ML19331E126
| ML19331E126 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/08/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331E124 | List: |
| References | |
| NUDOCS 8009050531 | |
| Download: ML19331E126 (22) | |
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UNITED STATES y))p(
g NUCLEAR REGULATORY COMMISSION
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 56 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 21, 1975, supplemented by letters of December 19, 1978 and April 28, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reas J.uole assurcnce (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i
have been satisfied, l
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800905063/
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective ar of September 1,1980.
FOR THE NUCLKAR REGULATORY COMMISSION i,
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f Operating Reacto Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 8. 1980 i
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UNITED STATES s.,
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. DPR-48 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 21, 1975, supplemented by letters of December 19, 1978 and April 28, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
<'I i
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and ~ paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 53, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of September 1,1980.
FC THE NUCLE R REGULATORY COMMISSION
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Operating Reactor ranch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 8, 1980 s
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 56 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT N0. 53 TO FACILITY OPERAilNG LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:
Remove Pages Insert Pages iv iv ix ix x
X 180 180 1 81 181 182 182 194 194 244 244 244A 244A 245 245 249 249 281 281 282 282 284 284 285 285 286 286 288 288 l
1 S
Table of Contents (Continusd)
SURVEILLAS !;
LIMITING CONDITION POR OPERATION REQUIREM PAGE 3.13 Refueling Operations 4.13 243 3.13.1 Core Reactivity 4.13.1 243 l 3.13.2 Protection From Damaged Spent Fuel 4.13.2 244 3.13.3 Containment Status 4.13.3 245 3.13.4 Radiation Monitoring Bases 4.13.4 240 2 46 3.13.5 Refueling Equipment Checkout 246 3.13.6 Refueling Equipment Operability 246 3.13.7 Spent Fuel Pit Cooling Systems 247 3.13.8 Fuel Inspection Program 3.14 Plant Radiation Monitoring 4.14 250 4.15 255 3.15 Auxiliary Electrical Power System 3.16 Environmental Radiological Monitoring Program 4.16 275 Bases 4.17.1 281 3.17.1 Ventilation Bases 3.17.2 Aircraft Fire Detection 4.17.2 283 4.18 289 3.18 Steam Generator Bases 4.19 292 3.19 Failed Fuel Monitoring 4.21 295D 3.21 Fire Protection 3.22 Shock Suppressors(Snubbers) 4.22 295W 296 5.0 Design Features 296 5.1 Site 296 5.2 Reactor Coolant System 296 5.3 Reactor Core 296 5.4 Containment System 298 5.5 Fuel Storage 299 5.6 Seismic Design iv Amendment No. 56, Unit 1 Amendment No. 53, Unit 2 l
LIST OF TABLES (Continued)
PAGE TABLE 4.8-1 Centrifugal Charging Pump System 185 186 4.8-2 Safety Injection Pump System 4.8-3 Residual Heat Removal Pump System 187 188 4.8-4 Accumulator Tanks 189 4.8-5 Component Cooling Pump System 190 4.8-6 Service Water Pump System 192 4.8-7 Hydrogen Control System 4.9-1 Isolation Seal Water System 203 4
4.9-2 Penetrat'.on Pressurization System 204 4.9-3 Containment Isolation valves 205 4.9-4 Main Steam Isolation Valves 208 4.11-1 Radioactive Liquid Waste Sampling and Analysis 226 236 4.12-1 Pathways of Release 4.12-2 Radioactive Gaseous Waste Sampling and Analysis 237 4.12-3 Effluent Gaseous Waste Monitors 239 4.14-1 Process and Internal Monitoring 252 4.15-1 4160 Volt Engineer Safeguard Bus Feeds 270 1
4.16-1 Environmental Radiological Monitoring Program 276 l
4.17-1 HEPA/ Charcoal Filter Systems Surveillance Requirements 284 Amendment No. 56, Unit 1 ix Amendment No. 53, Unit 2
_... ~.. _
- m. _.. _ _._.
