
- than the design pressure and is consistent with the accident analysis.
F 3 /4. 6.1. 7 DRYWEtt AVERARE AIR TEMPERATURE p j The limitation on drywell average air temperature ensures that the i containment peak air temperature does not exceed the design temperature of l 340*F during LOCA conditions and is consistent with the accident analysis, f 3/4.6.1.s DRYWFil AND SUPPRFitION CHAMBER PURRE SYSTEM i The drywell and suppression chamber purge supply and exhaust isolation i valves are required to be closed during plant operation except as required for l' : inerting, de-inerting and pressure control. Jhese valves have been j demonstrated capable of closing during a LOCATOR steamline break accident from c the full open position. 1 Yi W l ! ~ i i I l t i j i~ j LA SALLE - UNIT 2 B 3/4 6-2a AmendmentNo. 7 1 { 4
. . .-_.. _ .__ _ _ _ _ _ ._ _ _ __ _ _ . . . _ - ~ _ . . _ . _ _ _ . .
s ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERTI i During operations involving inerting, de-inerting and pressure control, i only the drywell or suppression chamber purge supply and exhaust ! Isolation valves may be open to prevent the creation of a bypass path ! between the drywell and suppression chamber. Creation of a bypass path , l between the drywell and the suppression chamber air space through the vent and purge lines would allow steam and gases from a LOCA to bypass the downcomers to the suppression poolin excess of design ! bypass leakage. 1 8 i 4 3 d I B-17 i
3/4.7 PLANT SYSTEMS BASES 3/4.7.1 CORE STaunay entu ING SYSTDI . sallIpMENT rnru ING WATER SYSTDtf l The OPERABILITY of the core staney cooling system - equipment cooling water systems and the ultimate heat sia 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.P CONTRO _ ROM Als AUXILIARY 51srTRIC EQUIPMENT annM Bathcracy FILTRA" ION SYS" M gg j F The OPERA 8ILITY of the emergency filtration systes),ensures control room and auxiliary electric equipment room 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 the rooms to 5 ren or less whole body, or its equivalent. This limitation is consistent with the requirements of Gemaral Design Criteria 19 of Appendix "A",10 CFR Part 50. Cumulative operation of the system with the heaters OPERA 8LE for 10 hours over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. 3/4.7.3 REACTOR CORE Itru ATION rnfW IM SYSTEM . The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of mactor 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 mode 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 prassurized. With the RCIC system inoperable, adequate core cooling is assured by the OPERABILITY of the HPCS system and justifies the specified 14 day out-of-service period. The surveillance requirements provide adequate assurance that RCICS will be OPERABLE when required. Althougi 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 detensine equivalent turbine / pump capabilities between test flow path and the vessel injection flow path. 1he pump discharge piping is maintained-full to prevent water hasunr. damage and to start cooling at the' earliest possible soment. The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water ( _)_ between the centerline of the pump discharge &nd the system high point vent. - LA SALLE - UNIT 2 8 3/4 7-1 Amendment No.
J ~ ^ ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS d i INSERT J
, which includes the control room and auxiliary electric equipment room
- recirculation filters, i
5 f n 4 4 j 4 e h B-18
~ _ - _ ___.__ -._
1 p AIBIINISTRATIVE CONTROLS I j o PLANT DPERATINC PhocFDURES AM) pommaMS -(Continued) E i the Initial Structural Integrity Tests were not within 2 years of each other. I ! The Onsite Review and Investigative Function shall be responsible for reviewing and approving chan j for Post Tensioning Tendons.ges to the Inservice Inspection Program 1
/
C1 The provisions of 4.0.2 and 4.0.3 are appitcable to the Tendon l / SurveillpePrograminsepetionfrequencies.- g 6.2.F QPrimary contai-t tankane Rate Tastina Fr sram ~ i ! 4 ~ A prograf shall be established to implement the leaksee rate tasting of the Option 8, as modified by approved exemptions. primary containment as This program shall be-in
- accordance with the guidelines contained in Regulatory Guide 1.163, "Perfomance-Based Containment Leak-Testing Prograa," dated September 1995.
