ML19209C271: Difference between revisions
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SOETON EOlsON COMPANY acNamA6 arrices aco savtaroN star:7 SO ETON. M A5 5 ACNU SETTE O 219 9 STE5 HEN b ROSEN MANAGEE NUCLEAR ENGINEEA8NS DEPARTMENT NED 79- 73 October 5,1979 Harold R. Denton, D! rector Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 | SOETON EOlsON COMPANY acNamA6 arrices aco savtaroN star:7 SO ETON. M A5 5 ACNU SETTE O 219 9 STE5 HEN b ROSEN MANAGEE NUCLEAR ENGINEEA8NS DEPARTMENT NED 79- 73 October 5,1979 Harold R. Denton, D! rector Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 | ||
Line 33: | Line 32: | ||
7910120 ] | 7910120 ] | ||
BOSTON EDISQN COMPANY H. R. Denton Page 2 NED 79-73 Boston Edison justifies continued operation of Pilgrim Nuclear Power Station I based on: | BOSTON EDISQN COMPANY H. R. Denton Page 2 NED 79-73 Boston Edison justifies continued operation of Pilgrim Nuclear Power Station I based on: | ||
: 1. The comprehensive review of the environmental interactions (due to analyzed high energy pipe breaks) between non-safety systems and safety systems; and | : 1. The comprehensive review of the environmental interactions (due to analyzed high energy pipe breaks) between non-safety systems and safety systems; and | ||
Line 46: | Line 44: | ||
: 3. Environmental Interaction Tabio, Part !! | : 3. Environmental Interaction Tabio, Part !! | ||
1 1 1n 177 i l9d J- | 1 1 1n 177 i l9d J- | ||
Commonwealth of Massachusetts) | Commonwealth of Massachusetts) | ||
County of Suifolk ) | County of Suifolk ) | ||
Line 55: | Line 51: | ||
a | a | ||
PILGRIM NUCLEAR POWER STATION 1 ENVIRONMENTAL INTERACTION TABLE PARTS I & II Legend | PILGRIM NUCLEAR POWER STATION 1 ENVIRONMENTAL INTERACTION TABLE PARTS I & II Legend | ||
: 1. Environmental Induced malfunction may provide adverse response, i.e. | : 1. Environmental Induced malfunction may provide adverse response, i.e. | ||
Line 63: | Line 58: | ||
: 4. System will not experience adverse environment. | : 4. System will not experience adverse environment. | ||
Abbreviations M.G. -Motor Generator MCC -Motor Control Center SYS -System INST -Instrumentation TRANS -Transmi tter MONIT -Moni toring RPS -Reactor Protection System RBCCW -Reactor Building Closed Cooling Water Systen RWCU -Reactor Water Clean Up System ISOL -Isolation RPV -Reactor Pressure Yessel LIQ -Liquid CRD -Control Rod Drive RHR -Residual Heat Removal System DW -Drywell RB -Reactor Building TB -Turbine Building CB -Control Building CR -Control Room N/A -Not Applicable OPER -Valve Operator FDWTR -Feedwater k 33-4 17 4 i 1[ | Abbreviations M.G. -Motor Generator MCC -Motor Control Center SYS -System INST -Instrumentation TRANS -Transmi tter MONIT -Moni toring RPS -Reactor Protection System RBCCW -Reactor Building Closed Cooling Water Systen RWCU -Reactor Water Clean Up System ISOL -Isolation RPV -Reactor Pressure Yessel LIQ -Liquid CRD -Control Rod Drive RHR -Residual Heat Removal System DW -Drywell RB -Reactor Building TB -Turbine Building CB -Control Building CR -Control Room N/A -Not Applicable OPER -Valve Operator FDWTR -Feedwater k 33-4 17 4 i 1[ | ||
