ML19341C223
| ML19341C223 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/23/1981 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19341C220 | List: |
| References | |
| NUDOCS 8103020420 | |
| Download: ML19341C223 (29) | |
Text
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.9 RIMOIE SilulDOWN 'HONil0 RING INSIRUME NIAIION Q
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HINIHUH 1
REA00HI HEA50REHINI OPERA 0lE
[d DISPLAY HLIERS 1OCATION RANGE CllANNEl5 INSIROHfNI o
Cah. 217 50-650"f 1/ Loop-l.
ItC Inlet leap g
Cab. 217 0-100 irches I
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2.
Hakeup Tank Level to DISPt AY IHillCAI!ONS 3.
Control Rod Drive Trip Cable Room open/ closed 1/ Breaker Ilreakers HINIHUM PAICil POINI HEASUREHENT OPERAllLE DISPLAY PAICil PolNIS LOCATION RANGE CilANNE LS Y,
INSI_RilHE NI o
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~ Amps 1
4.
NI Intermediate Range Level Log N Cah. 217 10 lo 10 6
5.
NI Source Range Level Cab. 217 10 to 10 CPS 1
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Deleted Cah. 217 0-5000 GPH 1/l. cop 1.
Occay lleat Removal flow 8.
Steam Generator Pressure A/0 Cah. 21/
0-1200 psig 1/St. Gen 4
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T Alli E 3. 3-10
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POSI-ACCIDI:NI H0Hl10 RING INSTRilHLHIATION HINIHilH CilANH[l.S INSTRIIHtNT' DPl~ RAlli t il m -
1.
Reactor Building Pressure 2
2.
Deleted 3.
Reactor Coolant Outlet Temperature 2
4.
Steam Generator level 1/ steam generator
- 5.
llorated Water Storage Tank level I
6.
High Pressure Injection flow 1/ loop m
- w 1.
Low Pressure injection flow 1/ loop 8.
Deleted 9.
Steam Generator Pressure 1/ steam generator 10 Incore Thermocouples All avallah w*
II.
Reactor Coolant System Pressure I
12.
Reactor Iluilding Water level 1
aReport all f ailures pursuant to Specification 6.9.1.11 1
I
TABLE 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 N/A N/A 1
N/A N/A 3
4 Diesel Generator Building A Diesel N/A 1
1 N/A N/A 1
'S Diesel N/A 1
1 N/A N/A 1
5.
Fuel Handling Suilding 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-12/2B 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
9.
Deleted 7
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L' THREE MILE ISLAND - UNIT 2 3.3-11 i
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t LIMITING CONDITIONS FOR OPERATION 3.6 CONTAINMENT SYSTEMS 3.6.1 PRIMARY CONTAINMENT
- CONTAINMENT INTEGRITY
- 3. 5.1.1 Primary CONTAINMENT INTEGRITY shall be maintained and all containment pesetrations, including at least two GPERABLE containment isolation valves or a jouble barrier in each penetration, shall be closed when not recuired open pe r 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 MODE.
- ACTION:
With one containment isolation valve per containment penetration open or
- inoperable, maintain the affected penetration (s) closed with either:
a.
At least one deactivsted automatic valve secured in the isolation l
position, or, a blind flange.
b.
At least one closed manual valve, e
- CONTAINMENT AIR LOCKS
-3.'6.1.3 ~ :Each containment air lock shall be OPERABLE with:
a.
Both doors cicsed except when the air lock is being used for transit entry and exit through the containment, then at least one air lock door shall be closed.
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) l
- A_P]LICABILITY
RECOVERY MODE.
ACTION:
'With an air lock inoperable.. maintain at least one door closed and restore the airflock 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 e
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LIMITING CONCITICNS FOR OPERATION INTERNAL ORE 55URE Primary containment pressure sna11 be maintained cetween 1 psig anc l
3.6.1.4 the minimum allowaele pressure as cetermined from Figure 3.5-1.
APOLICABILITY:
RECOVERY MCCE.
ACTION:
With the containment internal pressure outsica the ateve limits, restore the internal pressure to within the limits within I hour.
