ML20064G098
| ML20064G098 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 01/07/1983 |
| From: | Longenecker J ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT |
| To: | Check P Office of Nuclear Reactor Regulation |
| References | |
| HQ:S:83:176, NUDOCS 8301110303 | |
| Download: ML20064G098 (23) | |
Text
.
O Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:176 jgH 0 7 N Mr. Paul S. Check, Director-CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Check:
METil0D0 LOGY FOR CLINCil RIVER BREEDER REACTOR PLANT'S APPLICATION OF RADIOLOGICAL SOURCE TERMS IN CONTAINMENT Re ference: Letter, J. R. Longenecker to P. S. Check, llQ:S:82:153,
" Meeting Summary for the Environmental Qualification Meeting, December 20, 1982," dated December 21, 1982 Enclosed is the subject report that responds to the two commitments made in Enclosure 1 of the reference.
Any questions regarding the enclosed information may be directed to R. Wishau (FTS 626-6378) or A. Mellor (FTS 626-6355) of the Project Office Oak Ridge staff.
Sincerely, 1
r x(
a c J n R. Longenecker Acting Director, Office of Breeder Demonstration Projects Office of Nuc1 car Energy Enclosure DOOl cc: Service List Standard Distribution Licensing Distribution S
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,$Fih8&oSSSku LA
Enclosure Methodology for CRBRP's Appiication of Radiological Source Terms in-Contelnment i
Contents 1.
Introduct ion ll. Class IE Equipment Radiological Qualification Basis 111.
CRBRP Radiological Source Terms f or Design Basis Events IV.
Design Methodology used to Calculate the Radiation Environments A.
Cover Gas Release B.
Sodium Storage Tank Failure During Maintenance C.
Site Sultability Source Term (SSST)
V.
Application of CRBRP Radiological Source Terms to Class 1E Equipment Qual i f ication 4
,--r-,_.y,-,
+ _--
o l.
Introduction in establishing radiological qualification bases f or CRBRP electrical equipment, a clear distinction must be drawn between items qualified f or desi gn bases events and those qual if ied f or events beyond the desi gn base.
The bases and methodology for qualification of equipment f or design base events is treated in some detail in this report.
The same material relative to events beyond the design base is addressed in detail in Ref erence 1, and in summary f orm bel ow.
In this context, the term ' events beyond the design base' denotes Class 9 events, invol ving melting of substantial fractions of the core.
The accommodation of such events f or CRBRP is termed Thermal Margin Beyond the Design Base, or TMBDB.
For TMBDB, suf ficient instrumentation is provided to allow the operator to monitor the conditions in the RCB.
This instrumentation monitors the containment vessel temperature, atmospheric tanperature, pressure, radiation, and hydrogen concentration.
The capability for obtaining grab samples of the containment is al so provided.
The TMBDB instrumentation has been located so as to minimize the ef fects of the environment on the instrumentation, and the only equipment directly exposed to the severe TMBDB environment are the containment aimosphere thermocouples, the pressure sensors, and the f ilters f or the contal mnent ai r sample l ines.
All other instrumentation and all signal conditioning equipment is located in less severe environments.
The< source term used f or TMBDB qual if ication i s real isti cal ly calculated f or a hypothetical event which causes a complete meltdown of the core and the subsequent release of radioactive material from the Reactor Cavity to the Containment.
For completeness, equipment qual if ied to TMBDB conditions is identi f ied as such in Table 3 of this report.
However, the renalnder of the text treats qualification f or design base events only, ll. Class 1E Equipment Radiological Qualification Basis The radiation environment f or qual ification of CRBRP Class 1E equipment shall be based upon the most severe environment predicted to occur prior to, during, and following those portions of the specific accident transients f or which the omnponent is required to perf orm its saf ety function.
This qualification basis is consistent with RG 1.89 and NUREG-0588 as outlined in the latest revision to the PSAR Section 3.11.
Ill. CRBRP Radiological Source Terms f or Design Basis Events The nature of LMFBR accidents is f undsnental ly dif ferent f rom that of l
LWR accidents.
Specifically, the absence of stored energy within the l
Primary Heat Transport System (PHTS), together with the compartmentalization of the containment into cells within massive concrete walls, results in a decoupling of accidents consequences f rom areas that are not close to the source.
