ML20054C705
| ML20054C705 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/07/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054C658 | List: |
| References | |
| NUDOCS 8204210526 | |
| Download: ML20054C705 (20) | |
Text
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FACILITY OPERATING LICENSE NO.
DPR-73 f
DOCKET NO. 50-320 Replace the following pages of Appendix "A" Proposed Technical Specifications with the enclosed pages as indicated.
The revised pages contain vertical lines indicating the area of change.
Pages 3.3-8 3.3-9 3.3-11 3.5-1 3.6-2 3.74
.G.7-5
.3.7-7 r3.9-1 B 3/4 6-2 5-1 6-3 4.1-2 4.3-7 4.3-8
~4.6-1 6 4.6-2 4.6-3 8204210526 820419 PDR ADOCK 05000300 0
-,,w.-,.,-,,s.-..
c_.
TABLE 3.3-9 N
REMOTESHUTDOWNMONITORINGINSTRUMENTkt_10N N
h
~
MINIMUM
' DISPLAY METERS READ 0UT MEASUREMNT OPERABLE G
INSTRUMENT LOCATION RANG &_
CHANNELS E5 1.
RC Inlet Temp Cab. 217 50-650*F 1/ Loop b
2.
Makeup Tank Level Cab. 2!7 0-100 inches 1
5*
DISPLAY INDICATIONS to 1/ Breaker 3.
Control Rod Drive Trip Cable Room open/ closed Breakers MINIMUM DISPLAY PATCH POINTS PATCH POINT MEASUREHENT OPERABLE w
INSTRUMENT -
LOCATION RANGE CHANNELS
-w
~II
~3 4.
NI Intermediate Range Level Log N Cab. 217 10 to 10 Amps 1
~I 6
5.
NI Source Range Level Cab. 217 10 to 10 CPS 1
6.
Deleted 7.
Decay Heat Removal Flow Cab. 217 0-5000 GPM 1/ Loop 8.
Steam Generator Pressure A/B Cab. 217 0-1200 psig 1/St. Gen i
i
TABLE 3.3-10 5
A POST-ACCIDENT MONITORING INSTRUMENTATION 2
MINIMUM CHANNELS G
INSTRUMENT OPERABLE E5 1.
Reactor Building Pressure 2
I h
2.
Deleted 5
]
3.
Reactor Coolant Outlet Temperature 2
4.
Steam Generator Level 1/ steam generator" 5.
Borated Water Storage Tank Level 1
6.
High Pressure Injection Flow 1/ loop d>
7.
Low Pressure Injection Flow 1/ loop 8.
Deleted l
9.
Steam Generator Pressure 1/ steam generator 10.
Incore Thermocouples All available*
11.
Reactor Coolant System Pressure 1
12.
Reactor Building Water Level 1
3 t
AReport all failures pursuant to Specification 6.9.1.8.
TAB!.E 3.3-11 FIRE DETECTION INSTRUMENTS
... ~.
Required Instrument Location Instruments
' Alternate Operable Instrument Heat Flame Smoke Heat Flame Smoke 1.
Auxiliary Building N/A N/A 2
N/A N/A 2
2.
Control Building 351' Elevation N/A N/A 1
N/A N/A 3
. 331' Elevation (Control Room)
N/A N/A 1
N/A N/A 1
~ 305', 293', 280' Elevations N/A N/A 1
N/A N/A 7
- 3. -Control Building Area M/A N/A 1
11/A N/A 3
N. Biesel dinnerator Building
-"'A Diesel N/A 1
1 N/A N/A 1
e8. Diesel N/A 1
1 N/A N/A 1
5.
Fuel Handling Building N/A N/A 3
N/A N/A 1
6.
Reactor Building N/A N/A 1
N/A N/A 1
RC-P-1A/2A N/A N/A 1
N/A N/A 2
RC-P-1B/2B N/A N/A 1
N/A N/A 2
7.
River Water Pump House N/A 1
1 N/A N/A 2
8; Service Building N/A N/A 3
N/A N/A 3
l l
9.
Deleted es o.
M 96 THREE MILE ISLAND - UNIT 2 3.3-11 M
-.. _, _,. ~ "
LIMITING CONDITIONS FOR OPERATION 3.6 CONTAINMENT SYSTEMS 3.5.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY 3.b.1.1 Primary CONTAINMENT INTEGRITY shall be maintained and all containment penetrations, including at least two OPERABLE containment isolation valves or a double barrier in each penetration, shall be closed when not required open per procedures approved pursuant to Specification 6.8.2.