O LIST OP._ TABLES (Continued)
TABLE PAGE l
4.17-2 Particulate Filter System Surveillance Requirements 286 4.19-1 Failed Fuel Monitoring Instruments 295 6.2.1 Protection Factors for Respirators 310 6.3.1 Boundary Doors for Plood Conditions 332 6.6.1 Reporting of Radioactivity in the Environs 328 9
6.6.2 Special Reports 328a J
1 x
Amendment fio. 56, Unit 1 Amendment fio. 53 Unit 2
r LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.6.8 Hydroge n control systems 4.8.8.
Hydrogen control sys tems (Table 4.8-7)
A.
Hydrogen purge fans A.
liydrogen purge fans 1.
The two hydrogen purge f an systems 1.
The hydrogen purge fans shall be shall be operable whenever the started manually from the control reactor is critical except as l
room every 31 days.
Performance will be cceeptable if the fan spec i fied in 3.6.8.A.2.
starts upon actuation and operates 2.
From and af ter the date that one for 15 minutes, of the hydrogen purge fan systems is made or found to be inoperable 2.
When it is determined that one of for any reason, reactor operation the two hydrogen purge fan systems including recotery from an in-is inoperable, the remaining advertent trip is permissible only systems shall be demoristrated to during the succeeding 15 days pro-be operable immediately and daily vided that during those 15 days the thereafter.
one remaining system shall be operable.
3.
Not applicable.
3.
If these conditions cannot be met, the reactor snall be brought to the hot shutdown condition within four hours.
After a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the hot shutdown condition, if the system is not operable, the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
180 Amendment No. 56, Uni '
Amendment No. 53, Uni: 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.8.8.A.
4.8.8.A.
4.
Hydrogen purge filters shall 4.
For each HEPA or charcoal I
be periodically tested.
filter, at least once per 18 months or (1) after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal ad-sorber operation or (2) after any structural mainten-ance of the filter housings or (3) following painting, fire, or chemical release in any ventilation zone com-municating with the systen, or (4) after each completo or partial replacement of the filter bank, surveillance will be performed per Table 4.17-1.
B.
Hydrogen recombiners l
B.
Hydrogen recombiners g
1.
The two hydrogen recombiner sys-1.
The hydrogen recombiner sys-tems shall be operable whenever tems shall be functionally the reactor is critical except tested every six months.
as specified in 3.8.8.B.2.
Performance will be accepta-ble if the heaters energize 2.
From and after the date that one and bring the system to oper-of the hydrogen recombiner sys-ating temperature, the blower tems is made or found to be in-works, and the instruments operable for any reason, reactor indicate proper operation, operation, including recovery from an inadvertent trip, is 2.
When it is determined that permissiable only during the suc-one of the two hydrogen recom-ceeding 15 days provided that biner systems is inoperable, during those 15 days, the one the remaining system shall be remaining system shall be opera-demonstrated to be operable immediately.
ble.
181 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.8.8.B 3.
If these conditions cannot be 4.8.8.B.
3.
Not Applicable.
met the reactor shall be brought to the hot shutdown condition within four hours.
After a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the hot shutdown condition, if the system is not operable the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
182 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2 I
)
(
The availability of the systems is demon-into the primary coolant system following strated by immediately demonstrating the a loss-of-coolant accident and are based l
operability of the components redundant to on the values used for the accident analysis.,
the failed one, as well as the operability (4) of the inter-related systems and the ntandby AC and DC power supplies that feed The limits for the accumulators, and their them.
The continued availability of these pressure and volume assure the required
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components during the repair period is amount of water injection with the required I
demonstrated by repeating these tests daily.
boric acid concentration following a loss-
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of-coolant accident, and are based on the Assuming a reactor has been operating at values used for the accident analyses. (4) full rated power for at least 100 days, the magnitude of the decay heat decreases after The five component cooling system pumps initiating hot shutdown.
Thus, the require-and three heat exchangers are located in the ment for core cooling in case of a postu-Auxiliary Building and are a shared system lated loss-of-coolant accident while in the between Units I and II.
The components are hot shutdown condition is significantly accessible for repair after a loss-of-coolant reduced below the requirements for a pos-accident.
During tho recirculation phase tulated loss-of-coolant accident during following a loss-of-coolant accident on a power operation.
Putting a reactor in unit, only one component cooling pump and the hot shutdown condition significantly heat exchanger is required for minimum safe-reduces the potential consequences of a guard of that unit.
