ML20086L275

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Reg Guide 1.97 Review
ML20086L275
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 01/31/1984
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20086L272 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8402080065
Download: ML20086L275 (47)
v • d • e


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1 VEPC0 4

NORTH ANNA POWER STATION

? REG. GUIDE 1.97 REVIEW i

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TABLE OF CONTENTS Title Pagee Introduction 1 i Variable List 2 Notes and Justifications 33 Attachments I. Indicator Table 37 II. Regulatory Guide 1.97 Review Basis 40 l

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  • INTRODUCTION A review of instrumentation installed at Virginia Electric and Power Company's North Anna Power Station was performed to determine if the existing instrumentation conplies with the intent of the range, redundancy, power supply, seismic qualification and environmental qualification requirements of Regulatory Guide 1.97 Rev. 3 (R. G. 1.97), " Instrumentation for Light-Hater-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident". Contained herein are the results of that (eview, along with recommendations and/or justifications for each item reviewed.

The next section contains the Variable List for North Anna Power Station, preceded by a Guide explaining the terminology used in the List. Attachment I provides a summary of indicators by Item Number, Mark Number, Manufacturer and Type.

In initiating the review of existing instrumentation, a baseline set of criteria was developed. To establish these criteria, the Regulatory Guide 1.97 - Revision 3 recommended design and qualification criteria were compared to the North Anna Power Station design basis. Although the North Anna Power l

Station design basis was effectively established prior to the issuance of many of the Regulatory Guides referenced in Regulatory Guide 1.97, the design conforms to the intent of the Regulatory Guides as shown by the comparison ir.

Attachment II. Attachment II lists the required and recommended design documents of Regulatory Guide 1.97 and provides a comparison to the applicable North Anna Power Station design basis.

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4 Variable List Guide

1. The following terminology applies for the North Anna Power Station Variable List:

N/R - Not Required N/A - Not Applicable, Yes - Complies with the intent of Reg. Guide 1.97 j No - Does not comply with the interet of Reg. Guide 1.97

- Justification is stated

2. Control Room Display - Reg. ,3ulde 1.97 Variables will be available on Control Board Indication and/or available for call-up via CRT displays. Exceptions will be Chemistry and Health Physics variables which will be made available to the appropriate personnel by the transmittal of data, writtFt: or Verbal, and logged.

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VIRGIPIA ELECTRIC AND POWER COMPANY h REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ,

ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY l

A-1 Steam Generator 1 Yes Yes Yes No Narrow Range

. Level A-2 Steam Generator 1 Yes Yes Yes No Pressure I A-3 Core Exit 1 No No No No Temperature l A-4 RCS Cold Leg 1 Yes l No No Yes

! Water Temperature

! A-5 RCS Hot Leg 1 Yes No No Yes Water A-6 RCS Flow 1 Yes No No Yes 1

l A-7 RCS Wide Range 1 Yes No No Yes i Pressure i

! A-8 HPSI Flow 1 Yes No No No

A-9 Condensate Storage 1 Yes Yes Yes Yes Tank Water Level r A-10 Refueling Water 1 Yes Yes No Yes .

Storage Tank Level l A-ll PORY Position 1 Yes No No No Indication

! A-12 Pressurizer 1 Yes No No No l Liquid Temp.

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VIRGINIA ELECTRIC ANDkWER COMPANY $

REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA PO'.JER STATION ,

ITEM POWER CONTROL MVPEER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION A-1 Yes Yes Yes Yes Note 1

. A-2 Yes Yes Yes Yes Note 1 A-3 Yes Yes Yes -

Yes System to be upgraded.

j A-4 Yes Yes Yes Yes RTD's are to be replaced.

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A-5 Yes Yes Yes RTD's are to be replaced.

l Yes 1

A-6 Yes Yes Yes Yes Notes 1 and 2.

l i A-7 Yes Yes Yes Yes Note 1

Transmitters to be replaced A-8 Yes Yes Yes Yes Relocate and replace transmitters above submergence level, t Seperation of flow channels j required.

A-9 Yes Yes Yes Yes Acceptable l A-10 Yes Yes Yes Yes Replace with qualified transmitters i

A-ll Yes Yes Yes Yes System to be upgraded.

, A-12 Yes Yes Yes Yes Replace present RTD with qualified I dual element RTD, install a second I channel.

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VIRGINIA ELECTRIC AND PGWER COMPANY g REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ITEM ENVIRONMENTAL SEISMIC Nt#EER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY A-13 Pressurizer Level 1 Yes Yes Yes Yes A-14 Containment 1 Yes Yes Yes Yes HyJrogen Con-centration , .