Purging or other treatment of the containment atmosphere shall be prohibited until approved by the NRC.
APPLICAILITY:
RECOVERY MEIE.
ACTION:
With one containment isolation valve per containment penetration open or i
Anoperable,. maintain the affected penetration (s) closed with either:
a.
At least ont deactivated automatic valve secured in the isolation position, or b.
At least one closed manual valve, or a blind flange.
CONTAINMENT AIR LOCKS 3.6.1.3 Each containment air lock shall be OPERABLE sith:
Both doors closed except when the air lock is being used for transit
--a.
entry and exit through the containment, then at least one air lock door shall be closed unless otherwise specified per procedures approved pursuant to Specification 6.8.2.
~
b.
An overall air lock leakage rate of less than or equal to 0.05 L, at P,, 56.2 psig.
(Per occupational exposure considerations)
APPLICABILITY:
RECOVERY MODE.
ACTION:
With an air lock inoperable, maintain at least one door closed and restore the air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
THREE MILE ISLAND - UNIT 2 3.6-1 W
~v w
3'ww k.
LIMITING CONDITIONS FOR OPERATION INTERNAL PRESSURE 3.6.1.4 Primary containment pressure shall be maintained between 0 psig and the minimum allowable pressure as determined from Figure 3.6-1.
APPLICABILITY:
RECOVERY MODE.
ACTION:
With the containment internal pressure outside the above limits, restore the internal pressere to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
AIR TEPPERATURE 3.6.1.5 Primary containment average air.tamperature.shall ant arraad 130*F.
APPLICABILTTY:. RECOVERY MODE.
> ACTION:
With the containment average air temperature greater than 130*F, reduce the average air temperature to within the limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.2 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS 3.6.4.1 One gas partitioner shall be OPERABLE.
APPLICABILITY:
RECOVERY MODE.
ACTION:
With the gas partitioner inoperable, restore the inoperable instrument to OPERABLE status within 7 days.
HYDROGEN PURGE CLEANUP SYSTEM 3.6.4.3 Deleted.
THREE MILE ISLAND - UNIT 2 3.6-2 l
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3.7.7 CONTROL ROCM EMERGENCY AIR CLEANUP SYSTEM 3.7.7.1 The control room ventilation and emergecy air cleanup system shall be OPERABLE with-a.
Two control room styply far.s and associated cooling coils, b.
Two contvol room bypass fars, c.
One charcoal adsorber and HEPA filter train, and d.
Two isolation dampers in the outside air intake duct.
e.
The control room air inlet radiation monitor OPERA 3LE.
APPLICABILITY: itEC0VERY N00E ACTION:
a.
With one control room supply fan or its associated cooling coil tinoperable, restore the inoperable fan and/or cooling coil to
' OPERABLE status within 7 days.
b.
With one control room bypass fan inoperable restore the inoperable fan to OPERABLE status within 7 days, c.
With the filter train inoperable, restore the filter trein to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
With one isolation damper in the outside air intake duct inoperable, restore the inoperable damper to OPERABLE status to close the duct within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one isolation damper secured in the closed position.
e.
With the control rocm air inlet radiation monitor inoperable, restore it to OPERABLE status or place the control room emergency air cleanup system in the recirculation mode of operation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l i
t THREE MILE ISLAND - UNIT 2 3.7-4
?
3.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM
~
3.7.10.1 The FIRE SUPPRESSION WATER SYSTEM shall be OPERABLE with; a.
At least 2 of the following 4 high pressure pumps shall be OPERABLE with their discharge aligned to the fire suppression header:
1.
Unit 1 Circulating Water Flume Diesel Fire Pump 2.
Unit 1 River Water Intake Diesel Fire Pump 3.
Unit 2 River Water Intake Diesel Fire Pump 4.
Unit 1 River Water Intake Motor Fire Pimp I
A.
Tee (2) separate matar supplies of the following.four (4) shall be avaMable with at least 90,000 gallons eath:
1.
Altitude Tank 2.
Unit 1 Circulating Water Flume 3.
Unit 1 River Water Intake Structure 4.
Unit 2 River Water Intake Structure c.
An OPERABLE flow path capable of taking suction from a water supply and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe, or spray system riser required to be OPERABLE per Specification 3.7.10.2 and 3.7.10.4.
APPLICABILITY:
At all times ACTION:
a.
With 3 pumps or 3 water supplies inoperable, restore the inoperable equipment to OPERABLE status within 7 days or in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.