AIR TEMPERATURE Primary containment average air temcerature shall not exceed 13C'F.
i.
3.5.1.5 t
APPLICAEILITY:
RECOVERY MCDE.
ACTICN:
Witn tne containment average air temcerature greater than 130*F, reduce the average air tem:erature to witnin tne limit witnin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.6.2 CCMEL'STIBLE GAS CONTROL
'HYCROGEN ANALYZERS 3.6.4.1 One gas partitioner shall te OPERABLE.
A00LICABILITY: RECOVERY MODE.
ACTICN:
With the gas partitioner inocerable, restore the incperacle instrument to I
CPERABLE status witnin 7 cays.
-HYDROGEN DURGE CLEANUP SYSTEM I
3.5.4.3 Deleted.
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THREE MILE -ISLAND - UNIT 2 3.5-2
LIMITING CONDITIONS FOR OPERATION 3.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM 13.7.7.1 The control room ventilation and emergency air cleanup system shall be OPERABLE with:
Two control room supply fans and associated cooling coils, a.
b.
Two control room bypass fans, One charcoal adsorber and REPA filter train, and c.
d.
Two isolation dampers in the outside air intake duct.
The control room air inlet radiation monitor OPERABLE.
e.
APPLICABILITY:
RECOVERY MODE.
ACTION:
a.
With one control room supply fan or its associated cooling coil inoperable, restore the inoperable fan and/or cooling coil to OPERABLE status within 7 days, With one control room bypass fan inoperable r= store the inoperable b.
fan to OPERABLE status within 7 days.
- c. - With the filter train itc t table, restore the filter train to OPERABLE status with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
With oce isolation damper in the outside air intake duct inoperable, restore the inoperable damper to OPERABLE status or 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.
With the control room air inlet radiation monitor inoperable, restore e.
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 />.
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-THREE MILE ISLAND - UNIT 2 3.7-4
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. LIMITING CONDITIONS FOR OPERATION 3.1.10 FIRE SUPPRESSION SYSTEMS FIRE SUPDRESSION WATER SYSTEM 3.7.10.1 The FIRE SUPPRESSION WATER SYSTEM shall be OPERASLE with; At least 2 of the following 4 high pressure pumps shall be OPERABLE l
a.
with their discharge aligned to the fire suppression header:
1.
Unit 1 Circulating Water Flume Diesel Fire Pump 2.
Unit 1 River Water Intake Ofesel Fire Pump 3.
- Unit 2 River Water Intake Diesel Fire Pump 4.
Unit 1 River Water Intake Motor Fire Pump b.
Two (2) separate water sucolies of the following four (4) shall be available with at least 90,000 gallons each:
1.
Altituce Tank 2.
Unit 1 Circulating Water Flume 3.
Unit 1 River Water Intake Structure 4
Unit 2 River Water Intake Structure
.An OPERAELE flow path capable of taking suction from a water sucoly c.
anc transferring the water through distribution piping with CPERABLE sectionaliz,ing control or isolation valves to the yar hydrant curd valves and the first valve ahead of the water flow alarm device on each sprinkler, hose stanepipe or spray system riser required to be OPERABLE per Specifications 3.7.10.2 and 3.7.10.4.
APPLICABILITY: At all times.
ACTION:
a.
With 3 pumos or' three water supplies inoperable, restore the l
b inoperable equipment to OPERABLE status within 7 days or in lieu of
~
Eany 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.
THRCE MILE ISLAND - UNIT 2
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- LIMITING CONDITIONS FOR OPERATION DELUGE / SPRINKLER SYSTEMS 3.7.10.2 Tne Deluge and/or Sprinkler Syste=s located in the following areas shall be OPERABLE:
a.
Diesel Generator Fuel Oil Tanks b.
Diesel Generator Building Air Intake Air Intake Tunnel (Deluge - 2 of the 3 :ones) c.
d.
Hydrogen Purge Exnaust Filter AH-F-34#
Reactor Suilding Purge-Exhaust Filters AH-F-31A/S#
e.
f.