Therefore, a minimum loss-of-coolant accident, and also allows requirement of 4 component cooling pumps and more free access to some of the engineered three heat exchangers for two operating units safeguards components in order to effect provides sufficient redundancy. (5) repairs A total of six service water pumps are Failure to complete repairs within an installed; only one servi e water pump is odditional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of going to the hot required immediately following a postulated shutdown condition is considered indicative loss-of-coolant accident. (6) of a requirement for major maintenance and therefore in such a case, the reactor is to The hydrogen purge system is designed to be put into the cold shutdown condition.
purge combustible gases from the containment following a loss-of-coolant accid ent (7)(8).
The limits for the boron inj : tion tank The containment hydrogen sampling system is and refueling water storage tank insure used to determine the effectiveness of this the required amount of water with the system. The instrumentation, equipnent and proced-required boron concentration for injection ures for the tests which are required on the ventila-tion filter system will generally conform to the recommendations of ANSI N510-1975.
194 Amendment No. 56 Unit 1 Amendment No. 53 Unit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMEN P 3.13.1.B.
fuel is in the reactor, neutron 4.13.1 flux shall be monitored con-tinuously by at least one source range neutron monitor with both visual and audible indication.
C.
The movement of an irradiated C.
Not applicable, fuel assembly in the reactor core shall not begin until the reactor has been subcritical for a period of at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
D.
A least one RH,R pump and heat D.
The operation of at least one RHR exchanger shall be in operation pump and heat exchanger shall during a refueling operation, be verified once a shift.
E.
Direct communication between the E.
Communication between the control control room and containment room and the containment shall shall be operable, be verified before any alteration of the reactor core begins.
F.
A licensed fuel handling foreman or licensed senior reactor oper-F.
Not applicable.
ator shall be present at the reactor cavity during any move-ment of fuel within the contain-ment.
3,13.
2.
Protection from Damaged Spent Fuel 4.13
- 2. P30tection from Damaged Spent Fuel A.
During irradiated fuel movement A.
The charcoal adsorber mode of or crane operation with loads operation of fuel building over irradiated fuel in the fuel exhaust system shall be de-building, the fuel building monstrated to be operable:
exhaust system shall be:
244 Amendment No 56, Unit 1 Amendment No. 53, Unit 2
SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION 3.13.2.
1.
Operating with ventilation flow 4.13.2.
A.
1.
When operability is required by through the HEPA and charcoal Specification 3.13.2.A.1, by filters if there is any irradiated observing and documenting at fuel stored in the pool with less least once per shift, that the than 60 days decay time.
ventilation system is operating as required by Specification 3.13.2.A.
2.
When operability is required by 2.
Operable with automatic initiation of flow through the HEPA filters Specification 3.13.2.A.2, the and charcoal absorbers upon detec-following shall be done at least tion of hiah radiation at the fuel once per 31 days:
1)
Place the pool if all irradiated fuel stored Fuel Building Ventilation System in the pool has 60 days or greater in the Fuel Handling Mode for a decay time since irradiation minimum of 15 minutes, 2)
Verify ceased.
If automatic actuation flow through the HEPA and charcoal is inoperable, the system shall be adsorber train, 3)
Verify the manually placed in the " charcoal Fuel Building is maintained at \\
adsorber mode".
inch of water negative pressure with respect to the atmosphere.
B.
Not Applicable B.
If requirements of Specification 3.13.2.A., above, cannot be met, irradiated fuel movements or crane operation with loads over irradiated fuel shall be terminated after first, if applicable, placing loads in a safe condition.
Amendment No. 56, Unit 1 244A Amendment No. 53, Unit 2
LIMITING CONDITION FOR OPERATION SURVEIIIANCE REQUIREMENT 3.13.2 C.
Ventilation filters for the fuel building 4.13.2 C.
For each HEPA or charcoal filter, at least once including charcoal adsorbers and the auto-per 18 months or (1) after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of matic actuation of the charcoal filter system charcoal adsorber operation or (2) after any shall be periodically tested, structural maintenance of the filter housings -
or (3) following painting, fire, or chemical release in any ventilation zone connonicating with the system, or (4) after each complete or partial replacement of the filter bank, surveillanet will be performed per Table 4.17-1.