! A-15 Containment 1 Yes No No Yes i

Intermediate Range Pressure

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! A-16 Indicators 1 Yes Yes Yes N/R B-1 Neutron Flux 1 Yes No No Yes i

B-2 Control Rod 3 Yes N/R N/R N/R i Position l 3-3 RCS Soluble Boron 3 Yes N/R N/R N/R l

Concentration B-4 RCS Cold Leg Water 3 Refer to item A-4 i Temperature B-5 RCS Hot Leg Water 1 Refer to item A-5 l Temperature i

l B-6 RCS Cold Leg Water 1 Refer to item A-4 '

Temperature 4 B-7 RCS Pressure 1 Refer to item A-7 B-8 Core Exit - 3 Refer to item A-3 Temperature B-9 Coolant Level 1 Yes Yes Yes Yes l in reactor g PAGE 3 0F 30

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VIRGINIA ELECTRIC AND POWER COMPANY t REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ,

ITEM POWER CONTROL NUDGER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION A-13 Yes Yes Yes Yes Acceptable

. A-14 Yes Yes Yes Yes Acceptable A-15 Yes Yes Yes Yes Replace existing transmitters A-16 N/R Yes Yes Yes Reference Attachment I; Note 1 i B-1 Yes Yes Yes Yes Install new excore flux monitoring

! system l B-2 N/R Yes Yes Yes Acceptable B-3 N/R Yes Yes Yes The Boron concentration can be determined by the manual grab sample and/or post-accident suiapling system.

B-4 Refer to Item A-4 B-5 Ref er to Item A-5 B-6 Refer to Item A-4 i B-7 Refer to Item A-7

B-8 Refer to Item A-3 B-9 Yes Yes Yes Yes Acceptable i .

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VIRGINIA ELECTRIC AND POWER COMPANY a l

REG. GUIDE 1.97 VARIABLE LIST

  • NORTH ANNA POWER STATION ,

ITEM ENVIRONMENTAL SEISMIC NUMER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY l

i i B-10 Degrees in 2 Yes Yes N/R N/R

Subcooling B-ll RCS Pressure 1 Refer to item A-7 B-12A Containment Sump 2 Yes No N/R N/R Water Level

] (Narrow)

B-12B Containment Sump 1 Yes Yes No Yes Water Level (Wide)

B-13 Containment 1 Yes . Yes Yes Yes Pressure I i

! B-14 Containment Isolation 1 No Yes Yes Yes Valve Position B-15 Containment 1 Yes Yes Yes Yes j Pressure l C-1 Core Exit Temp- 1 RefErtoitemA-3

erature

! C-2 Radioactivity 1 Yes No No Yes

! Concentration or Radiation i Level in Cir-culating Primary Coolant

C-3 Analysis of; 3 Yes N/R N/R N/R

! Primary Coolant j (Gamma Spec-l trum) i i

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  • s VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION i

ITEM POWER CONTROL NIDEER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION B-10 Yes Yes Yes Ye: Acceptable

. B-ll Refer to Iter A-7 i

I B-12A Yes Yes .Yes Yes Replace receiver modules

! (radiation)

B-128 Yes Yes Yes Yes Replace receiver modules B-13 Yes Yes Yes Yes Acceptable B-14 Yes No No No Provide valve position indication for HCV-1936 and HCV-2936 in the control room, TSC and E0F B-15 Yes Yes Yes Yes Acceptable C-1 Refer to Item A-3 C-2 Yes Yes Yes Yes Note 4 C-3 N/R Yes Yc. Yes Acceptable i

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VIRGINIA ELECTRIC AND POWER COMPANY g REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ~

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ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY 1

. C-4 RCS Pressure 1 Refer to item A-7 1

, C-5 Containment 1 Yes Yes Yes Yes

] Pressure C-6A Containment 2 Refer to item B-12 4 Sump Water j Level (Narrow)

. C-6B Containment 1 Refer to item B-12 B

! Sump Water Level (Wide) l I C-7 Containment 3 Refer to item E-1 I Area Radiation i C-8 Effluent Radio- 3 Refer to items j activity Noble E-6 and E-7 1 Gas Effluent

! from Condenser l Air Re:noval Systehi Exhaust

! C-9 RCS Pressure 1 Refer to item A-7 i

C-10 Containment 1 Refer to item A-14 Hydrogen Con- .

, centration l C-ll Containment 1 Yes Yes Yes Yes 1

Pressure ,

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VIRGINIA ELECTRIC AND POWER COMPANY g REG. CUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ITEM POWER CONTROL

. NUMER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION C-4 Refer to Item A-7 l

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C-5 Yes Yes Yes Yes Acceptable i

! C-6A Refer to Item B-12A C-6B Refer to Item B-128

C-7 Refer to Item E-1 j C-8 Delete - Function Covered by Items E-6 and E-7 C-9 Refer to Item A-7 C-10 Refer to Item A-14 i C-li Yes Yes Yes Yes Acceptable j

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VIRGINIA ELECTRIC AND POWER COMPANY $

REG. GUIDE 1.97 VARIABLE LIST NORTil ANNA POWER STATION ,

ITEM ENVIRONMENTAL SEISMIC MUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY C-12 Containment 2 Yes Yes N/R N/R Effluent Radio-l activity -

Noble Gases i from Identified Release Points C-13 Radiation Expo- 2 Yes Yes N/R N/R

, sure Rate (inside build-

! ings or areas,

e.g., auxiliary building, reactor shield building annulus, fuel handling build-ing, which are in direct
centact with primary con-tainment where I penetrations and hatches l are located.)