As a resul t, in sharp contrast
to the LWR situation, there are many saf ety-related equipment items whose function is only required for a snall range of events.
- Thus, j
oompliance with the NUREG-0588 requirenents that each equipment item be quellfied f or the worst design basis accidents f or which its f unction is required, could result in definition of multiple source term speci f ications.
The CRBRP Project has rationalized this situation by identifying three enveloping radiological source terms, derived f rom di f ferent initiations:
1.
The Site Suitability Source Terms (SSST) 2.
The containment design basis accident of radiological consequence (sodium storage tank f ailure during maintenance) 3.
Cover gas release design basis accident with the reactor at power.
The rationale for selection of the appropriate qualification source terms f or any equipment item is as f ol lows:
1.
All equipment required to ensure proper functioning of the containment is qualified to the SSST.
This includes the containment isolation systen and certain monitoring equipment identifed in Table 3.
2.
All other saf ety equipment is qual if ied to 15e Sodium Storage Tank Fail ure or Cover Gas Rel ease.
The Plant Protection Systems is not requi red to operate f or the tank f ail ure, since, by def inition of the event, the reactor is already shut down.
3.
The PPS is qualif ied to the source terms associated with a release of cover gas with the reactor at power.
IV.
Design Methodology Usey to Calculate the Radiation Environments Extremely conservative design methodology was used to calculate the radiation dose rates due to the cover gas release and sodium storage tank f ailure during maintenance.
These calculations resulted in the peak dose rates and cummulative doses specified in Tables 1 and 2.
A.
Cover Gas Release Determination of the dose rates inside the RC8, resulting f rom a reactor cover gas release into the RC8 operating floor during normal operation, is based on the f ollowing calculational approach:
e The entire vol ume of cover gas above the sodium pool in the reactor vessel ( 880 cu. ft.) is assumed to be instantaneously (non-mechanistical ly) rel eased to the RCB operating f loor.
e The specific activity of the reactor cover gas is based on the release rates of fission products, activation and tritium sources
l to the cover gas in PSAR Table 12.1-11.
The resulting speci f ic activities are provided in Table 1, PSAR Chapter 12.
e The released aciivity is assumed to uni formly disperso into the RCO operailng f loor.
e No leakage to the annulus is assumed.
e Radioactivo decay is considerod.
e The gamma doso rates are calculated based on the f Inito cloud model of References 2 and 3.
e The bota dose rates are calculated based on the soml-inf inito cloud model of Ref erences 2 and 3.
The scenario described abovo is considorod highly conservativo f or the following reasons:
o Release of the enti re reactor vessel cover gas volumo to the operati n0 floor is not a postulated occurence.
The Roact or Vossel Hood Access Arons sool s, described in Section 5.1 of the PSAR, are designed to provent any leaknDo into the Hood Access Area.
e The radiological assessment is besod on 1% f ailed f uel.
The abovo estime10 f or f ailed f uoi is a dosl n paruvotor; the 0
expected value is on the ordor of 0.1%.
D.
Sodium Storago Tank Failuro Durin0 Maintenanco A description of the design methodolo0y used to calculato the radiation doso ratos duo to the sodlum storage tank during maintenanco is shown bolow, lho calculation of the Damn'a and bota doso rates is based on the f ollowin0 dosl n requiromonts:
0 e The doso ratos result f rom the relonso and deposition of sodium corosol into the reactor containment building above tho operati ng f loor, e This acrosol is the resul t of the release of 35,000 Gallons of primary sodl um into cel l 102A.
The coll hatch is assomod open with direct access to the operatin0 f loor.
Thi s postulated event is described in dotall in PSAR Chaptor 6.2.1.3.
~ e The resulting acrosol deposition has boon calculated usin0 the HAA-3 computer progrem.
The corosol is olther suspended in the containment domo volume, plated on the containment domo shel1, or settled on the reactor oporatin0 f l oor.
e The dominant sourco is settled motorial (approximately 82% of No 0 at 1 day; 96% at 4 days).
Thorof ore, the dosi gn basi s doso
point was chosen at a location just above (4 inches) the operating floor to provide a " worst case" envirorynent.
e The radiaton source term for the sodlum aerosol is based on the fire occuring af ter 30 years of reactor operation with the reactor having been shutdown 10 days.