Control Room Bypass Filter AH-F-5 g.
Diesel Generator Rooms h.
Fuel Handling Suilding Exhaust Filter AH-F-14A/E#
j.
Waste gas disposal filter WDG-F-1 k.
Auxiliary Building exhaust filters AH-F-10A/B*
1.
Condenser exhaust filters ##
Auxiliary Suilding backup exhaust filters **
m.
APPLICA5ILITY: At all times.
ACTION:
With one or more of the above recuired deluge and/or sprinkler systems inoperacle.
establish a roving (at least once per hour) fire watch" with cackup fire suppression equipment for the unprotected area (s) within 1 nour; restore the system to OPERABLE status within it 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 senedule for-restoring the system to OPERABLE status, i
" Except in :ne areas inaccessible per occupational exposure considerations.
- Supply lines may be isolated by one of.four manually operated valves and by a manually. operated deluge valve at the deluge station mounted on outside of building.
- # Supply line may be isolated by a single manually operated valve.
- 5upply111ne may be isolated near the standpipe by two canually operated valves.
THREE' MILE _ ISLAND - UNIT 2 3.7-7 y
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t LIMITING CONDITIONS FOR OPERATION 3.9 RADIOACTIVE 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 syste n operation.
APPLICABILITY: At all times.
ACTION:
a.
With oneLfuel handling building or auxiliary building air cleanup system inoperable, restore the inoperable system to OPERABLE status within 7 days.
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 vastes in the affected building until the air cleanup system-in that building i s restored to OPERABLE status.
EPICOR II PROCESSED WATER 3.9.13 Discharge of water processed by the EPICOR II system shall be pro-
-hibit'ed until approved by the NRC -Water processed by the EPICOR II system shall be discharged in accordance with peccedures approved pursuant to
.5pecification 6.8.2.
APPLICABILITY: At all times.
ACTION:
-Nene except as provided in Specification 3.0.3.
REA: TOR BUILDING SUMP WATER 3.~9.14 Processing and discharge of water in the Reactor Building sump and Water in
- Reactor Coolant System shall be prohibited until approved by the NRC.
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 -
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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 OPERASILITY of these items is required to continue monitoring and sitigating the March 28, 1979 incident.
3/4.6.4 COMBUSTIBLE GAS CONTROL The gas partitioner is provided to analyze the hydrogen concentration in the containment atmosphere so that actions can be initiated to reduce the hydrogen concentration if it approaches its flammable limit.
If excessive hydrogen concentrations are detected, appropriate actions will be initiated to reduce the hydrocca concentration to a safe level.
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THREE MILE ISLAND - UNIT 2 8 3/4 6-2
5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area is shown on Figure !.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone is shown on Figure 5.1-2.
5.2 CONTAINMENT
' CONFIGURATION The reactor containment building is a steel lined, reinforced concrete 5.2.1 building of cylindrical shape, with a dome roof and having the following design features:
Nominal inside diameter = 130 feet.
a.
b.
Nominal inside height = 157 feet.
Minimum thickness of ccncrete walls = 4 feet.
c.
Minimum thickness of concrete roof = 3.5 feet.
d.
Minimum thickness of concrete floor pad = 13.5 feet.
e.
Nominal thickness of steel liner = 1/2 inches.
f.
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Het free volume = 2.1 x 10 cubic feet.
g.
DESIGN PRES 5URE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be mainta'ined (per occunational evnosure considerations) for a maximum internal pressure of 60 psig and a temperature of 286 F.
5-1 THREE MILE ISLANO - UNIT 2 w
O ADMIN: Sir (ATIVE CONTRO.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff sh-11 meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable,wsitions, except for the Manager
)
Radiological Controls who snall meet or exceew 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 meet or exceed the requirements and recommendations of Sect' n 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire 3rigade shall be maintained under the direction of the Supervisor-Station Training and. shall meet or exceed the requirements of Section 27 of the NF?A Code-1975.
6.5 REVIEV 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 6.5.1.2 The Plant Operations Review Committee shall be composed of the:
who shall have an academic degree in engineering or a.
