ML20084K742

Rev 2 to Position Paper on Reg Guide 1.97

ML20084K742
Person / Time
Site:	Brunswick
Issue date:	04/19/1984
From:	Warenko M CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20084K706	List: ML20084K705 ML20084K742 ML20084K755
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:

SUBMITTED BY: @[ /pfd&%-d RECOMMENDED BY: (( 7_ g APPROVED BY:

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REV. NO. SUBMITTED BY RECOMMENDED BY APPROVED BY DATE 1 /h? M 9Wkk: k / 2S O 2 fr) M WY& '

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B405140164 840508 PDR ADOCK 05000324 F

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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 9 O e

b 11 Rev. 2 O

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4.0 PLAN'r-SPECIFIC POSITION O.i EACH VARIABLE (Cont'd)

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,?a? 1 \' .,4.2.10 variable 310 - Primary Centainment Isolation Valve Position a -

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-', 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 i to indicate the potential for being breached or the

'; actual breaching of the barriers to fission product releases. The <

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, barriers are (1) fuel cladding, (2) primary coolant pressure p.s 1

'\', 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

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pyragraphs and where this variablo is covered under another variable

}, type, itis' indicated.

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4. 1- Cli Radioactivity Concentration or Radiation Level in s .. Ciret.latina Primary Coolant i

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.n- , .t Brunswich does 'not intend to continuously sonitor ch'e qq < >

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radioactivity 13 vel of the primary coolant. During normal l

operation the Radiation !!onitoring System provides 1

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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.

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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 r

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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 discussiens the six are

]i listed below and their applicability to Brunswick simma rized : . .

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J , RG 1.97 -

Brunswick

'1. Drywell Purge, SGTS S3GT

2. Secondary Containment Purge S3GT

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3. Secoddary Containment (RX

. Shield Bldg. Annulus) '

N/A

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4. Aux 11tdry Building N/A

,, 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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