The source term for primary sodium is shown on PSAR Table 12.1-6.
The calculation methods used were as follows:
o The gamma dose rate f rom the suspended, plated, and settled sodlum aerosol was calculated using the SCAP computer progran.
The gamma ray energy associated with the individual isotopes was taken f rom Ref erence 4.
The SCAP computer program is described in Appendix A of the PSAR.
The beta dose rates were calculated based on the methodology e
described in Ref erence 5 (See Chapter IV). The beta energy associated with the Individual isotopes was taken f rom Ref erence 4.
C.
Site Sultability Source Term (SSST)
The methodology for calculating the radiation environment associated with the SSST is contained in the PSAR Section 15. A-1.
CRBRP util izes this source term in compl iance with the speci f ic direction f rom the Nuclear Regulatory Conmission (Ref erence 6).
V.
Application of CRBRP Radiological Source Terms to Class IE Equipment Qualification The radiation environment for qualification of Class 1E equipment shall be based on the sum of the background radiation over the equipment quallfled life, plus that associated with the most sovero design basis event during or following which that equipment must renain f unctional.
CRBRP uses the sodium tank f ailure during maintenance and the cover gas rel ease desi gn basis acci dents to gonorate the source terms f or determining the radiation environments within containment f or all equipment except f or equipment required f or contalrunent isolation (CIS).
For the CIS equipment, the CRBRP qual if ication progrem uses the radiological source term (SSST) to def ine the radiation environment f or qual ifying Class 1E equipment requi red to f unction during and f ol lowing the SSST release to mitigate the consequences of the release as prescribed in Ref erence 6.
A review of the saf ety functions required to mitigate and monitor the consequences of the cover gas release, the sodium storage tank f ail uro during maintenance, and the non-mochanistic application of SSST resulted in CRBRP establishing the enveloping radiation environments for in-containment Class IE equipment as shown in Table 3.
This table
contains a complete listing of Class IE equipment located within contai nment.
Table 3 provides the basis f or using a specific enveloping radiation environment.
The Class 1E equipment located in-containment is designed to perf orm the f ollowing basic saf ety f unctions:
- 1) Reactor Shutdown, 2) Decay Heat Renovel, 3) Containment Isolation, and 4) Accident Monitoring.
In order to determine the equipment required to f unction during the enveloping radiation environments specified f or equipnent qualif ication, one must determine the plant operating modes possible during which the equipment must f unction.
For the cover gas rel ease desi gn basi s accident, it is assumed that the release could occur during any plant operating condition.
Ther ef or e, al l desi gn basis saf ety f unctions woul d be requi red.
For the sodi um tank f ire event, the reactor has been shutdown 10 days prior to initiation of the enveloping radiation environment, theref ore, no reactor shutdown f unctions are required.
CRBRP's application of the non-mechani stic SSST i s consi stent with Ref erence 6 and requi res that only the containment isolation system f unction during the resulting enveloping environment.
S
References (1) CRBRD-3, " Hypothetical Core Disruptive Accident Considerations in CRBRP", Vol ume 2, " Assessment of Thermal Margin Beyond the Desi gn Base".
(2)
K. G. Murphy and K. M. Campe,13th AEC Air Cleaning Conference " Nuclear Power Plant Control Room Ventilation System Design f or Meeting General Design Criteria 19" (August 1974)
(3) Regulatory Guide 1.3 uAssunptions Used for Evaluating the Potential Radiological Consequences of a LOCA f or BWR" (4) " Table of the isotopes" Sixth Edition by C. M. Lederer, J. M. Hol lander, and I. Pulman: Uni versi ty of Cal i f orni a, J oh n W il ey & Son s, Inc.