4 loss of coolant accident, P, . is 39.6 psig.The peak calculated primar i primary containment air weight per day.TheL.,maximum allowable at P,, is 0.635% of prim Leakage rate acceptance criteria are: a. l Primary containment overall leakage rate acceptance criterion is $1.0 L L During p the first unit startup following testing in accordance with this., \ cgram,thelea ined. Type 8 for the e rate acceptance criteria are s 0.60 Type C tests, and s 0.75 L, for Type A L* tests. '
- b. Air lock testing acceptance criteria are:
! 1) I Overall air lock leakage rate is $0.05 L, when tested at 2 P,. i 2) j between the door seals is pressurized to 210 psig.For each d The provisions of specification 4.0.2 do not apply to the test fre \ specified in the Primary Containment Leakage Rate Testing Program quencies i The provisions of specification 4.0.3 are applicable to Leakage Rate Testing Program. 6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN I-The following actions shall be taken for REPORTABLE EVENTS:
- a. The Commiission shall ',e notified.and a Licensee Event Report j
! submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and
- b. Each REPORTABLE EVENT shall be reviewed pursuant to Specification 6.1.G.2.c(1).
{ Isen 'k' LA SALLE - UNIT 2 6-20a
- Amendment No.
1 i t
-- . ....- ...- - - - - - . - - - . . - . - - . - - _ ~ . _ - . - . . -
i i ! ATTACHMENT B l PROPOSED AMENDMENTS TO THE i LICENSE / TECHNICAL SPECIFICATIONS 4
- INSERT K i
j 8. Ventilation Filter Testina Proaram NFTP) i { 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, F dated March 1978, and conducted in general conformance with l ASME N510-1989. i The provisions of Specitit:ations 4.0.2 and 4.0.3 are applicable to the VFTP test frequencies. l 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 general conformance with Regulatory Guide 1.52, Revision 2, j and ASME N510-1989, at the system flowrate specified below
- ESF Ventilation Flowrate (cfm)
System SBGT System a 3600 and s 4400 CREF System a 3600 and s 4400 i l 1 i j. i B-19 i i i
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT K (Continued) i
- 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 general conformance with Regulatoly Guide 1.52,
- Revision 2, and ASME N510-1989, at the system flowrate specified below:
j ESF Ventilation Penetration and Flowrate (cfm) System System Bypass ~ SBGT System 0.05 % 2 3600 and s 4400 CREF System 0.05 % > 3600 and s 4400 CRRF System 2.0 % 218000 and s 28900 AEERRF System 2.0 % 214000 and s 19900
- c. Demonstrate for each of the ESF systems that a laboratory test of a semple of the charcoal adsorber, when obtained as 2 described in Regulatory Guide 1.52, Revision 2, shows the
, methyl lodido penetration less than the value specified below when tested at a temperature of 30*C, a relative humidity of 70 % and a face velocity as specified below in general conformance with ASME D3803-1989. ESF Ventilation Penetration Faco System Velo lty (fpm) SBGT System 0.5 % 40 CREF System 2.5 % 40 CRRF System 15.0 % 80 AEERRF System 15.0 % 80 B-20
ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT K (Continued)
- d. Demonstrate for each of the ESF systems that the pressure drop across the combined moisture separator, heater, prefilter, 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 Flowrate (cfm) System (inches wg) SBGY System 8 2 3600 and s 4400 CREF System 8 2 3600 and s 4400
- e. Demonstrate that the heaters for each of the ESF systems dissipate the electrical power specified below when tested in general conformance with ASME N510-1989. These readings shall include appropriate corrections for variations from 480 Volts at the bus.