Chairman physical science field and a minimum of five years of 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 require-ments 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 th6 Plant Operations Review Committee.
O THREE MILE ISLAND - UNIT 2 a-3 p.
s 2-7 LImTING coxDITlor. 3~t" bATION 2.0 KAITORING REQUIRErENT5 t
2.1.2 Gaseous _E f fluents Applicability Applies to the controlled release of radioactive gases from 1MI Unit has. I and 2.
Objective g ective To define the Ifmits and conditions To ensure that radioactive gaseaus for the controlled release o' cadit,-
releases from the facility are with-in the limits of specifications.
active gaseous effluents tr the environs to ensure that these releases are as low as practicable. These releases should not result in radia-tion exposures in of f site areas great-er than a few percent of background exposures. The instantaneous release rate for all effluent discharges should be within the limits specified in 10CFR 20.
To assure that the releases of radio-active gases to offsite areas meet the as low as practicable concept, the follwing ob.iectives app 1y:
The release rate of radionuclides, a.averaged over a yearly interval, ex-cept particulate nuclides l
l with half thes greater tnan 8 days, t
discharged from Unit Nos.1 and 2, should result in a dose rate at the site boundary of less than 5 mrem /yr to the whole body or any organ.
b.
The release rate of particulate radionuclides with half-lives longer than 8 days, should result in a dose in the unrestricted area of less than 15 mrem /yr by I
inhalation or to the thyroid of a child through the cow-milk chain.
Specification
~
Specification 1
During release of radioactive gaseces The instantaneous release rate of wastes, the following conditions a.
gross gaseous activity except for shall be met:
t halogens and particulates with half-j
' lives longer than eight days shall not i
A.
During release of gaseous waste l
exceed:
from the waste gas decay tanks, the 9'" * " * * " " *
- 3 Qi 5m
{ pec),
- 5. 1.5 x 10 m l
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LIMITIG COGITIONS FOR OPER ATION 2.0 tCN]TN]% r<EculE Era.T5 Specification (Cont' d1 Specification (Cont'd1 1.
Waste gas discharoe monitor where Og is the release rate in UC1/sec for isotope 1, and MPC1 (Unit 1: RM-A7; Unit 2: WOG-R-laS0)
(uC1/m ) is the maximun gemis-or similar device, shall be operanle.
3 sible concentration of isotope and defined in Appendix B. Table 2.
Auxiliary 'and Fuel Handline II, Column 1. 10CFR 20.
Building and Unit Exhaust Vent exhaust gas, iodine and particulate conitor b.
The instantaneous release (Unit 1: Rn aB; Unit 2: HP-R-219) or similar device, shall be operable.
rate of particulates with half-lives greater tnan 3.
The waste gas decay tank discharge eight days, releasec to the en-valves (Unit 1: WOO-V47; Unit 2: WOO.
virons as part of airtorne.ef-Y-3CA or 303) Shall be operable, fluents, shall not exceed 0.3 uC1/ sec.
4 The was'.e gas decay tant discharge valves (Ur.it 1: V0G-V47; Unit 2: W OG-V -
c.
The release rate of gross gase-30A or TJB) shall be closed en receipt ous activity shall not exceed:
of aa.y one of the following conditions:
0 4m a.
A hich radiation signal from the 3
1
- UiE Ti sei waste ga's dischar e monitor (Unit 1:
y i
RM-A7; Unit 2: WOG-R-1480 ).
when averaged over any calendar b.
A high radiation signal from the Auxiliary and Fuel Building exhaust qua rter.
monitor (Unit 1: Ut-A8; Unit 2: HP-d.
The release rate of l
R-219).
particulates witn half-lives A high flow sicnal frcn the Waste greater than eight days, shall not Gas Decay Tant discharge flow trans-c.
exceed: 0.024 uC1/sec., when aver-mitter (Unit 1: FT-123; Unit 2: 30G-aged over any calencar cuarter, FT-3923.
e.
Radioactive gaseous wastes coll ected in the gas decay tanks d.