C-14 Effluent Radio- 2 No Yes N/R N/R activity Noble Gases (from buildings as

indicated in C-13) l D-1 RHR System 2 Yes No N/R N/R

! Flow PAGE 9 0F 30

VZRGINIA ELECTRIC AND ?0WER COMPANY t

} REG. GUIDE 1.97 VARIABLE LIST i NORTH ANNA POWER STATION ,

i I ITEM POWER CONTROL NUPEER SOURCE ROOM TSC EOF REMARKS

, DISPLAY LOCATION LOCATION j C-12 Yes Yes Yes Yes Acceptable

. C-13 Yes Yes Yes Yes Acceptable i

C-14 Yes Yes Yes Yes Equipment is adequate once changes described in item E-9 are incorporated.3 i .-

D-1 Yes Yes Yes Yes Considered Category 3 variable.

See Note 9 l

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VIRGINIA ELECTRIC AND POWER COMPANY ,

j REG. CUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ,

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ITEM ENVIRONMENTAL SEISMIC d

VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY NUMBER i

D-2 RHR lleat Ex- 2 Yes No N/R N/R changer Outlet

. Temperature D-3 Accumulator l 2 No No N/R N/R Tank Level _

i r)-4 Accumulator 2 Yes No N/R N/R Tank Pressure I D-5 Accumulator 2 Yes No N/R N/R Isolation

! Valve Position D-6 Boric Acid 2 Yes No N/R N/R i Charging (Flow) i i

D-7 Flow in HPI 2 Refer to item A-8 System f D-8 Flow in LPI 2 Yes No N/R N/R

, System l D-9 Refueling Water 2 Refer to item A-1C i Storage Tank Level

D-10 Reactor Coolant 3 Yes N/R N/R N/R
Pump Status
D-ll Primary System 2 Refer to item A-l' j Safety Relief 2

Valve Position j (including PORV valves) 4 l

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VIRGINIA ELECTRIC AND POWER COMPANY [

! REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ,

ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION I

D-2 Yes Yes Yes Yes Considered Category 3 variable.

See Note 9 i

D-3 Yes Yes Yes Yes Considered Category 3. See Note 10 i D-4 Yes Yes Yes Yes Considered Category 3. See Note 70 l

D-5 Yes Yes Yes Yes Considered Category 3. See Note 10

D-6 Yes Yes Yes Yes Replace transmitter.

D-7 Yes Yes Yes Yes Refer to Item A-8 D-8 Yes Yes Yes Yes Environmentally qualified transmitters to be installed.

D-9 Yes Yes Yes Yes Refer to Item A-10 D-10 N/R Yes Yes Yes Acceptable D-ll Refer to Item A-ll l

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VIRGINIA ELECTRIC AND POWER COMPANY $

REG. GUIDE 1.97 VARIABLE LIST NORTil ANNA POWER STATION ,

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ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNCANCY D-12 Pressurizer 1 No Yes Yes No Level 4

D-13 Pressurizer 2 No No N/R N/R Heater Status D-14 Quench Tank 3 Yes N/R N/R N/R Level D-15 Quench Tank 3 No N/R N/R N/R Temperature D-16 Quench Tank 3 Yes N/R N/R N/R Pressure D-17 Steam Generator 1 Yes No No Yes Level
D-18 Steam Generator 1 Refer to Item A-2 i Pressure i

l D-19 Main Steam 2 No No N/R N/R Safety-Relief Valve Positions i D-20 Main Feedwater 3 Yes N/R N/R N/R Flow D-21 Auxiliary or 2 Yes Yes N/R N/R Emergency Feed-

{ water Flow.

1 I D-22 Condensate 1 Refer to item A-9 l Storage Tank

Level PAGE 13 0F 30

s VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 UARIABLE LIST NORTH ANNA POWER STATION ITEM POWER COMROL NUPEER SOURCE P0OM TSC E0F REMARKS i

! DISPLAY LOCATION LOCATION 1

l D-12 Yes Yes Yes Yes Add density compensation to reduce i

error and expand range of transmitters to full range allowed by taps. Note 7.

D-13 Note 5 D-14 N/R Yes Yes Yes Acceptable D-15 N/R Yes Yes Yes Note 6 D-16 N/R Yes Yes Yes Acceptable i D-17 Yes Yes Yes Yes Transmitters to be replaced.