) | ) | ||
PILGRIM NUCLEAR POWER STATION ENVIRONMENTAL INTERACTION TABLE PART I Non-safety systems whose environmentally induced malfunccion cannot affect plant sTfety response during a high energy pipe break. | PILGRIM NUCLEAR POWER STATION ENVIRONMENTAL INTERACTION TABLE PART I Non-safety systems whose environmentally induced malfunccion cannot affect plant sTfety response during a high energy pipe break. | ||
: 1. Air Ejector Offgas Radiation Monitoring System | : 1. Air Ejector Offgas Radiation Monitoring System | ||
Line 95: | Line 87: | ||
, _$ y. | , _$ y. | ||
2. | 2. | ||
: 24. Generator | : 24. Generator | ||
Line 103: | Line 94: | ||
: 28. Security System | : 28. Security System | ||
: 29. 120 VAC POWER SYSTDI | : 29. 120 VAC POWER SYSTDI | ||
] 14ei. u'? l 7, aK | ] 14ei. u'? l 7, aK f | ||
f | |||
Pg. 1 of-4 PflGRIM NUCLIAR l'0WER SIAT!DN 1 N i NVI RoretINT At INIF RAli!ON TAl:1 f m PART II c DJ | |||
Pg. 1 of-4 PflGRIM NUCLIAR l'0WER SIAT!DN 1 N i NVI RoretINT At INIF RAli!ON TAl:1 f m PART II c | |||
DJ | |||
~ | ~ | ||
Main Ste.vi reeikater LDCA 1~ | Main Ste.vi reeikater LDCA 1~ | ||
Insi4T7e sTde Reactor Tu~rfine Reactor RWCU RCIC HRI - | Insi4T7e sTde Reactor Tu~rfine Reactor RWCU RCIC HRI - | ||
Systems __ _ Location Small Turbine Re c t'ar Reactor Reactor | Systems __ _ Location Small Turbine Re c t'ar Reactor Reactor | ||
_ L a rge _Rullding Bul g 3_ Inside Building _ Bui ldirl Small Lar3e, F M ng Buildin3_,,Buildin t | _ L a rge _Rullding Bul g 3_ Inside Building _ Bui ldirl Small Lar3e, F M ng Buildin3_,,Buildin t Neutron flonitoring_Sys eSource Range DW/RB/CR 2 2 2 4 2 2 4 2 2 2 _4 4 olocal Power Range DW/RB/CR 2 2 2 4 2 2 4 2 eRod Block Monitor 2 ]_ 4 4 DW/RB/CR 2 2 2 4 2 2 4 2 2 ' | ||
eTransverse In-core f 4 4 Probe DW/RB/CR 2 2 2 4 2 2 4 2 2 2 4 4 | |||
Neutron flonitoring_Sys | _'tBCCW (Pat 65) RB 4 4 2 4 4 2 4 4 4 I 2 4 4 Fire Protection RB/TB 4 4 2 2 4 2 2 4 4 2 ? 2 HVAC All 2 2 2 2 2 2 2 2 2 2 2 Makeuo Water Treatment TB 4 4 Equipment and Floor p ain System 2 2 4 2 2 4 4 2 li_ 2 | ||
eSource Range DW/RB/CR 2 2 2 4 2 2 4 2 2 2 _4 4 olocal Power Range DW/RB/CR 2 2 2 4 2 2 4 2 eRod Block Monitor 2 ]_ 4 4 DW/RB/CR 2 2 2 4 2 2 4 2 2 ' | |||
eTransverse In-core f 4 4 Probe DW/RB/CR 2 2 2 4 2 2 4 2 2 | |||
2 4 4 | |||
_'tBCCW (Pat 65) RB 4 4 2 4 4 2 4 4 4 I | |||
2 4 4 Fire Protection RB/TB 4 4 2 2 4 2 2 4 4 2 ? 2 HVAC All 2 2 2 2 2 2 2 2 2 2 2 Makeuo Water Treatment TB 4 4 Equipment and Floor p ain System 2 2 4 2 2 4 4 2 li_ 2 | |||
) ? | ) ? | ||
RB/TB/DW 2 2 4 4 2 4 4 ? ? | RB/TB/DW 2 2 4 4 2 4 4 ? ? | ||
Line 133: | Line 109: | ||
