ML20052C463
| ML20052C463 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/06/1982 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | SHOREHAM OPPONENTS COALITION, SUFFOLK COUNTY, NY |
| Shared Package | |
| ML20052C459 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8205050011 | |
| Download: ML20052C463 (15) | |
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4/6/82 TABLE 1 SNPS CONFORMANCE TO REGULATORY GUIDE 1.97, REVISION 2 Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 1. Control Rod Complete Position
- 2. Neutron Flux Later Existing equipment will remain intact.
Await BWR Owners Group Generic Solution.
- 3. Coolant Level Later Await BWR Owners in Reactor Group Generic Solution. (Part of Study discussed in item #13.)
- 4. Reactor Coolant 6/83 Included in Post -
System (RCS Accident Sample Soluble Boron System Concentration (Sample)
- 5. RCS Pressure 6/83 Required instrumentation already included in design.
Transmitters are being qualified to applicable IEEE Standards.
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NOTE: Some requirements appear more than once in the guide.
They are listed below only once, however, in the order that they first appear in Table 1 of the guide.
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t Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 6. Main Steamline 6/83 Required instrumen-Isolation Valves tation already in-Leakage Control cluded in design.
System Pressure Transmitters are being qualificd to applicable IEEE Standards.
- 7. Primary System Fuel Load Required instrumen-Safety Relief tation already in-Valve Positions cluded in design.
- 8. Primary Contain- Fuel Load Required instrumen-ment Pressure tation already in-(Drywell) cluded in design.
8A. Primary Contain- Fuel Load Required instrumen-ment Pressure tation already in-(Suppression cluded in design.
Chamber)
- 9. Containment and Fuel Load Required instrumen-Drywell Hydrogen (expanded tation already in-Concentration range re- cluded in design. An quired by expanded range is 6/83) being implemented.
- 10. Containment and Fuel Load Required instrumen-Drywell Oxygen (expanded tation already in-Concentration range re- cluded in design. An quired by expanded ranged is 6/83) being implemented.
- 11. Primary Contain- 6/83 Required switches ment Isolation and lights already Valve Position included in design.
Limit switches are being qualified to appl'icable IEEE Standards,
- 12. Drywell Atmosphere Fuel Load Required instrumen-I Temperature tation already in-cluded in design.
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Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 13. BUR Core Later Presently being re-Thermocouples viewed by BWR Owner's group & NRC tor alternatives.
- 14. Radioactivity Later Await BWR Owner's Concentration Group Generic or Radiation Solution.
Level in Circul-ating Primary Coolant
- 15. Analysis of Fuel Load Included in Post Primary Coolant Accident Sample (Gamma Spectrum) System.
- 16. Primary Contain- Fuel Load Required instrumen-ment Area Radi- tation already in-ation cluded in design.
17A. Radiation Exposure Later Await BWR Owner's ;
Rate Group Generic Solution.
- 18. Drywell Sump Later Existing instrumen-Level tation will remain intact. Await BWR Owner's Group Generic Solution.
- 19. Containment Fuel Load Required instrumen-Effluent tation already in-Radioactivity - cluded in design. .
Noble Gases
- Environmental and seismic qualifi-cation protection will not be provided t'or the low-range ,
normal station vent monitor, but will be
Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 19. (cont'd) provided for the high-range, post-ac-cident station vent monitor and for all RBSVS monitors. In addition, the low-flow, RBSVS effluent activity will be
, monitored over the range of appro mately 1 x 10-gi- I through 1 x 10+4 !
Ci/qc. This sensi- -
tivity has been de-termined to be ade-quate to assure mon-toring of off-site .
dose limits.
- 19A.RSSVS Discharge Complete.
Flow
- 20. Environ Radio- Later On hold based on activity Ex- July 1981 Errata to posure Rate Reg. Gd. 1.97 Rev. 2 !
(continuous indication at fixed locations) -
- 21. Main Feedwater Flow Complete.
- 22. Condensate Storage Complete.
1 Tank Level.
- 23. Drywell Spray Later Await BWR Owner's Flow Group Generic Solution.