ESF Ventilation Wattage (kw) System SBGT System a 21 and s 25 CREF System a id and s 22 i B-21
- ATTACHMENT C 1
2 ! LASALLE COUNTY NUCLEAR POWER STATION l UNITS 1 A14D 2 1
! EVALUATION OF SIGNIFICANT HAZARD CONSIDERATIONS
- FOR PROPOSED CHANGES TO i
i FACILITY OPERATING LICENSES l NPF-11 AND NPF-18 i APPENDIX A TECHNICAL SPECIFICATIONS l j VENTILATION FILTER TESTING PROGRAM J i l l l i 1 1
. . . - . - - . - - - - - .. - . - . .~.. .. .- -.. . - . . - . . - - - . - -
M i. 1 l ATTACHMENT C SIGNIFICANT HA"ARDS CONSIDERATION L Summary of the Proposed Technical Soecification Channes: 1 Commonwealth Edison Company (Comed) proposes to make the a following revisions to the LaSalle County Nuclear Power Station (LaSalle), ! Units 1 and 2, Technical Specifications (TSs): ! 1. Drvwoll and Supprpssion Chamber Purae System
! TS 3.6.1.8 and associated Bases will be revised to prohibit the simultaneous opening of the drywell and suppression chamber i purge system isolation valves;
[ 2. Ventilation Filter Testina Proaram !. The requirements of Standby Gas Treatment System (SBGTS) Technical Specification Surveillance Requirements (TS SRs) j 4.6.5.3.b, 4.6.5.3.c, 4.6.5.3.d.1, 4.6.5.3.d.3, 4.6.5.3.e, and 4.6.5.3.f will { be relocated to TS 6.2.F 8, Ventilation Filter Testing Program, i- ^ The requirements of TS SRs 4.7.2.b, 4.7.2.c, 4.7.2.d.1, 4.7.2.d.3, 4.7.2.e,4.7.2.f, and associated footnotes will be relocated to TS 6.2.F.8, Ventilation Filter Testing Program, and TS 6.2.F.8 will be added to describe the Ventilation Filter Testing i Program;
- 3. Other Control Room and Auxiliary Electric Eauloment Room
! Emeroency Filtration System Chanaes ! TS SR 4.7.2.a will be revised to requira flow through the control j room and AEER recirculation filters; - TS SR 4.7.2.d.2 vi!!! be revised to require the control room and
- AEER recirculation filterc to be online while the surveillance is
- being performed and that both the control room and AEERs are to i
be maintained at a positive pressure; i ! C-1 l t l
_ _ _ _ _ ._ _ _ . _ . _ _ _ _ _ . _ _ _ . . . _ - . _ . . _ . _ . _ . ~ . . . ~ . . _ . _ . _ _ _ 5 ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION o 4 TS 3.7.2 Bases will be revised to specifically identify the control
- room and AEER recirculation filters being required for system
- operability; '
and
- 4. Editorial Chanael TS 6.2.F.7 will be reformatted to be consistent with the remainder of TS 6.2.F. No technical changes will be made.
Comed has evaluated the proposed TS amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in Title 10, Code of Federal Regulations, Part 50, Section 92 (10 CFR 50.92), operation of LaSalie, Units 1 and 2, in accordance with the proposed amendment will not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluzted because:
- a. Drvwell and SuDDression Chamber Purae System The purpose of the drywell and suppression chamber purge system isolation valves is to mitigate the consequences of a design bases accident. Operation of these valves will have no effect on the probability of a design bases accident occurring.
The current TS 3.6.1.8 allows for the drywell and suppression chamber purge system isolation valves to be open simultaneously. In this condition, containment pressure and offsite dose during design bases accidents would be greater than previously evaluated. The proposed revision to TS 3.6.1.8 would prevent the simultaneous opening of the drywell and suppression chamber purge system isolation valves thus assuring that the consequences of design bases accidents previously evaluated are still bounding, , C-2 1
l ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION , i
- b. Ventilation Filter Testina Proaram The SBGTS and Control Room and AEER Emergency i Filtration System are designed to mitigate the radiological
- consequences of previously evaluated design bases i accidents. Operation and testing of these systems will have j no effect on the probability of a design bases accident occurring.
ll ! The proposed revisions associated with this change relocate
- the requirements for SBGTS and Control Room and AEER
! Emergency Filtrathn System filter testing from the current TS
- SRs to a new TS .sdministrative control program. The testing
- l. requirements are boing upgraded to the latest industry i standards. Filter testing in accordance with the proposed program will ensure that Title 10, Code of Federal j Regulations, Part 50 (10 CFR 50), Appendix A, General Design l Criteria (GDC) 19 and 10 CFR 100 limits are not exceeded.
- c. Other Control Room and Auxiliary Electric Eauipment Room f Emeroency Filtration System Channes
! The SBGTS and Control Room and AEER Emergency i Filtration System are designed to mitigate the radiological [ consequences of previously evaluated design bases
, accidents. Operation and testing of these systems will have
! no effect on the probability of a design bases accident j, occurring, j The proposed revisions associated with this change l acknowledge that the AEERs are required to be habitable l during design bases accidents. This is consistent with the plant's design bases. C-3 r ) i i 4
4 l ATTACHMENT C { SIGNIFICANT HAZARDS CO.,$1DERATION l
- d. EditoriaLCh*Anta l
l The proposed revisions to TS 6.2.F.7 reformat the 1 { requirement to estab'ish consistency with the remaintier of. 1 TS 6.2.F. There are no technical changes being proposed. 1 l Based upon the above, the proposed amendment will not increase
- the probability or consequences of any accident previously
- evaluated.
l
- 2) Create the possibility of a new or different kind of accident from l any accident previously evaluated because:
- a. Drvwell and Suppression Chamber Purae System No new plant equipment is being installed, and use of
[ currently installed plant equip.uont is not afiscted by this ! proposed change. The proposed revision to TS 3.6.1.8 provides additional limitations on the opening of the drywell and suppression chamber purge system isolation valves, j b. Ventilation Filter Testina Proaram i. No new plant equipment is being installed, and use of
- currently installed plant equipment is not affected by this i proposed change. These propcaed revisions will i demonstrate operability of the Control Room and AEER Emergency Filtration System using the latest industry j standards.