(5) LA-4558-MS, " Surf ace Contamination: Deci sion Level s" by J. W. Heal y, Los Alamos Scientific Laboroicry (6)
Letter, R. P. Deni se (USNRC) to L. W. Caf f ey (CRBRP), May 6,1976 I
l TABLE 1 COMPARISON OF RADIOLOGICAL l
QUALIFICATION REQUIREMENTS WITH l
ANTICIPATED RELEASES i
- 1. PEAK DOSE RATE DOSE RATE CORRESPONDING BASIS FOR DOSE (RAD /HR) FOR MORE REALISTIC DOSE RATE RATE QUALIFICATION EVENT (RAD /HR)
(.2p+ 8) RADS
(.2p+ 8) RADS I
- SSST 1.4 x 106 NONE I
35000 GALLON 102 4000 GALLON 19 j
TANK FIRE, AIR TANK FIRE, AIR COVER GAS 128 REALISTIC 9.2 RELEASE RELEASE RATE PHTS DBL 62 TIME PHASED 0.5 RELEASE
- 35000 GALLONS, INERTED 1
-INSTANTANEOUS l
RELEASE COLD TRAP 5
REALISTIC 0.6 l
FIRE Cs CONTENT 2
- CONSERVATIVE l
Cs CONTENT RAPS CRYOSTILL 81 REALISTIC 5
i FAILURE RELEASE RATE i
- DESIGN BASE i
RELEASE RATE i
12 82 3tn28
'l f
TABLE 2
)
COMPARISON OF RADIOLOGICAL QUALIFICATION REQUIREMENTS WITH ANTICIPATED RELEASES
- 2. CUMULATIVE DOSE l
DOSE (RADS)
CORRESPONDING l
BASIS FOR DOSE FOR QUALIFICATION MORE REALISTIC DOSE RADS l
(.2#+ 8) RADS EVENT
(.2p+ a) RADS l* SSST 1.3 x 108 NONE l
35000 GALLON 5x105 4000 GALLON 1.5 x 104 j
TANK FIRE, AIR TANK FIRE, AIR l
- COVER GAS 650 COVER GAS RELEASE 59 RELEASE
- PHTS DBL 2800 TIME PHASED 28 RELEASE l
)
- 35000 GALLONS, INERTED
-INSTANTANEOUS j
RELEASE
- COLD TRAP 105 REALISTIC 8x103 FIRE Cs CONTENT
- CONSERVATIVE Cs CONTENT
- RAPS CRYOSTILL 3.5 x 103 REALISTIC 341 FAILURE RELEASE RATE
- DESIGN BASE RELEASE RATE I
i 12 ea vss n
\\
TABLE 3 ENVELOPING RADIATION ENVIROPMENTS FOR IN-CONTAINMENT CLASS lE EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT
~
COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System 12 Electrical Power Connectors and Terminations X
Qualified for Max. Environment of Equipment Being Serviced Cable X
Electrical Penetrations X g 12 NIB 202A,B,C 120/208 Vac UPS Panel X
Required for Reactor Shutdown Equip. Used for Accident Monitoring-System 23 4
Chilled Water i
System TBD ECW Pressure Switch X
Required for Maintaining Cell
. Cooling During all Plant Power TBD NCW Pressure Switch X l
_0peration 23ECNV353 Isolation After Water Leak X
Valve Operator 23ECNV354 X
23ECNV400 X
X 23ECNV401j 23ECMOV328 Containment Isolation Valve X
Required to Mitigate the 23ECMOV333 Operators and Position Switches X
Consequences of SSST 23iiCMOV635C X
23NCMOV635B X
1 23NCMOV635A X
23NCMOV631 X
ENVELOPING RADIATION ENVIRO *ENTS FOR IN-CONTAIMENT CLASS lE EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS S0DIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System 23. (Cont.)
23ECMOV338l-Containment Isolation Valve X
Required to Mitigate the 23ECMOV348 l
Operators and Position X
Consequences of SSST 23ECMOV343 /
Switches X
System 25 Nuclear Island HVAC Sys.
25 ARA 0V46C RCB Air Supply Valve Operator X
Required to Mitigate the
& Position Switch Consequences of SSST 25 ARA 0V47C RCB Air Exhaust Valve Operator X
Required to Mitigate the
& Position Switch Consequences of SSST 25 ARK 021, 22 & 23 EI&C Cubicle Unit Coolers X
Required to Provide Cooling to Accident Monitoring Equipment.
System 26B Non-Sodium Fire Protection Sys.
26BTMOVl41 Containment Isolation Valves X
Required to Mitigate the Consequences of SSST System 27 Reactor Contain-ment IaC 271CB0301
- Pressure Sensor (Bellows and X
(See Next Page) 27IC8031 )
NaK Tubing)
- No Electrical Parts In-Containment.
ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS lE EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT Systen 27 '(Cont.)
27ICB026 A-H1
- Containment Vessel Thenno-Note: This equipment is 27ICB027 A-H/
couples designed to monitor the 27ICB028A,B)
- Containment Atmosphere environment associated with 27ICB029A,B )
Thermocouples TMDBD.
It is also utilized 27ICA001A,B
- Containment / Air Sampling to monitor the worst case Filters in-containment DBA.
27RCA0V034 Containment Isolation Valve X
Required to Mitigate the Con-for Sump Pump Discharge sequences of SSST 27AAV001,2,3,4 Containment Vacuum Breaker /
X Valves System 28 Recirculating Gas Cooling 28 MATE 10 Sensors Temperature X
Required for Inert Cell Cooling 1
28MBTE10 Sensors Temperature X
During All Plant Operating 28MBMEl Sensors Moisture X
Conditions 28MAMEl Sensors Moisture X
28MANEl/NSH-1 Switches Liquid Level X
28MBNEl/NSH-1 Switches Liquid Level X
i 28MAK001 A&B Fan Motor X
28MBK001A&B Fan Motor X
28MAMV001A,B Solenoid Drain Valve Operator X
28MBMV001 A,B Solenoid Drain Valve Operator X
28 MAS 0V001A,B Solenoid Valve Pneumatic X
Isolation Valve 28MBS0V001 A,B Solenoid Valve Pneumatic X
i Isolation Valve
- No Electrical Parts In-Containment.
4u-4 TABLE 3 ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS lE EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT Systen 44 Nuclear Island General Purpose Maint. Equip.
i 445RHV033B Containment Isolation Valve X
Required to Mitigate the Operator and Position Switch Consequences of SSST 44SRHV069A,,)
X System 56 Reactor Heat Transport Inst.
and Contr. Sys.
56PRK201A PHTS Na Pump Pony Loop 1 X
Required for Maintaining 56PRK201B PHTS Na Pump Pony Loop 2 X
Forced Circulation of Sodium 56PRK201C PHTS Na Pump Pony Loop 3 X
for Decay Heat Removal even 1
56PRKil2A PHTS Na Pump Drive ARD though Natural Circulation is Bearing Fan Motor Loop 1 X
adequate.
56PRKil2B PHTS Na Pump Drive ARD Bearing Fan Motor Loop 2 X
56PRKil 2C PHTS Na Pump Drive ARD 1
Bearing Fan Motor Loop 3 XJ 56PRST103AP, BP, PHTS Na Pump Tachometer X
Not Required for Sodium j
CP Loop 1, Channel A,B,C Tank Fire Since Plant is Shutdown and Pony Motors 56PRST203AP, BP, PHTS Na Pump Tachometer X
are Activated.
CP Loop 2, Channel A,D C 3
56PRST303AP, BP PHTS Na Pump Tachometer X) 3 CP Loop 3, Channel A,B,C
TABLE 3 ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS 1E EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS S0DIUM BASIS FOR ENVELOPING EQUIPMENT 10 NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST' RADIATION ENVIRONMENT Systen 56 (Cont.)
Reactor Heat Transport Instr.
and Control Sys.
56PRBill AP, BP PHTS Primary PPS Panel, Channel X
Since the signal conditioning CP A, B & C equipment is used for both Reactor Shutdown and Accident 56PRBill AS, BS, PHTS Secondary PPS Panel, X
Monitoring functions, the equipment is qualified for the CS Channel A, B & C Sodium Tank Fire even though
-_/
the reactor is shutdown.
56PRPT124AP Reactor Inlet Pressure 56PRPT125AP Transmitter, Loop 1 X
Pressure sensors are located 56PRPT224BP Reactor Inlet Pressure in an inert cell which are 56PRPT225BP Transmitter, Loop 2 X
designed for the enveloping 56PRPT324CP Reactor Inlet Pressure 30 year background radiation 56RPRT325CP Transmitter, Loop 3 X
}
while the transmitters are located in an air cell and are qualified for the cover gas release.