23A. Suppression Later Await BWR Owner's Chamber Spray Group Generic Flow ,
Solution.
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Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 24. Drywell Pressure Fuel Load Transmitter will be qualified to applicable IEEE Standards.
- 25. Suppression Pool 6/83 Required instrumen-Water Temperature tation already in-cluded in design.
- 26. Suppression Pool Fuel Load Additional instru-Water Level mentation being added to expand range as required, assuming the timely availability of necessary equipment.
- 27. HPCI Flow 6/83 Required instrumen-tation already in-cluded in design.
, Transmitter and in-dicator are being qualified to applicable IEEE Standards.
- 28. RCIC Flow 6/83 Required instrumen-tation already in-cluded in design.
Transmitter and indicator are being qualified to ap-plicable-IEEE Standards.
- 29. Core Spray 6/83 Required instrumen-System Flow tation already in-cluded in design.
Transmitter and indicator are being qualified to t
applicable IEEE Standards.
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Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 30. RHR System Flow 6/83 Required instrumen-tation already in-cluded in design.
Transmitter and indicator are being qualified to applicable IEEE Standards.
- 32. RHR Heat Exchang- 6/83 Required instrumen-er Outlet Temper- tation already in- .
ature cluded in design.
Thermocouples will be qualified to applicable IEEE Standards.
- 33. Cooling Water 6/83 Required instrumen-Temperature to tation already in-ESF System cluded in design.
Components Thermocouples will be qualified to applicable IEEE Standards.
- 34. Cooling Water 6/83 Required instrumen-Flow to ESF tation already in-System Components cluded in design.
Transmitters and indicators are being qualified to applicable IEEE Standards.
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Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 36. Sump Level in 6/83 Required instrumen-Spaces of Equip- tation already in-ment Required cluded in design.
4 for Safety Transmitters will -
be qualified to applicable IEEE -
Standards.
- 38. High Radioactivity Complete.
Liquid Tank Level
- 39. Emergency Venti- 6/83 Required switches lation Damper already included in Position design. Instrumen-tation will be qualified to applicable IEEE Standards.
- 40. Status of Standby 6/83 Required indication Power and Other already included in Energy Sources design. Transmitters Important to Safety and indicators are being qualified to applicable IEEE Standards.
- 41. Radiation Exposure Later Await BWR Owner's Rate (inside Group Generic -
buildings or areas Solution which are in direct contact with primary i containment where penetrations and hatches are located)
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l Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 42. Effluent Radio- Fuel Load Required instrumen-activity - Noble tation already in-Gases, Station Vent cluded in design.
Environmental and seismic qualifica-tion / protection will not be provided for the low-range, normal' station vent monitor, but will be provided for the high-range, post accident station vent monitor.
42A. Station Vent- 6/83 Transmitter will be Flow Rate qualified to applicable IEEE ;
Standards. '
- 43. Effluent Radio- Fuel Load Required instrumen-activity, Halo- tation already in-gens and Parti- cluded in design.
culates (Contin-uous Sampling)
- 44. Environs Radio- 6/83 Equipment will be activity - Radio- _ procured.
halogens and Particulates (portable)
- 45. Plant and Environs 6/83 Equipment will be .
Radiation procured.
(portable)
- 46. Plant and Environs 6/83 Equipment will be Radioactivity procured.
(portable)
. .. . ... ....:..-...a. . . . . .. ...x 9-Reg. Guide 1.97, Rev. 2 Require- Imple-ment Measured mentation Variable Date Status of Compliance
- 47. Post Accident Fuel Load New post-accident Sampling (Certain items sampling being im-required by plemented on sched-6/83) ule, assuming the timely availability of the necessary equipment.
- 48. Wind Direction Complete.
- 49. Wind Speed Complete.
- 50. Estimation of Complete.
Atmospheric Stability e
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Pcg2 ! cf 6 RECHLATORY CUIDE I.97, REY. '2 CROSS REFERENCE TO 4/6/82
' TABIE 1- SNPS CONFORMANCE TO REG. GUIDE 1.97. MRV.2 SilOREHAM ASSESSMENT REC.1.97, REV. 2 MEASURED VARI ABLE TABLE 1 ITEM NO.