THREE MILE ISLAND - UNIT 2 3.7-5 l
_ _ - = _ =- =_ __ __==.- - -
DULUGE/ SPRINKLER SYSTEMS 3.7.10.2 The Delugte and/or Sprinkler Systems located in the following areas shall be OPERABLE:
.. =..
a.
Diesel Generator Fuel Oil Tanks b.
Diesel Generator Building Air Intake c.
Air Intake Tunnel (Deluge - 2 of the 3 zones) d.
Hydrogen Purge Exhaust Filter AH-F-34#
Reactor Building Purge Exhaust Filters AH-F-31A/B#
e.
f.
Control Room Bypass Filter AH-F-5 g.
. Diesel Generator Rooms
- h.
. Fuel Handling Building Exhaust Filter AH-F-14A/B#
j.
Waste gas disposal filter WDG-F-1 k.
Auxiliary Building exhaust filters AH-F-10A/B#
1.
Condenser exhaust filters ##
Auxiliary Building backup exhaust filters **
m.
APPLICABILITY:
At all times.
ACTION:
With one or more of the above required deluge and/or sprinkler systems inoperable, establish a roving (at least once perhour) fire watch
- with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
- Except in the areas inaccessible per occupational exposure considerations.
- Supply lines may be isolated by one af four manually operated valves and by
~
- Ja manually operated deluge valve at the deluge station mounted on cutside of building.
- Supply line may be isolated by a single manually operated valve.
- Supply line may be isolated near the standpipe by two manually operated valves.
THREE MILE ISLAND - UNIT 2 3.7-7
LIMITING CONDITIONS FOR OPERATION 3.9 RADI0 ACTIVE WASTE STORAGE FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS 3.9.12 The fuel handling building / auxiliary building air cleanup systems shall be OPERABLE with exhaust ventilation flow through the HEPA filters during system operation.
APPLICABILITY:
At all times.
ACTION:
a.
With one fuel handling building or auxiliary building air cleanup system inoperable, restore the inoperable system to OPERABLE status l
'mithiin 7 days.
l b.
With no air cleanup system in the fuel handling building or the auxiliary building OPERABLE, suspend all operations involving move-ment of liquid and gaseous radioactive wastes in the affected building until the air cleanup system in that building is restored to OPERABLE status.
EPICOR II PROCESSED WATER 3.9.13 Discharge of water processed by the EPICOR II system shall be pro-hibited until approved by the NRC.
Water processed by the EPICOR II system shall be discharged in accordance with procedures approved pursuant to Specification 6.8.2.
APPLICABILITY:
At all times.
ACTION:
None excapt as provided in Specification 3.0.3.
REACTOR BUILDING SUMP WATER 3.9.14 Processing and discharge of water in the Reactor Building sump and Reactor Coolant System shall be prohibited until approved by the NRC. Water in the Reactor Building sump and Reactor Coolant System shall be processed and discharged in accordance with procedures approved pursuant to Specification
6.8.2. APPLICABILITY
At all times.
ACTION:
None except as provided in Specification 3.0.3.
THREE MILE ISLAND - UNIT 2 3.9-1
CONTAINMENT SYSTEMS 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1.5 AIR TEMPERATURE The average air temperature of the containment atmosphere is currently being maintained well below the 130 F limit.
The action will maximize the service life of the instrumentation and equipment installed in the containment.
Continued OPERABILITY of these items is required to continue monitoring and mitigating the March 28, 1979 incident.
3/4.5.4 CDMBUSTIBLE GAS CONTROL The gas partitioner is provided to analyze the hydrogen concentration in the tumtainment atmosphere so that actions can be sinitiated.to veduce the 1 hydrogen concentration if it approaches its flammable limit.
If excessive hydrogen concentrations are detected, appropriate actions will be initiated i
to reduce the hydrogen concentration to a safe level.
O.
Hwe b
L 1
4 THREE MILE ISLAND - UNIT 2 B 3/4 6-2
5.0 DESIGN FEATURES 5.1 SITE LNCLUSIONAREA 5.1.1 The exclusion area is shown on Figure 5.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone is shown on Figure 5.1-2.
SITE BOUNDARY FDR GASEDUS TFFLUENTS 3.1.3 The sitasboundary for gaseous effluents shall be as shown in Sigure 5.1-3.
1 SITE BDUNDARY FOR LIQUID EFFLUENTS
{
5.1.4 The site boundary for liquid effluents shall be as shown in Figure 5.1-4.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:
a.
Nominal inside diameter = 130 feet.
b.
Nominal inside height = 157 feet.
c.
Minimum thickness of concrete walls = 4 feet.
d.