56PRTE128A IXH Outlet Temperature Equipment located in inert 56PRTE128B Sensors, Loop 1, Channels cells and is qualified for 56PRTE128C A,B,C enveloping background 56PRTE228A IXH Outlet Temperature 56PRTE228B Sensors, Loop 2, Channels 56PRTE228C A,B,C
/
i
TABLE 3 ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS 1E EQUIPMENT
~
APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System 56 (Cont.)
56PRTE328A IXH Outlet Temperature Equipment located in inert 56PRTE328B Sensors, Loop 3, Channels cells and is qualified for 56PRTE328C A, B, C enveloping background radiation.
56PRFE125AS PHTS Sodium PM Flowmeter 56PRFE125BS Sensors, Loop 1, Channels 56PRFE125CS A, B, C 56PRFE225AS PHTS Sodium PM Flowmeter 56PRFE225BS Sensors, Loop 2, Channels 56PRFE225CS A,B,C 56PRFE325AS PHTS Sodium PM Flowmeter 56PRFE325BS Sensors, Loop 3, Channels 56PRFE325CS A,B,C 56PRTE129A,B P:!TS Sodium Pump Outlet 56PRTE130A,B Temperature Sensors, Loop 1 56PRTE229A,B PHTS Sodium Pump Outlet 56PRTE320A,B Temperature Sensors, Loop 2 56PRTE329A,B PHTS Sodium Pump Outlet 56PRTE330A,B Temperature Sensors, Loop 3 t
s System 31 4
Reactor System 31SDR003 Solenoid Scram Valves X
Required to function during the most severe DBA occuring during plant operation.
TABLE 3 ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS 1E EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT Systen 81 Auxiliary Liquid-~
Metal Sys.
81 PPHV131 Val. (Oper.) Makeup Pump Drain X
Required to function during Tank the most severe DBA occuring during plant operation.
81 PPHV135 Val. (Oper.) Cold Trap A Equipment located in inert Outl et cells and is qualified to 81 PPHV136 Val. (Oper.) Cold Trap A enveloping background Inlet radiation. The 30 year 81 PPHV143 Val. (Oper.) Cold Trap A background radiation is orders Outlet of magnitude larger than accident 81 PPHV149 Val. (Oper.) Cold Trap Outlet environment.
Hdr 81 PPHV153 Val. Oper, Overflow Vessel Return 81 PPTE100 Temperature, Overflow Heat Exchanger Outlet (T/C) 81 PPTE101 Temperature, Overflow Heat Exchanger.0utlet (T/C) 81 PPE003B Cabinet, Variable Transformer X
Required to function during Drive the most severe DBA occuring 81 PPB 002A Local Panel, Primary X
during plant operation.
Processing 81 PPB 0028 Local Panel, Primary X
Processing 81 PPP001 A Pump, Primary Na Makeup X
j J
TABLE 3 ENVELOPING RADIATION ENVIROMENTS FOR IN-CONTAINMENT CLASS lE EQUIFMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System 81 (Cont.)
81 PPP001B Pump, Primary Na Makeup X
Required to function during 81 PPE001 A Cabinet, Makeup Pump Control X
the most severe DBA occuring 81 PPE001B Cabinet, Makeup Pump Control X
during plant operation.
81 PPE002A Cabinet, Makeup Pump Capacitor X
81 PPE002B Cabinet, Makeup Pump Capacitor X
81 PPE003A Cabinet, Variable Transformer Xj Drive 81 PPHV102 Valve (Operator), Overflow Equipment located in inert Heat Exchanger Bypass cells and is qualified to 81 PPHV103 Valve (Operator), Overflow enveloping background Heat Exchanger Inlet radiation. The 30 year 81 PPHV109 Valve (Operator), Cold Trap background radiation is orders Inlet Header of magnitude larger than 81 PPHV128 Valve (Operator), Cold Trap accident environment.
B Inlet 81 PPHV102A Valve Accessory Package X
Required to function during 81 PPHV103A X
the most severe DBA occuring 81 PPHV109A X
during plant operation.