REG. 1.97. REV.2 ITEM NO.
COOLANT LEVEL IN Tile REACTOR 3 A
RCS PRESSURE 5 A
PRIMARY CONTAINHENT PRESSURE 8 A
(DRYWELL)
A Suppression Pool Water Level 26 A DRYWELL AND WETWELL 0xygen 10 CONCENTRATION A SUPPRESSION POOL WATER TEMPERATURE 25 l SUHP LEVEL IN SPACES OF EQUIPMENT 36 A
REQUIR6D FOR SAFETY l
NEUTRON FLUX 2 '
B.1 I CONTROL ROD POSITION 1 l B-2 l RCS SOLUBLE BORON CONCENTRATION (Sample) 4 B-3' ,
COOLANT LEVEL IN THE REACTOR 3 B-4 B-5
- BWR CORE TilERH0 COUPLES I3 RCS PRESSURE 5 B-6 DRYWELL PRESSURE 8 B-5 DRYWELL DRAIN SUMPS LEVEL 18 B-8 (IDENTIFIED AND UNIDENTIFIED LEAKAGE)
Pens 2 ef 6 Sil0REHAH ASSESSMENT REG. 1.97 REV. 2 ITEH NO. REG. 1.97, REV. 2 NEASURED VARI ABLE TABLE 1 ITEM NO.
B-9, PR1HARY CONTAINHENT PRESSURE 8 (DRYWELL)
B-9 PRIMARY CONTAINHENT PRESSURE l Ba (Suppression Chamber)
B-10 PRIMARY CONTAINHENT ISOLATION 11 VALVE POSITION C-1 RADIDACTIVITY CONCENTRATION OK 14 RADIATION LEVEL IN CIRCULATING PRIMARY COOLANT C-2 ANALYSIS OF PRIMARY COOLANT 15 (gamms Spectrum)
C-3 BWR CORE TilERH0 COUPLES 13 C-4 RCS PRESSURE 5 PRIMARY CONTAINHENT HIGH RANCE 16 C-5 AREA RADIATION C-6 DRYWELL DRAIN SUHPS LEVEL 18 '
(IDENTIFIED AND UNIDENTIFIED LEAKAGE)
C-7 SUPPRESSION POOL WATER LEVEL 26
- C-8 DRYWELL PRESSURE 8 C-9 RCS PRESSURE 5 C-10 PRIMARY CONTAINHENT PRESSURE 8 (Drywell)
C-10 PRIMARY CONTAINHENT PRESSURE Ba (Suppression Chamber) e
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Pcg2 3 cf 6 SHOREHAM ASSESSMENT REG. l.97. REV. 2 ITEM NO. REG. 1.97 REV. 2 MEASURED VARIABLE TABLE 1 ITEM NO.
C-1I DRYWELL AND WETWELL llYDROGEN 9 CONCENTRATION 4
C-12
- DRYWELL AND WETWELL OXYGEN 10 CONCENTRATION C-13 CONTAINHENT EFFLUENT RADI0 ACTIVITY 19 '
NOBLE GASES (INCLUDING RBSVS)
C-14 SECONDARY CONTAINHENT AREA RADIATION 41 C-15 CONTAINMENT EFFLUENT RADIOACTIVITY 19 NOBLE GASES (INCLUDING RBSVS)
D-1 MAIN FEEDWATER FLOW 21 .
D-2 CONDENSATE STORAGE TANK LEVEL 22 D-3 SUPPRESSION CHAMBER SPRAY FLOW 23a D-4 DRYWELL PRESSURE '24 D-5 SUPPRESSION POOL WATER LEVEL 26 D-6 SUPPRESSION POOL WATER TDfPERATURE 25 D-7 DRYWELL ATMOSPHERE TEMPERATURE 12 -
D-8 , DRYWELL SPRAY FLOW 23 D-9 HAIN STEAHLINE ISOLATION VALVES 6 LEAKAGE CONTROL SYSTEM PRESSURE D-10 SRV POSITION 7
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Pcgs 4 of 6 Sil0REHAM ASSESSHENT REG. l.97, REV. 2 ITEM NO. REG. l.97, REV. 2 HEASURED VARIABLE TABLE 1 ITEM NO.