Observation of less of flow shall be held up to a minimtri of through the Unit vent.
r 45 days, except when the release a il-B.
- t. ' ' ig pur.,,f the Reactor s
rate shall not exceed:
ding, -.se folicwings conditions shall be met:
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1.
The Reactor Building Purge Exhaus; b ftRT i 1.
Monitor (Unit 1: *M-A9; Unit 2: EF-R-(no e gases) 225 and/or HP-R-226 and HP-R-219) or similar device shall be operable.
or f
urge Exhaust Yalves (Unit 2.
The n 2.
0.003 uti/sec (particulates AH-VI A and AH-v!B and Dameers; l
with half-lives Unit 2: 05129 A/O and 05129 B/C) greater than 8 shall be operable.
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L LIMIT]hG CONDIl.. V C DERATION 2.0 Phlf0Rlt.G REOUIREPENTS Specification (Cont'd)
Specification (Cent'd) f.
Radioactive gas and particuistes 3.
The valves (Unit 1: AH-VIA and purged fran the reactor building shall AH-VIB and Campers: Unit 2: D5129 A/D be filtered through the high ef ficiency and 05129 B/C) shall be interlocked t
I particulate air filters) to close or recirculate, respectively on receipt of a high radiation signal i
from the Reactor Building Exhaust l
I g.
The maximri activity to be con-Monit,r (Unit 1: R71-A9; Unit 2: HP-R-l tained in one gas decay tank shall not 225 and HP-R-226) respectively.
exceed 8800 curies (equivalent to Xe-133).
C.
The flow rate for radioactive effluent streams an:1 the Auxiliary' l
h.
When the release rate of radio-and fuel Handling eut!!1ng and the l
active materials in gaseous wastes.
Reactor Building, shall be monitored averaged over a calendar quarter and recorded. Gaseous effluents from
- exceeds, the Wa ste Gea Decay Tanks and y
gg 3,3 the Reactor Building Purge Exhaust shall be continuously ponitored and g,6 x 10 g l
gi
- recorded, (noble gas)
D.
Radioa:tive gaseous waste sampling I
cr and activity analysis shall be per-D.006 uu/see particulates with fomed in accordance enth Table 2.3-2.
half-lives greater than 8 days)
E.
The waste gas decay tank -ffluent monitor (Unit 1: RM-A7; Unit 2: WDG-R -
the licensee shall notify the h"AC with-1480) shall be tested using the in-1'-
in 30 days, identifying the causes and stalled check source or equivalent describing the proposed program of ac-prior to any release of radioactive tion to reduce such release rates.
gas fran a holdup tant and shall be I
calibrated quarterly using a re-ferenced calibration source in a controlled reproducible geometry.
F.
During power operation, the con-densor vacuum pump discharge shall be
(
g continuously monitored for gross 1
gaseous activity. The monitor shall not be inoperable for more than a l
week. Whenever this monitor is in-operable, a grab sample shall be radioactivity. (8,Y )yzed for gross taken daily and anal G.
Facility records shall be main-tained of radioactive concentration,"
- release ratio and vohme of each batch of gaseous effisents released i
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2-10d TABLE 2.7-1 (Continued)
TABLE NOTATION b.
Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the Chemical Cleaning Building.
l c.
The principal gamma emitters for which the LLD specification applies exclusively are the follouine <adionuclides:
Mn-54, Fe-59, Co-58, Co-58, Co-60, 2n-65, Mo-90 s-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. T1 a list does not mean that only these nuclides are to be dete;.d and reported. Other peaks which are measurable and identifisole, together with the above nuclides, shall also be identified aDJ reported. Nuclides which are below the LLD for the analysis shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" valves shall not be used in the required dose calculations.