1.
Verify that on a high radiation test signal the system autcenatically starts (unless already in operation) and directs its exhaust flow through the HEPA filters and charcoal adsorber banks. If automatic actuation is inoperable the system shall be manually placed in the charcoal adsorber mode.
3.13.3 Containment status 4.13.3 Containment status A. During refueling ooerations contaiment integrity A.
Containment door status shall be verified once (See section 1.0.C) shall be maintained as a shift, specified in section 3.9.5 except as specified in 3.13.3.B.
B. The equipnent hatch or both doors on the P.
Peactor coolant boron concentration and Tavg personnel hatch may be opened during the re-shall be verified once a shift when the equipnent fueling operation provided the shutdown margin hatch is open or both doors on the personnel is maintained equal to or greater than 10%
hatch are open.
AK/K and Tavg is maintained at or less than 140 P.
Amendment No. 56, Unit 1 245 Amendment No. 53; Unit 2
Bnsis:
4.13 The surveillance specified ensures that the required condition of core reactivity are met and maintained during core alterations.
The surveillance of the containment, ventilation system, and radiation monitors ensures the availability of these systems such that the limits of 10CFR100 will not be exceeded during the postulated fuel drop accident.
The instrumentation, equipment and procedures for the tests which are required on the ventilation filter system will generally conform to the recommendations of ANSI N510-1975.
1 Amend ent No. 56, Unit 1 249 Amendmert No. 53, Unit 2
SURVEILLANCE REQUIREMENP LIMITING CONDITION FOR OPERATION 3.17 Ventilation 4.17 Ventilation 3.17.1 Applicability 4.17.1 Applicability Applies to the testing of particulate Applies to the testing of particulate filters and charcoal adsorbers in filters and charcoal adsorbers in safety-safety-related air filtration systems.
related air filtration systems.
Objective Objective To verify that leakage efficiency and To verify that leakage ef ficiency and iodine removal efficiency are within iodine removal efficiency are within acceptable limits.
acceptable limits.
Specification Specification Safety-related ventilation filters shall be periodically tested.
A.
The control room makeup air charcoal A.
The control room makeup air charcoal adsorber system shall be operable adsorber system shall be demonstrat-except as specified in 3.17.1.B.
ed operable.
The control room char-coal booster fans shall be started from the control room every 31 days.
Performance will be acceptable if the fan starts upon actuation and directs air through the charcoal adsorbers and operates for 15 min-utes.
B.
From and after the date that the.
B.
Not Applicable, control room makeup air charcoal ad-sorber system is made or found inoper-able for any reason restore the system to operable status within 7 days or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within s
the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
281 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2 i
)
SURVEILLANCE REQUIREMENP LIMITING CONDITION FOR OPERATION 3.17.1.
C.
The control room makeup, drumming 4.17.1.
C.
For each IIEPA or charcoal filter, at least once per 18 months or (1) station and miscellaneous vents charcoal filter systems shall be after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation or (2) after any periodically tested.
structural maintenance of the filter housings or (3) following painting, fire, or chemical release in any ventilation zone communicating with the system, or (4) after each complete or partial replacement of the filter bank, surveillance will be performed per Table 4.17-1.
D.
IIEPA filters shall be periodically D.
The IIEPA filter banks specified in Table 4.17-2 shall be tested at tested.
least once per 18 months.
Acceptance criteria shall be per Table 4.17-2.