Notes 1 and 3 D-18 Refer to Item A-2 j D-19 No No No No Install position detector and I indicator 1

D-20 N/R Yes Yes Yes Acceptable l

j D-21 Yes Yes Yes Yes Acceptable

! D-22 Refer to Item A-9 i

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VIRGINIA ELECTRIC AND POWER COMPANY a i REG. GUIDE 1.97 VARIABLE LIST

] NORTH ANNA POWER STATION

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4 ITEM ENVIRONMENTAL SEISMIC NtpeER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY D-23 Containment 2 No Yes N/R N/R

! Spray Flow i D-24 Heat Removal 2 Yes No N/R N/R i by the Contain-ment Fan Heat Removal System 1 D-25 Containment a No No N/R N/R Atmosphere l

! D-26 Containment 2 Yes No N/R N/R Sump Water

< Temperature

! D-27 Makeup Flow-in 2 Yes No N/R N/R D-28 Letdown Flow 2 Yes No N/R N/R i out D-29 Volume Control 2 No No N/R N/R l Tank Level 1

D-30 Component Cool- 2 No No N/R N/R l ing Water Temp-i erature to ESF

! System .

l D-31 Component Cool- 2 No No N/R N/R

ing Water Flow j to ESF System 1

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VIRGINIA ELECTRIC AND POWER COMPANY t REG. GUIDE 1 97 VARIABLE LIST NORTH ANNA POWER STATION ,

ITEM POWER CONTROL NUMBER SOURCE ROOM TSC E0F REMARKS l

i DISPLAY LOCATION LOCATION

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l D-23 Yes Yes Yes Yes Note 8

! . D-24 Yes No Yes Yes Replace sensors with qualified l

transmitters and RTD's.

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! D-25 Yes Yes Yes Yes Replace with qualified RTD's and rescale

! D-26 Yes Yes Yes Yes Note 11 D-27 Yes Yes Yes Yes Replace with qualified transmitter l

D-28 Yes Yes Yes Yes Replace with qualified transmitter

D-29 Yes Yes Yes Yes Replace with qualified transmitter
Note 12 i D-30 No No Yes Yes Install temperature channel to j monitor operatior,at the charging

! purp cooling system.

l l D-31 No Yes Yes Yes Install flow channel to monitor i operation of the charging pump cooling system.

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VIRGIN 1A 2.Lt.LTIK10 ANU t'Urt.K Lunran t ,

g REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION j

1 ITEM ENVIRONMENTAL SEISMIC VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY NUMBER D-32 High-Level 3 Yes N/R N/R N/R Radioactive

. Liquid Tank Level-

D-33 Radioactiva 3 No N/R N/R N/R l Gas Holdup Tank Pressure i D-34 Emergency Vent- 2 No No N/R N/R ilation Damper Position 4 D-35 Statu ,of stand-i by power and other energy i sources important i to safety.

I i D-35A 4160V Emergency 2 Yes Yes N/R N/R j Bus 1J-Voltage I

D-35B 4160V Emergency 2 Yes Yes N/R N/R j Bus 1J-Current J

l D-35C 4160V Emergency 2 Yes Yes N/R N/R

! Bus 1H-Voltage -

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I D-35D 4160V Emergency 2 Yes Yes N/R N/R

! Bus 1H-Current

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I 480V Emergency 2 Yes Yes N/R N/R D-35E Bus 1J l -

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i VIRGINIA ELECTRIC AND POWER COMPANY , t REG. CUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION l l

, ITEM POWER CONTROL '

NUMBER SOURCE ROOM TSC EOF REMARKS l

l DISPLAY LOCATION LOCATION D-32 N/R Yes Yes Yes Adequate

. D-33 Yes Yes Yes ,

Yec Rescale or replace existing instrument D-34 Yes No Yes Yes Install Limit Switches l D-35 For items D-35A - D-35AB control l Room displays will be available

! once the multiplex system is

! installed.

D-35A Yes Yes Yes Yes l

l D-35B Yas Yes Yes Yes D-35C Yes Yes Yes Yes D-35D Yes Yes Yes Yes D-35E Yes Yes Yes Yes I

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VI.KGIN LA ELECTRIC AND t'UWt,K Cuftt'ANI ,

REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION

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ENVIRONMENTAL SEISMIC ITEM CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY

., NUPEER VARIABLE j

D-35F 480V Emergency 2 Yes Yes N/R N/R

Bus 1J1 1

I D-35G 480V Emergency 2 Yes Yes N/R N/R 1 Bus 1H

'l I D-35H 480V En.ergency 2 Yes Yes N/R N/R j Bus 1H1 D-351 Emergency MCC 2 Yes Yes N/R N/R

1J1-1 D-35J Emergency MCC 2 Yes Yes N/R N/R lJ1-1A D-35K Emergency MCC 2 Yes Yes N/R N/R 1J1-2N&S I