Minimum thickness of concrete roof = 3.5 feet.
e.
Minimum thickness of concrete floor pad = 13.5 feet.
f.
Nominal thickness of steel liner = 1/2 inches.
6 g.
Net free volume = 2.1 x 10 cubic feet.
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 2 psig and a temperature of 286*F.
(Per occupational exposure considerations)
THREE MILE ISLAND - UNIT 2 5-1
ADMINISTRATIVE CONTROLS
~ ~ '...
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for the Manager Radiological Controls who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Supervisor-Station Training and shall o
seet or exceed the requirements and recommendations'of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
5.4.2 A training program for the Fire' Brigade shall be maintained under the Jdirection of the Supervisor-Station Training and shall meet or exceed the
. requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The Plant Operations Review Committee (PORC) shall function to advise the Manager Site Operations on all matters related to nuclear safety and radioactive waste safety.
COMPOSITION l
6.5.1.2 The Plant Operations Review Committee shall be composed of the:
a.
Chairman who shall have an academic degree in engineering or i
physical science field and a minimum of five years of l
applicable experience, who shall meet or exceed the qualifications of b.
1 Member Regulatory Guide 1.8, September 1975.
c.
7 Members -
who shall meet or exceed the qualification requirements of Section 4.7.2 of ANSI /ANS-3.1-1978.
The Manager Site Operations shall designate the Chairman and the Vice Chairman from among the members of the Plant Operations Review Committee.
THREE MILE ISLAND - UNIT 2 6-3
SURVEILLANCE REQUIREMENTS w=
BORON INJECTION (Continued) h.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the BWST temperature is at least 50 F when the outside air temperature is less than 50 F.
i.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (when system is in operation) by verifying that the standby reactor coolant system pressure control system:
1.
Surge tank water volume is filled to between 55% and 80% of tank capacity and the tank is pressurized to the operating RCS 1rressure t'25 psig but not ' higher than 600 psig.
2.
Isolation valves on the discharge side of the water filled tank maam st the reactoricoolant system are-open.
3.
< The in-service nitrogen supply bank is pressurized to between 225 and 400 psig.
j.
At least once per 7 days by verifying that the standby reactor coolant system pressure control system surge tanks and the charging water storage tank contain borated water with:
1.
A baron concentration of between 3000 and 4500 ppm.
2.
A dissolved gas concentration of less than 15 sec/kg of water.*
k.
At least once per 31 days by verifying that the standby reactor coolant system pressure control system isolation valve on the dis-charge side of the water filled tank nearest the reactor coolant system closes automatically on a tank low level test signal.
" Dissolved gas concentration for the SPC System is determined by taking a representative sample from the sampling point located downstream of SPC-T-1.
THREE MILE ISLAND - UNIT 2 4.1-2 Change No. 6
TABLE 4.3-6 5$
E' REMOTESHUTDOWNMONITORINGINSTRUMENTATIONSURhEILLANCEREQUIREMENTS n,
25 DISPLAY METERS CHANNEL CHANNEL 5;
INSTRUMENT CHECK CALIBRATION 82 1.
RC Inlet Temp.
M R*
3 C'
2.
Make Up Tank Level M
R*
Ei DISPLAY INDICATIONS G
3.
Control Rod Drive Trip Breakers M
N/A n3 DISPLAY PATCH POINTS INSTRUMENT 4.
NI Intermediate Range Level Log N M
R*
,l L,
4 5.
NI Source Range Level M
R*
4 6.
Deleted 7.
Decay Heat Removal Flow M
R*
8.
Steam Generator Pressure A/B M
R*
- Nuclear detectors and all channel components located inside containment and components inaccessible due to occupational exposure considerations may be excluded from CHANNEL CALIBRATION.
lj t
a TABLE 4.3-10 yx h
REMOTESHUTDOWNMONITORINGINSTRUMENTATIbHSUNEILLANCEREQUIREMENTS 3
CHANNEL CHANNEL E
INSTRUMENT CHECK CALIBRATION 1.
RC Inlet Temp.
M R*
2.
Make Up Tank Level M
R*
DISPLAY INDICATIONS i
E_
3.
Control Rod Drive Trip Breakers M
N/A
[
DISPLAY PATCH POINTS INSTRUMENT 1.
Reactor Building Pressure S
R*
2.
Deleted 3.
Reactor Coolant Outlet Temperature S
R*
4.
Steam Generator Level N/A N/A 5.
Borated Water Storage Tank Level S
R*
t 6.
High Pressure Injection Flow M**
R*
7.