81 PPHV131 A X
81 PPHV136A X
81 PPHV143A X
81 PPHV149A X
81 PPHV153A Xj System 82 Inert Gas Receiv-ing & Processing System 82CGHV154B Containment Iso. Valve Opera-X Required to mitigate the tor & Position Switches consequences of SSST
TABLE 3
~
ENVELOPING RADIATION ENVIR0tetENTS FOR IN-CONTAINMENT CLASS lE EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS S0DIUM BASIS FOR ENVELOPING EQ'JIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System 82'(Cont.)
82CGPV501B Containment Iso. Yalve Operator X
Required to mitigate the
& Position Switches consequences of SSST 82CGPV351B X
X 82CGHV153B 82RPHV137A X
l 82RPHV138A X
1 82APHV001 Xj 82CFPT328 Pressure Sensor, Rtr. Cover X
Required for Accident Gas Monitoring during the 82CGPT329 X
worst case containment DBA.
82CGPT330 X
82CGA013A,B Compressors Rtr. Cover Gas X
Radiation Monitors System 92 Reactor Vessel Instr. Sys.
92AAB002A Reactor Coolant Operating X)
Level sensor located in Level Sensor (Connector) l Reactor and designed for 92AAB0028 X
background radiation over 92AAB002C X
life sensor while connector is qualified for worst case DBA. Although the Reactor is shutdown during a tank fire the connectors are qualified for the tank fire to assure that the sodium level can be monitored (Accident Monitoring function).
-..m
TABLE 3 ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS 1E EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System 95' Flux Monitoring System 95AAB006A, B, C Wide Range Preamplifiers X
Required for Accident Monitoring for tank fire DBA.
95AAB008A, B, C Wide Range Detector Assemblies Equipme..t located in inert cells and qualified for background radiation. The 30 year background radiation is orders of magnitude larger than accident environment.
95AAB003A, B, C Power Range Junction Boxes X
Equipment qualified for the most severe DBA occuring during plant operation.
95AAB004A, B, C Power Range Detector Assemblies Eouipment located in inert cells and qualified for background radiation. The 30 year background radiation is orders of magnitude larger than accident environment.
ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS lE EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System 96 TBD Head Access Area Monitor X?
Required to Mitigate the TBD Head Access Area Monitor X
Consequences of SSST TBD Head Acces Area Monitor Xl 96PMB002A RCB Exhaust Monitors X)
Required for Isolation 96PMB0028 RCB Exhaust Monitors X
Containment During the 96PMB002C RCB Exhaust Monitors Xj Worst Case Containment DBA.
Since these Detectors Must Function a Short Time, They Are Qualified for the Enveloping Cover Gas Release 96PB043 RCB High Range Radiation Required Instrumentation for Monitor
- TMB DB. Also used for 96 PPB 044 RCB High Range Radiation Accident Monitoring to Monitor
- Monitor the Consequences of 96 PPB 045 RCB High Range Radiation the Worst Case Containment Monitor
- J DB A..
96PMRE090A&B Radiation Monitors for Cover X
Required to Function During 96PMRE091A88 Gas and Following the Most Severe Containment DBA.
96PPRE-046A,B,C Accident Area Monitor for Cells X
Required to Monitor the Con-161C,D,E sequences of the Worst Case 96PPRE-047A,B,C Accident Area Monitor for Cells X
Containment DBA.
105E,Y & 111 96PPRE-048A,B,C Accident Area Monitor for Cells X
165, 167 & 106 96PPRE-002 Accident Area Monitor for Cell X
163 96PPRE-008 Accident Area Monitor for Cell X
105S (Valve Gallery) d
- Located in the Annulus
ENVELOPING RADIATION ENVIRONMENTS FOR IN-CONTAINMENT CLASS lE EQUIPMENT APPLICABLE ENVELOPING RADIATION ENVIRONMENT COVER GAS SODIUM BASIS FOR ENVELOPING EQUIPMENT ID NO.
EQUIPMENT DESCRIPTION RELEASE TANK FIRE SSST RADIATION ENVIRONMENT System % '(Cont'd) 96PPRE-014 Accident Area Monitor for Cell X 1, Required to Monitor the Con-105A (Access Area) sequences of the Worst Case 96PPRE-032 Accident Area Monitor for Cell X
Containment DBA.
105V ( Access Area)
)
96PPRE-037 Accident Area Monitor for Cell X/
105F (Make-up Pump Valve Operating Gallery) s A
Y
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s
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