& Turb. Seallnq Sys. TB 4 4 ? 2 4 7, 2 Circ. Wtr. __t_ c , 7 2 2 Circulating Water Sys. House 4 4 4 4 4 4 4 4 4 4 To5densate Demineralizer , | & Turb. Seallnq Sys. TB 4 4 ? 2 4 7, 2 Circ. Wtr. __t_ c , 7 2 2 Circulating Water Sys. House 4 4 4 4 4 4 4 4 4 4 To5densate Demineralizer , | ||
4 4 System TB 4 4 2 2 4 2 2 4 4 2 2 2 | 4 4 System TB 4 4 2 2 4 2 2 4 4 2 2 2 | ||
_ Condensate System TB 4 4 4 2 4 4 2 4 4 4 Condensate Transfer & 4 4 Storage System TB 4 4 4 2 4 4 2 4 4 4 4 4 Unit AC Power Source TB 4 4 2 2 | _ Condensate System TB 4 4 4 2 4 4 2 4 4 4 Condensate Transfer & 4 4 Storage System TB 4 4 4 2 4 4 2 4 4 4 4 4 Unit AC Power Source TB 4 4 2 2 4 2 2 4 4 i | ||
4 2 2 4 4 i | |||
2 2 2 | 2 2 2 | ||
~ | ~ | ||
Pg. 2 of 4 .- | Pg. 2 of 4 .- | ||
Line 144: | Line 117: | ||
Inside inside -ReacF' e ' Turbine Reactor RWCU -RCIC hfCl - | Inside inside -ReacF' e ' Turbine Reactor RWCU -RCIC hfCl - | ||
Systems Small Large Turbine Reactor Reactor Reactor | Systems Small Large Turbine Reactor Reactor Reactor | ||
_ Location Building Building Inside Building Building Small _ _ _ | _ Location Building Building Inside Building Building Small _ _ _ | ||
Lag Building Building Building 24V DC Power Sys. RB 4 4 2 2 | Lag Building Building Building 24V DC Power Sys. RB 4 4 2 2 | ||
_4 2 2 4 4 2 2 - 2 Cont. Atmos. Monitoring DW/RB 2 2 2 4 2 2 4 2 2 2 2 2 Reactor Vessel Hd Vent DW 2 2 Main Turb. & Controls TB 4 4 2 4 4 h h 4 4 4 4 4 a 2 4 4 Reactor Manual Control 2 | _4 2 2 4 4 2 2 - 2 Cont. Atmos. Monitoring DW/RB 2 2 2 4 2 2 4 2 2 2 2 2 Reactor Vessel Hd Vent DW 2 2 Main Turb. & Controls TB 4 4 2 4 4 h h 4 4 4 4 4 a 2 4 4 Reactor Manual Control 2 | ||
_4 4 4 4 4 CR 4 4 4 4 4 4 4 4 4 4 CRD Hydraulic System 4 4 JNon-S(RAM) RB 4 4 a Safety / Relief Valve 2 4 ,_ 2 4 4 4 4 4 | _4 4 4 4 4 CR 4 4 4 4 4 4 4 4 4 4 CRD Hydraulic System 4 4 JNon-S(RAM) RB 4 4 a Safety / Relief Valve 2 4 ,_ 2 4 4 4 4 4 4 | ||
_Sys. (Non-ADS) DW/RB 3 3 3 4 3 3 4 3 3 4 4 4 Recirculation System ePumps DW 2 2 4 4 2 4 4 2 evalve & Operators 2_ 4 4 4 DW 2 2 4 4 2 4 4 2 2 4 4 4 eMG Sets TB/RB d 4 4 4 4 4 4 4 4 4 4 4 eMCC TB/RB 4 4 4 4 4 4 4 4 4 4 4 4 eFlow Control CR/RB 4 4 4 4 4 4 4 4 4 4 eControTTns t. 4 4 Transmitters RB 4 4 4 4 4 4 4 4 4 4 4 4 | |||
4 | __ l S | ||
_Sys. (Non-ADS) DW/RB 3 3 3 4 3 3 4 3 3 4 4 4 | 9 9 | ||
Recirculation System | |||
ePumps DW 2 2 4 4 2 4 4 2 evalve & Operators 2_ 4 4 4 DW 2 2 4 4 2 4 4 2 2 4 4 4 eMG Sets TB/RB d 4 4 4 4 4 4 4 4 4 4 4 eMCC TB/RB 4 4 4 4 4 4 4 4 4 4 4 4 eFlow Control CR/RB 4 4 4 4 4 4 4 4 4 4 eControTTns t. 4 4 Transmitters RB 4 4 4 4 4 4 4 4 4 4 4 4 | |||
__ l | |||
9 | |||
Pg. 3 or 4 ~ | Pg. 3 or 4 ~ | ||
PILf. RIM NUCLFAR POWER STATION 1 INVIRONMlNTAL INI[HAC110N TAlttf F'' | PILf. RIM NUCLFAR POWER STATION 1 INVIRONMlNTAL INI[HAC110N TAlttf F'' | ||
PART ll C | PART ll C | ||
Line 173: | Line 135: | ||
feedwater | feedwater | ||
/ | / | ||