D-35L Emergency MCC 2 Yes Yes N/R N/R l 1J1-3 i

D-35F Emergency MCC 2 Yes Yes N/R N/R l

lH1-1 D-35N Emergency MCC 2 Yes Yes N/R N/R

! 1H1-1A i

D-350 Emergency MCC 2 Yes Yes N/R N/R

IH1-2N

! N/R

D-35F Emergency MCC 2 Yes Yes N/R 1H1-2S l

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REG. GUIDE 1.97 VARIABLE LIST t l

. NORTH ANNA POWER STATION j ITEM F0WER CONTROL -

SOURCE ROOM TSC EOF REMARKS NUMBER i DISPLAY LOCATION  : LOCATION j D-35F Yes Yes Yes Yes For items D-35A - D-35AB, Control Room Displays will be available once the multiplex system is installed.

D-35G Yes Yes Yes Yes D-35H Yes Yes Yes Yes I

l D-351 Yes Yes Yes Yes D-35J Yes Yes Yes Yes

! D-35K Yes Yes Yes Yes l

! D-35L Yes Yes- Yes Yes i

! - D-35M Yes Yes Yes Yes

, D-35N Yes Yes Yes Yes D-350 Yes Yes Yes Yes D-35P Yes Yes Yes Yes i

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~-VinulmiA 2.LtGIRAG ANU YUW2.K WMFAnt ' ~ , ,

REG. CUIDE 1.97 VARIABLE LIST

, NORTH ANNA POWER STATION ENVIRONMENTAL SEISMIC ITEM CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY i NUMBER VARIABLE l

! D-35Q Emergency MCC 2 Yes Yes N/R N/R l 1H1-3 l

. D-35R Emergency NCC 2 Yes Yes N/R N/R l

l lH1-4 i

D-35S 125V Distribu- 2 Yts Yes N/R N/R

i tion Cabinet 1 j I Voltage D-35T 125V Distribu- 2 Yes Yes N/R N/R l

i tion Cabinet 1 II Voltage D-35U 125V Distribu- 2 Yes Yes N/R N/R l tion Cabinet 1 i III voltage I D-35V 125V Distribu- 2 Yes Yes N/R N/R ti.,n Cabinet 1 I IV voltage D-35W 120V AC Vital 2 Yes Yes N/R N/R i Bus Dist.

Panel 1-1 Voltage D-35X 120V AC Vital 2 Yes Yes N/R N/R .

lj Bus Dist.

4 Panel 1-II j Voltage i .

l D-35Y 120V AC Vital 2 Yes Yes N/R N/R j Bus Dist.

Panel 1-III Voltage PAGE 21 or 30 4

VIRGINIA ELECTRIC AND POWER COMPANY ,

a REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ,

ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS

DISPLAY LOCATION LOCATION D-35Q Yes Yes Yes Yes For items D-35A - D35AB, Control Room Displays will be available

. once the multiplex system is installed.

0-35R Yes Yes Yes Yes D-35S Yes Yes Yes Yes i

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  • i D-35T Yes Yes Yes Yes D-35U Yes Yes Yes Yes i D-35V Yes Yes Yes Yes i

j D-35W' ,Yes Yes Yes Yes D-35X Yes Yes Yes Yo; l

i Yes D-35Y Yes Yes Yes i

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REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ITEM ENVIRONMENTAL SEISMIC VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY fil#6ER D-35Z 120V AC Vital 2 Yes Yes N/R N/R Bus Dist.

Panel 1-IV D-35AA Emergency 2 Yes Yes N/R N/R Diesel Generat-or EGB Watt D-35AB Emergency 2 Yes Yes N/R N/R Diesel Generat-or EGC-Z Watt ,

E-1 Containment 1 Yes Yes Yes Yes Area Radiation E-2 Radiation Expo- 3 Yes N/R N/R N/R sure Rate (in-side buildings or areas where access is re-quired to ser-vice equipment important to safety)

E-3 Containment 2 N/R N/R N/R N/R or Purge

  • Effluent .

E-4 Reactors Shields 2 N/R N/R N/R N/R Buildings Annulus (if in design)

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REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ITEM POWER CONTROL i NUPEER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION l

, D-35I Yes Yes Yes Yes For items D-35A - D35AB control room displays will be available

. once the multiplex system is installed.