! c. Other Control Room and Auxiliary Electric Eauloment Room
- Emeraency Filtration System Channes Np new plant equipment is being installed, and use of currently installed plant equipment is not affected by this proposed change. These proposed revisions will demonstrate habitability of the AEER by impcsing operability requirements on the AEER recirculation filter units.
C-4
i ATTACHMENT C l SIGNIFICANT HAZARDS CONSIDERATION f '.
- d. Editorial C_hannes The proposed revisioits to TS 6.2.F.7 reformat the j requirement to establish consistency _with the remainder of j TS 6.2.F. There are no t6chnical changes being proposed. ,
i
- Based upon the above, the proposed change will not create the j possibility of a new or different kind of accident or transient j previously evaluated.
1 l 3) Involve a significant reduction in the margin of safety because:
- a. Drywell and Suppression Chamber Purae System
) i The current TS 3.6.1.8 requirements are non-conservative j with respect to the assumptions used when evaluating steam [ bypass of the suppression chamber; specifically, a maximum i allowable leakage area of 0.03 square feet with the only j credible leakage path was assumed to be suppression j chamber vacuum breaker valve seat leakage. This proposed ! revision to TS 3.6.1.8 will make the TS requirements 2 consistent with those assumptions. ! b. Ventilation Filter Testina Proaram i
- j. These proposed revisions will ensure operability of the
- Control Room and Auxillary Electric Equipment Room (AEER) i Emergency Filtration System using the latest industry
- standards. Filter testing in accordance with the proposed j program will ensure that GDC 19 and 10 CFR 100 limits are L not exceeded.
J i i C-5 i i 4 i
l l ATTACHMENT C
- SIGNIFICANT HAZARDS CONSIDERATION i
- c. Other Control Room and Auxiliary Electric Eauloment Room Emeroency Filtration System Channes 4 These proposed revisions will ensure operability of the i
control roon and AEER Emergency Filtration System by demonstrating system performance with the control room and l AEER recirculation filter units to ensure GDC 19 limits are not
- exceeded.
- d. Editorial Channes
! The proposed revisions to TS 6.2.F.7 reformat the l requirement to establish consistency with the remainder of } T.S 6.2.F. There are no technical changes being proposed. ! Based on the above, the proposed TS change does not involve a i significant reduction in the margin of saf3ty. Guidance has been provided in " Final Procedures and Standards on No Significant Hazards Considerations," Final Rule,51 FR 7744, for the application of standards to license change requests for determination of the existence of significant hazards considerations. This document provides examples of amendments which are and are not considered likely to involve significant hazards considerations. These proposed amendments most closely fit the example of a change which either result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where
- the results of the change are clearly within the acceptance criteria with respect to the system or component specified in the Standard Review Plan.
This proposed amendment does not involve a significant relaxation of the criteria used to establish safety limits, a significant relaxation of the bases for the limiting safety system settings or a significant relaxation of the bases for the limiting conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(c), the proposed change does not constitute a significant hazards consideration. C-6
i l ATTACHMENT D LASALLE COUNTY NUCLEAR POWER STATION UNITS 1 AND 2
- ENVIRONMENTAL ASSESSMENT STATEMENT l FOR PROPOSED CHANGES TO I
j FACILITY OPERATING LICENSES j NPF-11 AND NPF-18 l l APPENDIX A TECHNICAL SPECIFICATIONS VENTILATION FILTER TESTING PROGRAM i i Q i i i 4 4 i i I
ATTACHMENT D ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW Commonwealth Edison hat, evaluated the proposed amendment against the criteria for identification of licensing and regulatory actions requiring l
- environmental assessment in accordance with 10 CFR Part 51.21. It has l been determined that the proposed changes meet the criteria for categorical exclusion as provided for under 10 CFR Part 51.22(c)(9). This l conclusion has been determined because the changes requested do not pose significant hazards considerations or do not involve a significant increase in the amounts, and no significant changes in the types of any effluents that may be released off-site. Additionally, this request does not i
involve a significant increase in individual or cumulative occupational radiation exposure. 1 4 i f 1 1 1
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