ML20052C463

From kanterella
Revision as of 19:13, 9 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Revised Tables Re Util Plans for Compliance W/Reg Guide 1.97 Which Were Included in Response to Interrogatories on Shoreham Opponents Coalition Contention 3 & Suffolk County Contention 27
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)


Text

--

5- .

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.

~ '

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.

8205050011 820430 PDR ADOCK 05000322 n O PDR

z, . . ,.

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.
w. . _

- 1 l

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.
17. Secondary Con- Later Await BWR Owner's tainment ARM Group Generic Solution.

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.

s. .

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.

i I

a.. ,

l

( l

i l

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.

31. LPCI System Flow Later Await BWR Owner's Group Generic Solution.
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.

35. SLCS Storage Later Await BWR Owner's Tank Level Group Generic Solution.

. .. - - . ~ . .

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.

37. SLCS System Flow Later Await BWR Owner's Group Generic Solution.
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)

I l

l l

^~

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

e

~- .

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

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

~ ~

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

  • 9

_ _ _ _ _ _ _ _ _ - _ _ _ _ - - ^^ ~ ~ ^ ^ ^

~

-~

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) .

l l

/

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

~

E-9 EFFLUENT RADIOACTIVITY NOBLE CASES 42 (STA. VENT)

E-9 STA. VENT FLOW RATE 42a

. .n . .

  • w e e

' ~ ' ' ' *

- 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

e 4

e

- ' * - * - -- -- -- . , . - - _ . __. . . . _ _ . , _ , , _ _ _ _ _ _