ePumps TB 4 4 4 2 4 4 2 4 4 4 4 4 | ePumps TB 4 4 4 2 4 4 2 4 4 4 4 4 eFlow Element TB 2 2 4 4 2 4 4 2 2 4 4 4 elevel Elements DW/RB 4 4 4 2 4 4 2 4 4 4 4 4 evalves & Operators TB 4 4 4 2 4 4 2 4 4 4 4 4 o!1CC TB 4 4 4 4 4 4 4 4 4 4 4 4 eFlow Control CR 4 4 4 4 4 4 4 4 4 4 4 4 erW Peating TB 4 4 4 2 4 4 4 4 4 4 4 4 einstrument Air TB 4 4 4 2 4 4 4 4 4 4 4 4 eControl Inst. Trans. TB 4 4 2 2 4 2 2 4 4 4 4 4 Turtelne Pressure fontrols eRypass Valves TB 4 4 4 2 4 I | ||
eFlow Element TB 2 2 4 4 2 4 4 | |||
2 2 4 4 4 elevel Elements DW/RB 4 4 4 2 4 4 2 4 4 4 4 4 evalves & Operators TB 4 4 4 2 4 4 2 4 4 4 4 4 o!1CC TB 4 4 4 4 4 4 4 4 4 4 4 4 eFlow Control CR 4 4 4 4 4 4 4 4 4 4 4 4 erW Peating TB 4 4 4 2 4 4 4 4 4 4 4 4 einstrument Air TB 4 4 4 2 4 4 4 4 4 4 4 4 eControl Inst. Trans. TB 4 4 2 2 4 2 2 4 4 4 4 4 Turtelne Pressure fontrols eRypass Valves TB 4 4 4 2 4 I | |||
4 2 4 4 i 4 4 4__ | 4 2 4 4 i 4 4 4__ | ||
_ ePressure Sensors TB 4 4 4 2 4 4 2 4 4 4 4 4 eControl Systems CR 4 4 4 4 4 4 4 , 4 4 '; 4 4 | _ ePressure Sensors TB 4 4 4 2 4 4 2 4 4 4 4 4 eControl Systems CR 4 4 4 4 4 4 4 , 4 4 '; 4 4 O | ||
e 4 | |||
4 | |||
i ovr | i ovr m | ||
m | |||
rn g oi 4 td 4 4 l cl C ai f eu iiRB ' | rn g oi 4 td 4 4 l cl C ai f eu iiRB ' | ||
~ | ~ | ||
g rn oi 4 td 4 4 | g rn oi 4 td 4 4 | ||
' 0 cl ai | ' 0 cl ai | ||
' lC eu RRB p | ' lC eu RRB p | ||
rg n oi 4 | rg n oi 4 td 4 4 Ucl C ai W eu RRB 4 '- eg _ | ||
td 4 4 Ucl C ai W eu RRB | |||
4 '- eg _ | |||
r 2 4 4 f a L | r 2 4 4 f a L | ||
o A C | o A C | ||
Line 206: | Line 152: | ||
1 4 4 | 1 4 4 | ||
. a g n r | . a g n r | ||
P S | P S g | ||
en N ni 4 2 4 i d hl Wiu | |||
'T B - | 'T B - | ||
g r oi rn 4 4 4 1 I e td t cl Nnt a ai OA weu IT T dhB e | g r oi rn 4 4 4 1 I e td t cl Nnt a ai OA weu IT T dhB e | ||
Line 214: | Line 159: | ||
Rt id 2 4 4 MAi nit f Rl I | Rt id 2 4 4 MAi nit f Rl I | ||
s n | s n | ||
M NR RIA - | M NR RIA - | ||
A P g IL IA en M 4 2 4 CT ini d UN tl NI ri M ~ uu MN TB O | A P g IL IA en M 4 2 4 CT ini d UN tl NI ri M ~ uu MN TB O |
Latest revision as of 06:17, 2 February 2020
ML19209C271 | |
Person / Time | |
---|---|
Site: | Pilgrim, 05000471 |
Issue date: | 10/05/1979 |
From: | Rosen S BOSTON EDISON CO. |
To: | Harold Denton Office of Nuclear Reactor Regulation |
References | |
NED-79-73, NUDOCS 7910120314 | |
Download: ML19209C271 (10) | |
Text
s 3*
SOETON EOlsON COMPANY acNamA6 arrices aco savtaroN star:7 SO ETON. M A5 5 ACNU SETTE O 219 9 STE5 HEN b ROSEN MANAGEE NUCLEAR ENGINEEA8NS DEPARTMENT NED 79- 73 October 5,1979 Harold R. Denton, D! rector Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Resoonse to Letter Entitled, " Potential Unreviewed Safety Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems", Harold R. Denton to All Operatinn Linht Water Reactors, Sectember 17, 1979
Dear Mr. Denton:
Please find enclosed per the request of the subject letter an assessment of Pilgrim Nuclear Power Station I concerning the potential ef fects of non-safety system failures (caused by a high energy pipe break) on safety system performance. More specific and' ccmprehensive information and analysis requested by the NRC Staff (Thursday briefing, September 20, 1979) is a;so contained.