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o 2-11 TABLE 2.3-2 Radioactive Gaseous Waste Sag ling and Analysis (5) 5 ample Type Sampling Frequency Tyoe ut'7.- Q1ty Analysis Detectacle Concentration (1)
Waste Gas Decay Tank Release Gas Each Tank H-3 10-6 uCf/cc Release Individual Gama Emitters 10 uCf/cc (2)
Reactor Building Purge Releases Gas Each Purge H-3
.10 uCf/cc Individual Gama Emitters 10 uCf/cc (2)
Condenser Vacuum Pume Releases Gas Monthly H-3 10-6,ggj,,
Monthly (3)
O Individual Cama Emitters 10 uCf/cc (2)
Auxiliarv and Fuel Hand 11no Buildino Exhaust Vent. Reactor Buildino Purce Vent and Unit Exnaust (6)
Vent Release Points Gas Monthly (4)
H-3 10 uCf/cc Individual Gama Emitters 10 uC1/cc (2)
)
Charcoal Weekly 1-131, I-133, !-135 10-12 uC1/cc Particul ates Weekly Individual Gamma Emitters 10-10 uCf/cc (2)
Monthly Cmpostte Sr-89, Sr-90 10'II uCf/cc Monthly Caposite Gross Alpha Emitters 10-11,c,fe, (1) The above cetectability ifmits are based on technical feasibility and on the potential significance in the environnent of the cuantities released. For some nuclides. Iow r detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.
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(2) For certain mixtures of garws esitters, it may not be possible to maanre radionuclides at.
levels near their sensitivity limits een other nuclides are present in the sample at much i
nigher levels. Under these circumstances, it will be more acpropriate to calculate tne levels of such radionuclides using caserved ratios in the gaseous camponent in tne reactor.
3 coolant for those radionuclides wnich are measuraole.
(3) Analysis shall also be perforced following each refueling period, start-up or similar operational occurrence which c5 'id altar the mixture of radionuclides.
(4) Sampled during periods when no waste gas decey tank release or reactor building purge is in progress.
(5) Deviations fran the sampling and analysis regime will he noteo in the report specified in Section 5.6.1.
(6) The Auxiliary and Fuel Handling Building Exhaust Vent and Reactor Building Purge Vent per-tain to Unit 1 (TM!-1), while the unit exhaust vent pertains to Unit 2 (TMI-2).
(7) Sample not :equired for Unit exhaust Vent (TMIr2)
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2-13 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Bases (Cont'd)
Bases (Cont'd)
These efforts should include con-5.6.1 of these Technical Specifica-gideration of meteorological tions. On the basis of such reports conditions during releases, and any additional information the Commission may obtain from the The annual objectives have been licensee or others, the Commission developed taking into account a may from time to time require the combination of system variables licensee to take such action as the including fuel failures, primary Commission deems appropriate.
system leakage, primary to secondary system leakage, and the performance of radionuclide removal mechanisms.
I-131 is not specifically monitored because it has decayed to less than detectable activity since the March 28, 1979 accident.
Specification a. above, requires the licensee to limit the con-centration of noble gases from the station of levels specified in 10 CFR 20, Appendix B, for unrestric-ted areas Based on a X/Q of 6.7 x 10-b 3
sec/m, this specification provides assurance that no member of the general public would be exposed to radioactive materials in excess of limits specified in the Commission's rules and regu-lations.
Specification b. above, requires tha licensee to limit the concen-tration particulates with half-lives greater than eight days, released from the station to unrestrictsd areas to levels such that no individual will receive more than 500 mrem /yr to the total body or 3000 mrem /yr to the skin.
The absence of iodine insures that the corresponding thyroid dose rate above background to an infact via the cow-milk-infant pathway is less than or equal to 1500 mrem /yr. A grazing period of 6 months has been applied to all radionuclides in particulate form with a half-lives l
greater than eight days,-to allow for the milk exposure pathway.
i i
2-14 f
LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS i
Bases (Cont'd)
Bases (Cont'd)
The release rate is determined by using the methodology of Regulatory Guide 1.109 (Rev. 1) and a relative depgsitgon factor (D/Q) of 2.1 x8 10 -
m' The D/Q of 2.1 x 10 m-2 was calculated for the nearest cow location 1.2 miles SE of the station, using on site meteoro-logical data.
