ML20069N320

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Proposed Tech Specs Adding -89 After ASTM D3803 in Testing Requirements Specified for SGTS & MCR Filter Sys Charcoal & Changing Test Temp for Testing SGTS Charcoal from 80 C to 30 C
ML20069N320
Person / Time
Site: Clinton Constellation icon.png
Issue date: 06/16/1994
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20069N306 List:
References
NUDOCS 9406220339
Download: ML20069N320 (8)
v • d • e


Text

. .

Attachment 2 to U-602302

. LS-91-023 Page 1 of 6 Current Technical Specifications Markup l

l 9406220339 940616 PDR ADOCK 05000461 P PDR

Attachment 2

' M

LS-91-023 CONTAINMENT SYSTEMS Page 2 of 6

.STAfidBY GAS TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.3 Two independent standby gas treatment subsystems shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and *.

ACTION:

a. With one standby gas treatment subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days, or:

1

1. In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN within f 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 />. 1

\ l l 2. In OPERATIONAL CONDITION *, suspend handling of irradiated fuel in j the secondary containment, CORE ALTERATIONS and operations 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 Specification 3.0.3 are not applicable. 1 SURVEILLANCE REQUIREMENTS 4.6.6.3 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 heaters OPERABLE.
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 j or chemical release in any ventilation zone communicating with the subsystem by:

l l

l iIdsWiWidiTGd fuel is being handled in the secondary containment and during CORR l ALTERATIONS and operations with a potential for draining the reactor vessel. j CLINTON - UNIT 1 3/4 6-38 Amendment No. 68

Attachment 2' to U-602302 LS-91-023

1. Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses 1 the test procedure guidance in Regulatory Positions C.S.a C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978*, and the system flow rate is 4000 cfm 10%.
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 1.52, Revision 2, March 1978*, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978*, for a methyl iodide

-hg I penetr t on of less than 0.175%; when tested in accordance with ASTM

.ethods, with the following parameters:

( D380 a) Bed Depth - 4 inches b) Velocity 10 lom_

c) Temperature Relative Humidity - -

y =

d) and

3. Verifying a subsystem flow rate of 4000 cfm 10% during system operation when tested in accordance with ANSI N510-1980.
c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber 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*, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978*,

for a othyl iodide penetration of less than 0.175%; in accordance with ASTM D380 ethods, with the following parameters:

a) Bed Depth - 4 inches b) Velocity - 40 fem -

c) Temperature,dity(Q.-]}_ ll d) Relative Humi - nn ThisT 8510-1980 shall be used in place of ANSI H510-1975 as referenced in Regulatory Guide 1.52, Revision 2, March 1978.

3/4 6-39 Amendment No. M , 68 CLINTON - UNIT 1

At tachment 2 No Cha nges , to uow23n2 For TrSorm<xwon Org iO4Tr s Pl Af1I J Y.S Ilf:1%

_3L4,L 7.19fiiR01 A00f1 VI fil ll AllOf[JYS1f fi f 1IMIIIf1G CONDIIloft iOR OPlRAT10N 3.7.2 Iwo independent Control Room Ventilation Systems shall be OPERABLE.1 APPL. ICAlU t .I T Y : OPlRAllot1AL C0t101TIONS 1, 2, 3, and

  • AC110th
a. In OPIRAT10t1Al C0t1Dil10N 1, 2 or 3 with one Control Room Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT SIIUTDOW11 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 C010 SHUIDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In OPERAIIONAl C0t1D111011 *-
1. With one Control Room Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days. Otherwise, immediately initiate and maintain operation of the OPERABLE system in the high radiation mode of operation or suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.4 are not applicable for entry into OPERA 110NAL CONDITION 4 or S.
2. With both Control Room Ventilation Systems inoperable, immediately suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
3. ihe provisions of Specification 3.0.3 are not applicable.

SURVElli ANCE RIQUIRfMf NTS 4.7.2 Each Control Room Ventilation System shall be demonstrated OPERABLE:t

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal.to 86*F.
b. At least once per 31 days on a STAGGERED lEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the makeup filter system operates continuously 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 operating; and with flow through the recirculation charcoal adsorber for at least 15 minutes.
  • During movement of irradiated fuel assemblies in the primary or secondary containment, during CORI AlTERA110NS, or during operations with a potential for draining the reactor vessel.

1 Automatic transfer to the chlorine mode is not required when chlorine containers having a capacity of 150 pounds or less are stored 100 meters or more from t he cont rol room or its fresh air inlets.

CllN10N UNil 1 3/4 /-3 AMillDMitil fio. 8?

Attachment 2 to U-602302

~ LS-91-023 Par,c 5 of 6

_P.LAt1T SYSTEMS CONTROL ROOM VENTILATI0ft SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.7.2 (Continued)

c. At least once per 18 months or (1) after any structural maintenance on the makeup or recirculation HEPA filters or charcoal adsorbe communicating with the makeup or recirculation filter system by:
1. Verifying that the makeup filter system satisfies the in place penetration and bypass leakage testing acceptance crite t C.S.a, C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2 March i

1978^, and the system flow rate is 3000 cfm i 10%.