The assessment has identified no impacts on required safety actions and one potential analysis conclusion which would increase the consequences of a high energy pipe break. The consequences of analyzed high energy pipe breaks considered are:
- 1. Calculated Peak Clad Temperature
- 2. Peak Containment Pressure
- 3. Peak Suppression Pool Temperature 4 Radiological Releases in particular, the assessment concludes that Pilgrim Statien air operated reactor head vent valves (2" line) utilize solenoid valves of the generic type outlined in NRC Sulletin 79-01A and a high energy pipe break environment could cause the two series head vent valves to open during the initial phases of the event. An analysis shows that such a bounded worst case may have a + 10 0F impact on Peak Clad Temperature. The analysis conservatively assumes that both head vent valves open completely and instantaneously coincident witn the worst pipe break inside containment, i
l l 2:1')c ' ;l I. (
7910120 ]
BOSTON EDISQN COMPANY H. R. Denton Page 2 NED 79-73 Boston Edison justifies continued operation of Pilgrim Nuclear Power Station I based on:
- 1. The comprehensive review of the environmental interactions (due to analyzed high energy pipe breaks) between non-safety systems and safety systems; and
- 2. The comDined low probability and relative insignificant ef fect of a " Pipe Break inside Containrent" result!ng in inadvertent operation of the reactor head vent valves, it is Bostor, ddison's Intent to eliminate the potential interaction of a " Pipe Break inside Containrent" and reactor head vent valve maloperation during the next scheduled or unscheduled plant outage.
Very truly yours, s_ )
.)
Enclosures:
- 1. Legend and abbreviations used in the "Environrental Interaction Table",
Parts I and 11.
- 2. Environmenta l Interaction Table, Part !
- 3. Environmental Interaction Tabio, Part !!
1 1 1n 177 i l9d J-
Commonwealth of Massachusetts)
County of Suifolk )
Then personally appeared before me Stephen L. Rosen, who being duly sworn, did state that he is the Nuclear Engineering Manager of Boston Edison Company, that he is duly authori::ed to execute the foregoing statement in the name and on be-haif of Bostor. Edisen Company and tpat the statements are true to the be st of his knowledge and belief. j h '[ A
/s/ Dorothy M. Looes Notary Public My Commission E-mires: July 6, 1984 4 4 ? ' 's M *1 l . ,
a
PILGRIM NUCLEAR POWER STATION 1 ENVIRONMENTAL INTERACTION TABLE PARTS I & II Legend
- 1. Environmental Induced malfunction may provide adverse response, i.e.
oIncreased Drywell pressure eIncreased wetwell pressure eIncreased suppression pool tenperature eIncreased Fuel Clad Temperature
- 2. Environmental induced malfunction will not provide advarse response.