Specification c. and d. above, estab-lish an upper limit for the release of gaseous activity at 16 percent of instantaneous release limit of novle gases and at eight percent of the release rate of particulates with half-lives greater than 8 days, averaged over any calendar quarter, respectively. The intent of this specification is to permit the licensee the flexibility of operation to assure that the public is provided a depend-able source of power under unusual operating conditions which may tempor-arily result in higher releases than the objectives.
Specification e, above, requires a 45 day holdup time for radioactive gaseous
~
waste collected in the gas decay tanks to assure decay of most radionuclides.
The whole body dose from noble gases
.at the site boundary is expected to be less than 10 mrem /yr (primarily from Kr-85). The whole body dose from particulates at the nearest farm is expected to be less than 5 mrem /yr.
Specification f. above, limits the radioactivity that may be released to the environment to "as low as prac-ticable."
Specification g. above, lir.its the maxi-.
mum'offsight dose.to well below the limits of~101CFR 100, postulating that the rup-Enre of a Waste Gas Decay Tank holding the maximum activity releases all of the contents to the atmosphere.
s
2-14 (Cont'd)
LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS Bases (Cont'd)
In addition to the limiting conditions for operation listed und r a,b, and c above, the reporting requirements of Specification h delineate that the licensee shall identify the cause whenever the radioactive gaseous release rate exceeds 4 percent of Specification a. or 2 percent of Specification b. above, averaged over a calendar quarter, and described the proposed program of action to reduce such release rates. The report must be filed within 30 days following the calendar quarter in which more than twice the design release rate occurred.
7 m
)
2-14b O
TABLE 2.1-3a RADI0ACT!YE GASEOUS EFFLUENT MONITORING INSTRU"ENTATION MINIMUM CHANNELS INSTRUMENT _
OPERABLE APPLICABILITY _
ACTION
- 10. EPICOR-II YENTILATION SYSTEM 37 a.
Noble Gas Activity Monitor 1
b.
Deleted 41 c.
Particulate Sampler 1
36 d.
Flow Rate Menitor 1
36 e.
Sampler Flow Rate Monitor 1
TABLE NOTATION _
O c At all times.
ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per B hours and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 41 - With the number of channels OPEPABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to ?O days provided samples are continuously collected with auxiliary sampling
. equipment as' required in Table 2.1-1.
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A endment No.10
~
2-18c TABLE 2.1-3b RADIDACTIVE GAREOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT
- r. HECK CHECK CALIBRATION TEST
- 10. EPP.OR-II VENTILATION SYSTEM a.
Noble Gas Activity Monitor D
M R(3)
Q(2) l b.
Deleted c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Flow Rate Monitor D
N.A.
SA SA e.
Sampler Flow Rate Monitor D
N.A.
SA SA O
TABLE NOTATION _
(2) CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alem annunication 0: curs if any of the following conditi,ons exist.
1.
Instrument indicates measures levels above the alam setpoint.
2.
Circuit failure (alam function only).
3.
Instrument indicates a downside failure (alam function only).
4.
Instrument controls not set in operate mode or the twitch position administrative 1y monitored and controlled.
The initial CHANNEL CALIBRATION shall be perfomed using one or (3) more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers c These that participate in measurement assurance activities with NBS.
standards shall pemit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION sources that have been related to the initial calibrz-tion shall be used.
'O 1
knendment No.10
. =
SURVEILLANCE REQUIREMENTS B_0RON 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 BUST tempareture 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 l
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 pressure i 25 psig but not higher than 600 psig.
2.
Isolation valves on the discharge side of the water filled tank nearest the reactor coolant system are open.
3.
The in-service nitrogen supply bank is pressurized to betwear, 225 and 400 psig.
j.
At least once per 7 days by verifying that the standby reactor l
coolant system pressure control system surge tanks and the charging water storage tank contain borated water with:
1.
A boron 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-l charge side of the water filled tank nearest the reactor coolant system closes automatically on a tank low level test signal.
l Dissolved gas concentration for the SPC System is determined i
by taking a representative sample from the sampling point.
t located downstream of SPC-T-1.