D-35AA Yes Yes Yes Yes 4

1 D-35AB Yes Yes Yes Yes i

E-1 Yes Yes Yes Yes Acceptable 1

l E-2 Yes Yes Yes Yes Acceptable E-3 N/R N/R N/R N/R Delete - Effluent discharges through common plant vent i

E-4 N/R N/R N/R N/R Delete - Effluent discharges through connon plant vent 9

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  • v1xGINLA r.Lt.GiniG Anu ru ra warant ,

REG. CUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION

. ITEM ENVIRONMENTAL SEISMIC VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY MLSSER i

E-5 Auxiliary 2' N/R N/R N/R N/R i Building (including any building con-taining primary system gases, e.g.,

waste gas decay tank)

E-6 Condenser Air 2 N/R N/R N/R N/R Removal System Exhaust E-7 Comon Plant 2 No Yes N/R N/R Vent or Multi-purpose Vent Discharging any 1 of above release 4 (if containment i purge is in-cluded) 1 E-8 Vent from Steam 2 Yes Yes N/R N/R Generator Safety Relief i Valves or ,

Atmospheric Dump Valves
E-9 All other 2 No Yes F/R N/R
Identified -

! Release

! Points l

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VIRGINIA ELECTRIC AND POWER COMPANY REG. CUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ,

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l j ITEM POWER CONTROL ROOM TSC EOF REMARKS

Nul6ER' SOURCE DISPLAY LOCATION LOCATION E-5 N/R N/R N/R N/R Delete - Function covered by E-7 i

l . E-6 N/R N/R N/R N/R Delete - Effluent discharges l

through common plant vent I

! E-7 Yes Yes Yes Yes Equipment is adequate once changes 1 described in Item E-9 are i incorporated E-8 Yes Yes Yes Yes Acceptable

, E-9 Yes Yes Yes Yes Flow element FE-GW-108 should be l changed and FT-GW-108 calibrated l

to increase present range of 0-400 SCFM to 0-585 SCFM, or 110% of max.

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VIRGINIA ELECrK10 AND FUWE.K LuttrANE REG. CUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ENVIRONMENTAL SEISMIC ITEM REDUNDANCY VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION NUPEER E-10 All Identified 3 Yes N/R N/R N/R Plant Release Points (except steam generator safety relief valves or atmo-spheric steam l

dump valves and condenser

!; air removal

. system exhaust)

Sampling with Onsite Analysis Capability.

. E-ll Airborne Radio- 3 'Yes N/R N/R N/R halogens and j! particulates (portable samp-

, ling with on-l site analysis

! capability)

Plant and 3 No N/R N/R N/R E-12

Environs Radia-

! tion (portable i

a instrumentation) -

4 4 E-13 Plant Environs 3 Yes h/R N/R N/R Radioactivity i (portable in-strumentation) l l E-14 Wind Direction 3 Yes N/R N/R N/R E-15 Wind Speed 3 Yes N/R N/R N/R PAGE L OF g

VIRGINIA ELECTRIC AND POWER COMPANY , t REG. GUIDE 1.97 VARIABLE LIST NORTH ANNA POWER STATION ITEM POWER CONTROL NIMER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION E-10 N/R Yes Yes Yes Acceptable

. E-ll N/R For items E E-13 Manual Acceptable documente i results ar e available to the op erator.

E-12 N/R Purchase portable instrumentation to cover range to 109 R/hr.

I E-13 N/R Initially, the dose rate is

calculated utilizing the radiation

! monitoring readings at the

station. A spectrometer is available at Surry Power Station and can be used for release
assessment analysis for North Anna samples.

! E-14 N/R Yes Yes Yes Acceptable E-15 N/R Yes Yes Yes Acceptable I

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VIRGINLA ELEG1K1U AND YUWE.R turtran s ,

REG. CUIDE 1.97 VARIABLE LIST lI NORTH ANNA POWER STATION i .

ENVIRONMENTAL SEISMIC ITEM RANGE QUALIFICATION QUALIFICATION REDUNDANCY NtpeER VARIABLE CATEGORY

! E-16 Estimation of 3 No N/R N/R 2 N/R Atmospheric Stability E-17 Primary Coolant 3 Yes N/R N/R N/R and Sump Samp-ling and Analy-sis E-18 Containment 3 Yes N/R N/R N/R Air Sample I

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a VARIABLE LIST NORTH ANNA POWER STATION NOTES AND JUSTIFICATIONS Note 1: Redundant channels are displayed on a common recorder. This does not impair the operator from obtaining the data in the event of a recorder failure. Tne data for each channel will be accessible to the operator via call-up from CRT's in the Control room. The CRTs will be capable of receiving data from either of two redundant computer systems which are fed by a redundant fully qualified IE multiplex system. Additionally, many of the points are available on the existing plant computer as another backup.

Note 2: Parameter is confirmatory in nature only (running /not running),

therefore we do not intend to upgrade. As a backup, item D-10 Reactor Coolant Pump current indication and RCP breaker status (open/ closed) is available to the' operator for each motor.