- 3. System is qualified for adverse environment.
- 4. System will not experience adverse environment.
Abbreviations M.G. -Motor Generator MCC -Motor Control Center SYS -System INST -Instrumentation TRANS -Transmi tter MONIT -Moni toring RPS -Reactor Protection System RBCCW -Reactor Building Closed Cooling Water Systen RWCU -Reactor Water Clean Up System ISOL -Isolation RPV -Reactor Pressure Yessel LIQ -Liquid CRD -Control Rod Drive RHR -Residual Heat Removal System DW -Drywell RB -Reactor Building TB -Turbine Building CB -Control Building CR -Control Room N/A -Not Applicable OPER -Valve Operator FDWTR -Feedwater k 33-4 17 4 i 1[
)
PILGRIM NUCLEAR POWER STATION ENVIRONMENTAL INTERACTION TABLE PART I Non-safety systems whose environmentally induced malfunccion cannot affect plant sTfety response during a high energy pipe break.
- 1. Air Ejector Offgas Radiation Monitoring System
- 2. Main Stack Radiation Monitoring System
- 3. Building Exhaust Vent Radiation Monitoring System
- 4. Radwaste Liquid Discharge Radiation Monitoring System
- 5. xBCCW Liquid Radiation Monitoring System
- 6. 'ndensate Storage Inlet Radiation Monitoring System
- 7. Standby Gas Treatment Exhaust Radiation Monitoring System
- 8. Control Room Ventilation Intake Radiation Monitoring System
- 9. Area Radiation Monitoring System
- 10. Environs Radiation Monitoring System
- 11. Fuel Pool Cooling and Cleanup 5ystem
- 12. Service Air System
- 13. Portable and Sanitary Water system
- 14. Process Sanp'. ing System
- 15. Communications System
- 16. Station Lighting
- 17. Main Condenser Gas Removal and Turbine See',ing System
- 18. Process Computer (Parts - Rod Worth Minimizer Program when <10% Rx.
Power is Safety Related)
- 19. Instrument Air System (Parts - Safety Related Accumulators,, Valves and Piping not included) 20,. Standby Liquid Control Sys (Parts)
- 21. Fuel Handling Eqaipmer.t
- 22. Screen Wash and H',po-Chlorination System
- 23. Maintenance Monorails and Hoists ,- ,
,l44 i
, _$ y.
2.
- 24. Generator
- 25. Generator Cooling
- 26. Generator Excitation
- 27. Turbine Building Closed Cooling Water system
- 28. Security System
- 29. 120 VAC POWER SYSTDI
] 14ei. u'? l 7, aK f
Pg. 1 of-4 PflGRIM NUCLIAR l'0WER SIAT!DN 1 N i NVI RoretINT At INIF RAli!ON TAl:1 f m PART II c DJ
~
Main Ste.vi reeikater LDCA 1~
Insi4T7e sTde Reactor Tu~rfine Reactor RWCU RCIC HRI -
Systems __ _ Location Small Turbine Re c t'ar Reactor Reactor
_ L a rge _Rullding Bul g 3_ Inside Building _ Bui ldirl Small Lar3e, F M ng Buildin3_,,Buildin t Neutron flonitoring_Sys eSource Range DW/RB/CR 2 2 2 4 2 2 4 2 2 2 _4 4 olocal Power Range DW/RB/CR 2 2 2 4 2 2 4 2 eRod Block Monitor 2 ]_ 4 4 DW/RB/CR 2 2 2 4 2 2 4 2 2 '
eTransverse In-core f 4 4 Probe DW/RB/CR 2 2 2 4 2 2 4 2 2 2 4 4
_'tBCCW (Pat 65) RB 4 4 2 4 4 2 4 4 4 I 2 4 4 Fire Protection RB/TB 4 4 2 2 4 2 2 4 4 2 ? 2 HVAC All 2 2 2 2 2 2 2 2 2 2 2 Makeuo Water Treatment TB 4 4 Equipment and Floor p ain System 2 2 4 2 2 4 4 2 li_ 2
) ?
