ML20084K742
| ML20084K742 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/19/1984 |
| From: | Warenko M CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20084K706 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, NUDOCS 8405140164 | |
| Download: ML20084K742 (5) | |
Text
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i CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT POSITION PAPER ON REGULATORY GUIDE 1.97 W9,/[3 DATE:
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LIST OF EFFECTIVE PAGES POSITION PAPER ON REGULATORY GUIDE 1.97 Page(s)
Revision i
1
- ii 1
1-13 1
14.a -
1 15, 16 1
17, 18 2
19 -3 3 1
34 2
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4.0 PLAN'r-SPECIFIC POSITION O.i EACH VARIABLE (Cont'd)
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1 \\'.,4.2.10 variable 310 - Primary Centainment Isolation Valve Position a
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,s, Brunswick provides position indication for all isolation U
and containment boundary valves except check valves and reanually operated valves.
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c' I,4 j)runswick's Position on RG 1.97 Type C Variables
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7 EG 1.97 defines Type C variables as "those variables that provide
'nformation to indicate the potential for being breached or the i
actual breaching of the barriers to fission product releases. The p
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, barriers are (1) fuel cladding, (2) primary coolant pressure p.s 1
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boundary, and (3) containment." Key variables under Type C are
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,"those variables which most directly indicate the accomplishment of a i
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\\ L.-sa?;ety function." Each variable is discussed in the following 8
N pyragraphs and where this variablo is covered under another variable i
A
}, type, itis' indicated.
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4.
1-Cli Radioactivity Concentration or Radiation Level in Ciret.latina Primary Coolant s..
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.t Brunswich does 'not intend to continuously sonitor ch'e
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radioactivity 13 vel of the primary coolant. During normal operation the Radiation !!onitoring System provides l
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s 4.3.1 (Continued) indication of breach. During accident conditions the Post-Accident Sampling Syste's will be used to obtain a sample' for radioactivity analysis.
4.3.2 Variable C2 - Analysis of Primary Coolant Brunswick concurs and will provide a system that meets the requirements of NUREG-0737 Item II.B.3.
4.3.3 Variable C3 - BWR Thermocouple See variable B5, paragraph 4.2.5.
4.3.4 Variable C4 - RCS Pressure The requirements for the variable are met by v,ariable A1,
. paragraph 4.1.1.
f 4.3.5 Variable C5 - Primary Containment Area Radiation See Variable E1, paragraph 4.5.1.
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4.3.6 variable C6 - Drywell Drain Sumps Level See discussion for variable 38, paragraph 4.2.8.
. Rev. 2
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- - 4.0 PLANT-SPECIFIC POSITTON 05 EAC11 VARIABLE (Cont'd) i 4.5 Brunswick's Pesf tion on RG 1.97' Tkpe E Variables g
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4.5.4 (Continued).
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- r Under variable E4'in RG 1.97, there are six sub-baddings.
For convenience and clarity of discussien the six are s
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listed below and their applicability to Brunswick i
simma rized :.
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J RG 1.97 Brunswick
'1.
Drywell Purge, SGTS S3GT 2.
Secondary Containment Purge S3GT s
t 3.
Secoddary Containment (RX N/A Shield Bldg. Annulus)
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4.
Aux 11tdry Building N/A
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5.
Common Plant Vent Stack 6.
All other Aelease Points Turbine Vents
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Instrun.entation for the stack and turbine building vents will be provided through TMI plant modifications80-034, 35
't and 36. These plant modifications meet the requirements of NUREG-0737 and applicable standards and regulatory guides including RG 1.97.
. Rev. 2.
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