Note 3: The Steam Generator wide range level transmitters have a range of 0-57T' H2 0. This range covers from 14" above the tube sheet to the separators which is 97.6% of the required range which meets the intent of R.G. 1.97.

p,g, j of 4

Note 4: Two independent and redundant systems are avallat,1e to obtain this sample. However, only one of the two is fully environmentally and seismically qualified. This is considered adequate to meet the intent of R.G. 1.97 and no modifications are planned. RM-CH-228,

' 229, 128, 129 and the new Post Accident System are the systems to be usid for back-up.

Note 5: Breaker position is adequate indication with pressurizer temperature and pressure available as backups. Additionally, the operating and emergency procedures reference only breaker position Indication.

tiote 6: One non-safety temperature indication with a range of 0-350*F is provided and considered adequate to meet the intent of this guide.

The quench tank design pressure is 100 psig. Prior to attaining this pressure, the tank ruptLee disk will provide a relief path to the i containment atmosphere. Therefore, any relief from the: pressurizer i

safety valves will be maintained below 100 psig and a corresponding saturation temperature less than 350*F.

Note 7: Existing level instrumentation meets the intent of this go'de once temperature compensation is added. Present instrumentation covers 390" of the 500" height of the pressurizer with only the curvature l portions of the vessel not being covered.

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bhf/1085B/40 -

Note 8: Existing instrumentation is considered adequate. A flow switch is installed on the discharge side of each Quench Spray Pump to monitor low flow with annunciator alarm available in the control room.

Additionally, the effectiveness of the Quench Spray flow can be determined by the use of containment temperature and pressure indication.

Note 9: Considered as a Category 3 variable. The RHR system is not required to operate during post accident conditions as identified in the updated Final Safety Analysis Report Section 5.5.4.3.3.

Additionally, RHR flow and and temperature are backup variables for monitoring core cooling which can be determined from redundant and qualified temperature and pressure measurements.

Note 10: The present accumulator tank level instrumentation indicates over a range of twelve inches. This narrow range is required to obtain the accuracy needed to meet technical specification conditions and meet the intent of R.G. 1.97. Variables D-3, 0-4 and 0-5 are located below the flood plane after accident and environmentally quallfled i

only for the environment that they see during normal plant operations. During power operations, the power to the accumulator isolation valve, which is oper, is removed with the breaker being l

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Mes#8@858/41

verified locked open by Technical Specification during start-up procedure. Therefore, accumulator pressure, level and valve position indication serve as a means to determine accumulator status during normal operations and to ensure their capability to perform their i

automative accident function which is independent of electrical signals and strictly mechanical in nature. Therefore, these variables should be cli.ssified as Category 3 and considered qualified for their intended normal operating environment fun:tions.

Note 11: The containment sump temperature indication is not required based on the regulatory r,osition delineated in Safety Guide 1 " Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps." Vepco's Emergency Core Cooling and Containment Heat Removal System pumps which take suction from the containment sump when the refueling water storage tank is empty assumed saturated I

water present to meet N.PSH requirements and meet the criteria of Safety Guide 1. Vepco considers this a Category 3 variable.

Note 12: The existing range covers from 22% to 78% of tunk volume which is satisfactory to monitor the operating needs of the variable. This range meets the intent of R.G. 1.97.

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ATTACHMENT I (ITEM A-16)

UNIT 1 NORTH ANNA POWER STATION MARK NO. MAKE/MODEL NO.

A-1 LI-1474, 1484, 1494 W-VX-252 LI-1475, 1485, 1495 W-VX-252 LI-1476, 1486, 1496 W-VX-252 A-2 PI-1474, 1484, 1494 W-VX-252 PI-1475, 1485, 1495 W-VX-252 PI-1476, 1486, 1496 W-VX-252 A-3 Thermocouple Indicators Honeywell (System to be replaced)

A-6 FI-1414, 1415, 1416 W-VX-252 FI-1424, 1425, 1426 W-VX-252 .

FI-1434, 1435, 1436 W-VX-252 A-7 PI-1402 W-VX-252 PI-1403 W-VX-252 A-8 FI-1940, 1943 W-VX-252 FI-1932, 1933, 1960 W-VX-252 FI-1961, 1962, 1963 W-VX-252 A-9 LI-CN100A W-VX-252 LI-CN100B-1 W-VX-252 A-10 LI-QS-100A W-VX-252 LI-QS-100B W-VX-252 LI-QS-100C W-VX-252 LI-QS-1000 W-VX-252 YI-VMSiOIA, 8 Sigma Ill System to A-11 be upgraded l

A-12 TI-1453 W-VX-252 A-13 LI-1459A W-VX-252 l

l LI-1460 W-VX-252 LI-1461 W-VX-252 l

A-14 H I-HC-101 W-VX-252 H I-HC-201 W-VX-252 A-15 PI-LM-100A W-VX-252 PI-LM-100B W-VX-252 PI-LM-100C W-VX-252 PI-LM-1000 W-VX-252 NOTE: All indications model W-VX-252 are acceptable.

Page 1 of 3 bhs/10858/43 -

MARK NO. MAKE/MODEL NO.