RB/TB/DW 2 2 4 4 2 4 4 ? ?
F.a W Cond. Gas Removal _ d 4 A
& Turb. Seallnq Sys. TB 4 4 ? 2 4 7, 2 Circ. Wtr. __t_ c , 7 2 2 Circulating Water Sys. House 4 4 4 4 4 4 4 4 4 4 To5densate Demineralizer ,
4 4 System TB 4 4 2 2 4 2 2 4 4 2 2 2
_ Condensate System TB 4 4 4 2 4 4 2 4 4 4 Condensate Transfer & 4 4 Storage System TB 4 4 4 2 4 4 2 4 4 4 4 4 Unit AC Power Source TB 4 4 2 2 4 2 2 4 4 i
2 2 2
~
Pg. 2 of 4 .-
PILCRIM NUCLFAR POW [R STATION 1 CO INVIRONMINIAl INILRACTION IABLF m PART !! c-CM Main Stemi reedwater (A v
Inside inside -ReacF' e ' Turbine Reactor RWCU -RCIC hfCl -
Systems Small Large Turbine Reactor Reactor Reactor
_ Location Building Building Inside Building Building Small _ _ _
Lag Building Building Building 24V DC Power Sys. RB 4 4 2 2
_4 2 2 4 4 2 2 - 2 Cont. Atmos. Monitoring DW/RB 2 2 2 4 2 2 4 2 2 2 2 2 Reactor Vessel Hd Vent DW 2 2 Main Turb. & Controls TB 4 4 2 4 4 h h 4 4 4 4 4 a 2 4 4 Reactor Manual Control 2
_4 4 4 4 4 CR 4 4 4 4 4 4 4 4 4 4 CRD Hydraulic System 4 4 JNon-S(RAM) RB 4 4 a Safety / Relief Valve 2 4 ,_ 2 4 4 4 4 4 4
_Sys. (Non-ADS) DW/RB 3 3 3 4 3 3 4 3 3 4 4 4 Recirculation System ePumps DW 2 2 4 4 2 4 4 2 evalve & Operators 2_ 4 4 4 DW 2 2 4 4 2 4 4 2 2 4 4 4 eMG Sets TB/RB d 4 4 4 4 4 4 4 4 4 4 4 eMCC TB/RB 4 4 4 4 4 4 4 4 4 4 4 4 eFlow Control CR/RB 4 4 4 4 4 4 4 4 4 4 eControTTns t. 4 4 Transmitters RB 4 4 4 4 4 4 4 4 4 4 4 4
__ l S
9 9
Pg. 3 or 4 ~
PILf. RIM NUCLFAR POWER STATION 1 INVIRONMlNTAL INI[HAC110N TAlttf F
PART ll C
~~
N Main Ste,un '
IEEiwater IDCA PWCU FRCIC liRI Inside IMde- W icior Tulk ne Reactor Turtiine Reactor Reactor
~
Systems Location Small _Large Reactor Building Building Inside Building Building Small ta rge _ Building _ Building , BuildinL "~
/
ePumps TB 4 4 4 2 4 4 2 4 4 4 4 4 eFlow Element TB 2 2 4 4 2 4 4 2 2 4 4 4 elevel Elements DW/RB 4 4 4 2 4 4 2 4 4 4 4 4 evalves & Operators TB 4 4 4 2 4 4 2 4 4 4 4 4 o!1CC TB 4 4 4 4 4 4 4 4 4 4 4 4 eFlow Control CR 4 4 4 4 4 4 4 4 4 4 4 4 erW Peating TB 4 4 4 2 4 4 4 4 4 4 4 4 einstrument Air TB 4 4 4 2 4 4 4 4 4 4 4 4 eControl Inst. Trans. TB 4 4 2 2 4 2 2 4 4 4 4 4 Turtelne Pressure fontrols eRypass Valves TB 4 4 4 2 4 I
4 2 4 4 i 4 4 4__
_ ePressure Sensors TB 4 4 4 2 4 4 2 4 4 4 4 4 eControl Systems CR 4 4 4 4 4 4 4 , 4 4 '; 4 4 O
e 4
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rn g oi 4 td 4 4 l cl C ai f eu iiRB '
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