Low Pressure Injection Flow M**
R*
l 8.
Deleted 9.
Steam Generator Pressure S
R*
?,'
t n{
10.
Incore Thermocouples S
R*
ua 11.
Reactor Coolant System Pressure S
R*
O I
(
12.
Reactor Building Water Level (Heise Gauge)
N/A SA#
l l
- Nuclear detectors and all channel components located inside.. Containment and components inaccessible due to occupational exposure considerations may be excluded from CHANNEL CALIBRATION.
- When applicable systems are in operation.
,s......
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S'URVEILLANCE REOUIREMENTS f
a=
4.6 -CONTAINMENT SYSTEMS i
4.6.1 PRIMARY CONTAINMENT l
CONTAINMENT INTEGRITY l
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
l l
a.
At least once per 31 days by verifying that:
l.
1.
All accessible (per occupational exposure considerations) penetrations not required to be open per approved procedures during RECOVERY MODE are closed by valves, blind flanges, or deactivated automatic valves secured in their witions.
.2.
The equipment hatch is closed and sealed.
b.
By' verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
CONTAINMENT AIR LOCKS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
~
a.
After each opening, except when the air lock is being used for l
multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying les:
than or equal to 0.01 L seal leakage when the volume between the door seals is stabilize 8 to a pressure to 10 psig.
b.
At least once per 6 months by conducting an overall air lock leakage test at P, 56.2 psig, and by verifying that the overall air lock leakage r$te is within its limit.
(Per occupational exposure considerations)
INTERNAL PRESSURE
- 4. 6.1. 4 The primary containment internal pressure shall be determined to within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
THREE MILE ISLAND - UNIT 2 4.6-1 Change No. 6
o SURVEILLANCE REQUIREMENTS AIR TEMPERATURE 4.6.1.5 The primary containment average air temperature shall be the arithmetical average of the temperatures at the following locations and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Location a.
RB nominal Elev. 350' (1 temperature indication) b.
RB nominal Elev. 330' (1 temperature indication) c.
RB nominal Elev. 305' (1 temperature indication)
A.6.4 CINBUSTIB1I GAS't0NTROL
'.HYDRDGEN ANALYZERS 4.6.4.1 The gas partitioner shall be demonstrated OPERABLE at least once per 31 days by performing a CHANNEL CALIBRATION using sample gases containing:
a.
One volume percent hydrogen, balance air.
b.
Four volume percent hydrogen, balance air.
HYDROGEN PURGE CLEANUP SYSTEM 4.6.4.3 The hydrogen purge cleanup system shall be demonstrated OPERABLE:
a.
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 or chemical release in any ventilation zone communi-cating with the system by:
1.
Verifying that the cleanup system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.S.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 1000 cfm i 10%.
2.
Verifying a system flow rate of 1000 cfm 10% during system operation when tested in accordance with ANSI N510-1975.
b.
At least once per 18 months by verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 1000 cfm 10%.
THREE MILE ISLAND - UNIT 2 4.6-2 Change No. 6 O
SURVEILLANCE REQUIREMENTS
~
c.
Deleted
" ~ - - - " ' ~ ~
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1 l
THREE MILE ISLAND - UNIT 2 4.6-3 Change No. 6
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i ADMINISTRATIVE CONTROLS 6.5.2 GENERATIONREVIEWCOMMITTEE(GRCl i
FUNCTION 6.5.2.1 independent review and audit of designated activitiTh on to provide es in the areas of:
a.
Nuclear unit operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Natallurgr i
Instrumentation and control e.
f.
Radiological safety Mechanical and electrical engineering g.
h.
Quality assurance practices 1.
Radioactive waste operations COMPOSITION 6.5.2.2 Chairman, appointed in writing by the Vice PresidThe G GRC members and alternates may m ers including the ent Technical Functions.
zation or from external sources.be appointed from within the corporate organi QUALIFICATIONS 6.5.2.3 engineering or physical science field; and in additiEach emic degree in an of five years of technical experience, of which a b2 in one or more of the areas specified in 6 5 2 on, shall have a minimum minimum of three years shall experience in a specialized field is acceptable as a Nine years of appropriat 1.
requirements.
Credit tow i
in above fields on a one ard experience may be given for advance degree wn for one basis up to a maximum of two yearsork ALTERNATES 6.5.2.4 Chairman to serve on a temporary basis; howeAll alternate m shall participate as voting members in GRC acti itiver, no more than two r
ng by the GRC v
es at any one time.
THREE MILE ISLAND - UNIT 2 6-6 r
-- -