282 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2
FILTER HYDR 0 GEN CONTROL ROOM DRUMMING HISCELLANEOUS PARAMETER PURGE HRI/At%ILUJtY MAKEUP STATION VENTS 1RV046 OAV038 OAV040 OPV005 OPV005 OAV043 OAV069 1RV047 OAV039 OAV041 UPSTREAM DOWNSTREAM BANKS 2RV046 2RV047
- of Elements 3
42 91 8
6 16 8
per Bank Acceptance Criteria
- a) In-place HEPA 2 99%
2 99%
27 99%
2 99%
j> 99%
2_99.95%
2199.95%
> 99.95%
> 99.95%
j> 99.95%
b) In-place Charcoal 2 99.95%
c) Flow rates (CFM) 360 + 10%
16500 + 10%
2000 + 10%
4000 + 10%
2000 + 10%
d) System Pressure Drops (inches of
<6
<6
<6
<6
<[
6
<[
6 Water)
Laboratory Analyses **
e 2 99%
el 95 %
e 2t 99%
e) 90%
ejt90%
for at at at at at 0
0 0
Charcoal Adsorbers T il900 Ti l25 F T1190 P T 1190 F Tjt190 F RH170%
RHjt95%
RHjt 70%
RH]t95%
RH2 95%
Laboratory Analysis:
See page 285 Acceptance Criteria:
See page 285 HEPA/ Charcoal Filter Systems Surveillance Requirements Table 4.17-1 284 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2
Footnotes from page 284
- Acceptance Criteria a)
In-Place HEPA:
These filter banks will remove greater than or equal to the specified amount of dioctyl phthalate (DOP) when tested "in-place".
b)
In-Place Charcoal:
These adsorbers will remove the specified amount of halogenated refigerant test gas when tested "in-place".
c and d)
Flow Rates and Pressure Drops:
The flow rates and pressure drops apply to the complete HEPA/ Charcoal System.
The total bypass flow of the sytem to the facility vent, including leakage through the system diverting valves, is less than or equal to one percent.
Laboratory Analysis At least two carbon samples, one from each of the specified charcoal adsorbers, will be analyzed to verify the designated removal efficiency, e, of an activated methyl iodine at the specified temperature, T, and relative humidity, RH.
The carbon samples will be prepared by emptying one bed from a removal adsorber tray, mixing the adsorbent thoroughly and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.
Instrumentation, equipment and procedures for carbon samples tested at the laboratory will generally conform to the recommendations in ANSI N510-1975.
The Control Rocm make-up efficiency, e, is as stated in answer to Question 9.8 in Amendment No.
17 of the Zion FSAR.
The Hydrogen Purge efficiency, e, is as stated in answer to Question 14.2 in Amendment No. 20 of the Zion FSAR.
HEPA/ Charcoal Filter Systems Surveillance Requirements Table 4.17-1 (continued) 285 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2
s Filters Surveillance Recuirements Number Frequet.cy Acceptance Criteria System Banks of Location (months)
(% DOP Removed)
Elements Auxiliary OAV029 42 Fan Room, 642' 18
-> 99%
Building Exhaust OAV030 42 Pan Room, 642' 18
> 99%
OAV031 42 Pan Room, 642' 18
> 99%
OAV032 42 Fan Room, 642' 18
> 99%
OAV033 42 Pan Room, 642' 18
> 99%
OAV034 42 Fan Room, 642' 18 2 99%
Cubicles OAV035 24 Fan Room, 642' 18
> 99%
Exhaust OAV036 24 Fan Room, 642' 18
> 99%
OAV037 24 Fan Room, 642' 18 2 99%
Inst.Calib.
OAV042 1
Col. L-14, 592' 18
> 99%
Room llot Lab OOV048 6
Purge Room 2, 617' 18
> 99%
Exhaust Decon OOV0ll 2
Pan Room, 617' 18
> 99%
Room Exhaust Containment 1RV030 42 Purge Room 1, 617' 18
-> 99g Purge Exhaust 2RV030 42 Purge Room 2, 617' 18
> 99g Particulate Filter Sitrveillance Requirements Table 14.17-2 286 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2
Basis many years even under continuous flow conditions.
A demonstration of effi-4.17 The off-site dose calculation for LOCA and ciency per table 4.17-1 will assure b-fuel handling accidents assume a 90%
that the required capability of the iodine removal efficiency for the air filters is met or exceeded.
In addi-passing through the charcoal filters, tion, the chemical analysis tests of with the' exception of the hydrogen purge iodine removal capability will ensure filters which assume a 99% efficiency.
(1) early detection of conditions leading The system components are not subject to to filter degradation. The instrumentation, rapid deterioration, having lifetimes of equipment and procedures for the tests which are required on the ventilation filter system
'will enerall; cen'e m to the rece m ndations of ANSI N510-1975.
U) FSAR Answer to Question 14.2 l
288 Amendment No. 56, Unit 1 Amendment No. 53, Unit 2
-