D-Il ISOLATION CONDENSER SYSTEM SilELL-SIDE NA SMPS-1 WATER LEVEL (Not Ingluded on TABLE 1) 4 D-12 ISOLATION CONDENSER SYSTEM VALVE NA SMPS-t POSITION (Not included on TABLE 1) i D-13 RCIC FLOW 28 9
D-14 IIPCI FLOW 27 D-15 CORE SPRAY FLOW 29 D-16 LPCI SYSTEM FLOW 31 .
D-17 SLCS FLOW 37 I ~
D-18 SLCS STORACE TANK LEVEL 35 I)-19 RilR SYSTEH FLOW 30 Il-20 RilR If7AT EXCilANGER OUTLET TEMPERATURE 32 D-21 COOLING WATER TEMPERATURE 11) ESF 33 SYSTEM COMPONENTS D-22 COOLING WATER FLOW TO ESF 34 SYSTEM COMPONENTS D-23 HIGli RADIDACTIVITY LIQUID TANK LEVEL 38 I)-24 EMERGENCY VENTILATION DAMPER POSITION 39
. D-25 STATUS OF STAND 8Y POWER AND UtilER ENERGY 40
- SOURCES IMPORTANT TO SAFETY (IlYDRAULIC, l PNEUHATIC) .
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Pcno 5 ef 6 SHOREHAM ASSESSHENT REG. 1.97. REY. 2 ITDI NO. REG. l.97. REV. 2 HEASURED VARIABLE TABLE 1 ITEM NO.
E-1 PRIMARY CONTAIMMENT 111C11 RANCE 16 AREA RADIATION 4 E-2 SECONDARY CONTAINHENT AREA RADIAT10N 17 E-3 RADIATION EXPOSURE MATES 17a E-4 CONTAINHENT EFFLUENT RADIDACTIVITY 19 NOBLE GASES (INCLUDING RBSYS)
E-4 RBSVS FLOW 19s E-5 CONTAINHENT EFFLUENT RADIDACTIVITY 19 NOBLE CASES (INCLUDING RBSVS)
E-5 RBSVS FLOW , 19e E-6 CONTAINHENT EFFLUENT RADIDACTIVITY 19 NOBLE CASES (INCLUDING RBSVS)
E-6 RBSVS FLOW 19a E-7 EFFLUENT RADIDACTIVITY NOBLE CASES 42 (STA. VENT)
E-7 STA. VENT FLOW RATE 42a E-8
EFFLUENT RADIOACTIVITY NOBLE GASES 42
- (STA. VENT)
E-8 STA. VENT FLOW RATE 42a
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E-9 EFFLUENT RADIOACTIVITY NOBLE CASES 42 (STA. VENT)
E-9 STA. VENT FLOW RATE 42a
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- Pcga 6 cf 6 SHOREHAM ASSESSMENT REC. l.97. REY.'2 ITEM No. REC. 1.97 REV. 2 HEASURED VARIABLE TABLE 1 ITEM NO.
E-10 EFFLUENT RADIDACTIVITY llALOCENS AND 43 L' ARTICULATES (SAMPLING) 4 E-Il ENVIRONS RADIDACTIVITY EXPOSURE itATE 20 (CONTINUOUS INDICATIONS AT FIXED LOCATIONS)
E-12 ENVIRONS RADIDACTIVITY RADIO-HALOCENS 44 AND PARTICULATES (PORTABLE)
E- l 'l PLANT AND ENVIRONS RADIATION (PORTABLE) 45 E-14 PLANT AND ENVIRONS RADIDACTIVITY (PORTABLE) 46 E-15 WINil DIRECTION 4B
. E-16 WIND SPEED 49 E-17 ESTIMATION OF ATHOSPHERIC STABILITY 50 E-la POST ACCIDENT SAMPLING CAPABILITY 47 E-19 POST ACCIDENT SAMPLING CAPABILITY 47 O
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