THREE MILE ISLAND - UNIT 2 4.1-2 Change No. 4
x TA8LE 4.3-6 E
REMDTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS G
CHANNEL CHANNEL DISPLAY METERS CHECK CAllBRATION INSTRUMENT M
R*
1.
RC Inlet Temp.
z M
R*
Q 2.
Make Up Tank Level f%I DISPLAY INDICATIONS M
N/A 3.
Control Rod Drive Trip Breakers CHANNEL C)(ANNEL DISPLAY PATCH PolNTS CHECK CALIBRATION INSTRUMENT M
R*
4.
NI Intermediate Range Level Log N M
R" i.,
5.
NI Source Range Level 6.
Delete.
M R*
7.
Decay Heat Removal Flow M
R*
8.
Steam Generator Pressure A/B
- Nuclear detectors and al channel components located inside containment and components inaccessible due to occupational exposure considerations may be excluded from CHANNEL CALIBRATION.
t
TABLE 4.3-10 f
n; POST-ACCIDENT MONITORING INSTRUNENTATION SURVElttANCE REQUIREMENis m
3 r-CHANNEL CHAletEL UI INSTRUMENT CHECK Call 8 RATION G
!3 1.
Reactor Building Pressure 5
A*
e gj 2.
Deleted.
U 3.
Reactor Coolant Outlet Temperature 5
R*
4.
Steae Generator Level N/A N/A l
5 R*
S.
Borated Water Storage Tank Level I
6.
High Pressure Injection Flow M**
R*
f-7.
Low Pressure Injection Flow Maa Ra Y*
om 8.
Deleted.
9.
Steam Generator Pressure 5
R*
- I 10.
Incore Thermocouples 5
A*
11.
Reactor Coolant System Pressure 5
R*
12.
Reactor Building Water Level (Helse Gauge)
N/A SA#
- Neutron detectors and all channel components located inside containment and components inaccessible due to occupational exposure considerations may be excluded from CilANNEL CALIBRATION.
- When applicable systems are in operation.
- Unless an appropriate engineering evaluation demonstrates the instrument to be in calibration, t
l
SURVEILLANCE REOUIRENs 'S 4.6 CONTAINMENT SYSTEMS 4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that:
a.
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 positions.
2.
The equipment hatch is closed and sealed.
By verifying that each containment air lock is OPERABLE per b.
Specification 3.6.1.3.
CONTAINMENT AIR LOCKS Each containment air lock shall be demonstrated OPERABLE:
4.6.1.3 After each opening, except when the air lock is being used for a."
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 less i
than or equal to 0.01 L seal leakage when the volume between the I
door seals is stabilize 8 to a pressure to 10 psig.
i At least once per 6 months by conducting an overall air lock leakage b.
test at P, 56.2 psig, and by verifying that the owerall air lock leakage.rlte is within its limit. (Per occupational exposure considera-tions) l INTERNAL PRESSURE The primary containment internal pressure shall be determined to 4.6.1.4 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 />.
i I
- Exemption to Appendix "J" of 10 CFR 50.
THREE MILE ISLAND - UNIT 2 4.6-1 1
t SURVEILLANCE REQUIREMENTS AIR TEMPERATURE 4.6.1.5 The primary containment average air te'mperature 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 RB nominal Elev. 350' (2 temperature indications) a.
b.
RB nominal Elev. 330' (2 temperature indications)
RB nominal Elev. 305' (2 temperature indications) c.
4.6.4 COMBUSTIBLE GAS CONTROL HYOROGEN 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:
One volume percent hydrogen, balance air.
a.
b.
Four volume percent hydrogen, balance air.
HYOR0 GEN PURGE CLEANUP SYSTEM 4.6.4.3 DELETED.
THREE MILE ISLAND - UNIT 2 4.6-2
_ _. - _ _ = _ _.
4
~ ~ - -
I SURVEILLANCE REQUIRF. MENS.
t i
DELETED.
J K
i 1
l l
1 i
l i
I f
1 THREE MILE ISLANO. UNIT 2 4.6-3 0
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