2. Verifying that the recirculation filter system satisfies bypass leakage testing acceptance criteria of less than 2% total bypass and uses test procedure guidance in Regulatory Positions C.S.a and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978*, and the system l flow rate is 64,000 cfm i 10%.
3. Verifying, within 31 days after removal, that a laboratory analysis l of a representative carbon sample obtained in accordance with Regula- '

meets the laboratory testing criteria of Regulatory P Regulatory Guide 1.52, Revision 2, March 1978*, for a methyl iodide penetration of less than 0.175% for stem makeup filter system carbon ad-carbon adsorber when sorber and 6% for recirculation filter tested; in accordance with ASTM D380 49 ethods, with the following parameters:

Make Up Filter System a) Bed Depth 4 inches 40 fpm b) Velocity c) Temperature 30 C d) Relative Humidity - 70%

Recirculation Filter System a) Bed Depth - 2 inches ]

l b) Velocity - 80 fpm c) Temperature - 30 C 70%

d) Relative Humidity f'

4. Verifying flow rate of 3000 cfm i 10% for the makeup l tion when tested in accordance with ANSI N510-1980.

as referenced in shall be used in place of ANSI N510-1975

^ ANSI H510-1980 Regulatory Guide 1.52, Revision 2, March 1978.

3/4 7-4 CLINTON - UNIT 1

Attachment 2

  • to U-602302 LS-91-023 Page 6 of 6 plat (T SYSTEMS C0f(TROL ROOM VEllTILATIOff SYSTEM SURVEILLANCE REQUIREMEt(TS JContinued) 4.7.2 (Continued)
d. Af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying within 31 days af ter removal, that a laboratory analysis of a representative ~

carbon sample obtained in accordance with Regulatory Position C16.b of Regulatory Guide 1.52, Revision 2, March.1978^, ocets the laboratory test-ing criteria of Regulatory Position C.6.a of Regulatory Guide 152, Revi-sion 2, March 1978*, for a methyl iodide penetration of less than 0.175%

i for the makeup filter system carbon adsorber and 6% for the recirculatio I filter system carbon adsorber when tested; in accordance with ASTM D3803  !

{

methods, with the following parameters.

Hake Up Filter System ,

a) Bed Depth - 4 inches-b) Velocity - 40 fpm I c) Temperature - 30 C d) Relative Humidity - 70%

Recirculation Filter System a) Bed Depth - 2 inches b) Velocity - 80 fpm c) Temperature 30 C d) Relative Humidity -

70%

e. At least once per 18 months by:
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Vater Gauge while operating the makeup filter system at a flow rate of 3000 cfm i 10%.
2. Verifying that on a high chlorine actuation ** and a manual initia-tion test signal, the system automatically ** switches to the chlorine mode of operation and the dampers close within 2 seconds.***

3 Verifying that the control room leak rate is limited to < 4000 cfm i 10% at > 1/8-inch Water Gauge (V.G.) with respect to a3facent areas.

4. Verifying that on a smoke mode actuation test signal, the system automatically switches to the sinoke mode of operation at a flow rate less than or equal to 64,000 cfm 10%.

l

5. Verifying that on a high radiation actuation test signal, the system J automatically switches to the high radiation node of operation and l

^ ANSI N510-1980 shall be used in place of ANSI NS10-1975 as referenced in ,

Regulatory Guide 1.52, Revision 2, March 1978. l

containers having a capacity of 150 pounds or less are stored 100 meters from the control room or its f resh air inlets.

"*This specification is not applicable af ter all chlorine containers having a capacity of 100 pounds or greater are removed from the. site including the chlorine containers located at the site sewage treatment plant. 1 3/4 7-5 Amendment No.12 CLINTON - UNIT 1

\

' Attachment 3 '

to U-602302 LS-91-023 Page1of2 Current Teclinical Specifications BASES Markup

Attachment 3

. to U- 6023u2

. LS-91-023 3&7 pl AtlT_ SYSTEfiS Page 2 of 2 BASES 3/4.11 SilVIDOWN SERVICE WATER SYSTEM The OPERABILITY of the shutdown service w'ater system ensures that sufficient cooling capacity is available forThe continued operation redundant of safety-related cooling capacity of these sys-equip-ment during accident conditions.

tems, assuming a single failure, is consistent with the assumptions used in the accident analyses within acceptable limits.

The ultimate heat sink (UHS) specification ensure that sufficient cooling capacity is available for continued operation of safety-related equipment The for at least 30 days to permit safe shutdown and cooldown of the reactor.

surveillance requirements ensure that quantities maintained are consistent with the assumption used in the accident analysis as described in the USAR and the guidance provided in Regulatory Guide 1.27, January 1976. i

)

3/4.7.2 CONTROL ROOM VENTil ATION SYSTEM The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for Theoperations OPERABILITY personnel of during and following all design basis accident conditions.

this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent "A",

with the requirements of General Design Criterion 19 of Appendix Surveillance testing provides assurance that system and component 10 CFR 50. ry ecifications for performances continue to be in accordance with perf 50, 1980 Continuous l Clinton Unit 1, including applicable parts of ANSI ours during each operation of the system with the heaters OPERABLE of moisture on the adsorbers

'or 131 day period is sufficient to reduce the buildup and llEPA filters. The specified heater dissipatiin is based on a bus voltage of 460 volts. Ileater test results shall be adjus ed to account for actual bus voltage, bl510-19@

3]4.7.3 REACTOR CORE ISOLATION COOLING SYSTEf1 The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat j

sink and the loss of feedwater flow to the reactor vessel without requiring The RCIC actuation of any of the Emergency Core Cooling System equipment.

system150ispsig.

exceeds conservatively required to be OPERABLE whenever reacto pressure core cooling systems can provide adequate core cooling for events requiring the RCIC system.

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 emergency cor'e cooling when the reactor is pressurized.

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.

8 3/4 7-1 letter dated 6/29/93 CllNTON - UNIT 1

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