B-1 N"I-1-318,D, 328,0 W-VX-252 358,0, 36B,0 W-VX-252 41B,C, 428,C W-VX-252 438,C, 448,C W-VX-252 B-9 LI-1-1310,ll,12 W-VX-252 20,21,22 W-VX-252 B-12B LI-RS-151A W-VX-252 LI-RS-151B W-VX-252 C2 RM-CH-128 W (LATER)

RM-CH-129 W (LATER)

C-11 PI-LM-110A W-VX-252 PI-LM0110B W-VX-252 UNIT 2 MARK NO. MAKE/MODEL NO.

A-1 LI-2474, 2484, 2494 W-VX-252 LI-2475, 2485, 2495 W-VX-252 LI-2476, 2486, 2496 W-VX-252 A-2 PI-2474, 2484, 2494 W-VX-252 PI-2475, 2485, 2495 W-VX-252 PI-2476, 2486, 2496 W-VX-252 A-3 Thermocouple Indicators Honeywell (System to be replaced)

A-6 FI-2414, 2415, 2416 W-VX-252 FI-2424, 2425, 2426 W-VX-252 FI-2434, 2435, 2436 W-VX-252 A-7 PI-2402 W-VX-252 PI-2403 W-VX-252 A-8 FT-2940, 2943 W-VX-252 FT-2932, 2933, 2960 W-VX-252 FT-2961, 2962, 2963 W-VX-252 A-9 LI-CN200A W-VX-252 LI-CN200B-1 W-VX-252 Page 2 of 3 bhg/108SB/44

__.2

UNIT 2 MARK NO. MAKE/MODEL NO.

A-10 LI-QS-200A W-VX-252 LI-QS-2006 N-VX-252 LI-QS-200C W-VX-252 LI-QS-2000 W-VX-252 A-11 YI-VHS201A,8 Sigma Ill System to be upgraded A-12 TI-2453 W-VX-252 A-13 LI-2459A W-VX-252 LI-2460 W-VX-252 LI-2461 'r;-VX-252 A-14 H I-HC-201 W-VX-252 A-15 PI-LM-200A W-VX-252 PI-LM-2006 W-VX-252 PI-LM-200C W-VX-252 PI-LM-200D W-VX-252 B-1 NI-2-318, 310, 32B, 32D W-VX-252 NI-2-358, 350, 368, 36D W-VX-252 NI-2-418, 41C, 428, 42C W-VX-252 NI-2-438, 43C, 448, 44C W-VX-252 B-9 LI-2-1310, 1311, 1312 W-VX-252 LI-2-1320, 1321, 1322 W-VX-252 B-12B LI-RS-251A W-VX-252 LI-RS-251B W-VX-252 C-2 RM-CH-228 W (LATER)

RM-CH-229 W (LATER)

C-11 PI-LM-210A W-VX-252 PI-LM-2108 W-VX-252 Page 3 of 3 bhg/10858/45

ATTACHMENT II REGULATORY GUIDE 1.97 REVIEW BASIS NORTH ANNA POWER STATION

1. Electrical Regulatory Guide
a. Reg. Guide 1.89 " Qualification of Class IE Equipment for Nuclear Power Plants.

The North Anna review basis is IEEE-3'23-71, IEEE-323-74 for Units 1 and 2 respectively and 344-71 (as applicable). Equipment test reports were reviewed to determine compliance with the intent of IEEE-323-74 and IEEE-344-1975.

The new equipment review basis is NUREG 0588 Category I requirements or where fully qualified equipment is unavailable, the best available equipment was obtained.

b. Reg. Guide 1.100 " Seismic Qualification of Electric Equipment for Nuclear Power Plants."

The North Anna review basis is IEEE-344-74 or seismic conditions referenced in the test reports for existing equipment.

Page 1 of 6 M;mGBTC{MGS .-

c. Reg. Guide 1.75, " Physical Independence of Electric Systems."

The North Anna electric systems do not conform to the reconmendations in Reg. Guide 1.75 sirce this was not in the original design criteria. New equipment will be integrated into our e.tisting separation provisions. The North Anna separation criteria has been approved b3 the NRC staff as described in Safety Evaluation Report Supplement No. 1. Section 8.4.

d. Reg. Guide 1.32, " Criteria for Safety Related Electric Power Systems for Nuclear Power Plants."

The North Anna review basis is "IEEE Std. 308-71, Criteria for Class IE Electric Systems for Nuclear Power Generating Stations." The North Anna IE Electric Systems have been approved by the NRC staff as describea in the Safety Evaluation Report Section 8.3.3.

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e. Reg. Guide 1.118 " Periodic Testing of Electric Po"er and Protection Systems." This Regulatory Guide invokes the requirements of IEEE 388-75, which are applicable to protection systems. The display l information required by Regulatory Guide 1.97 is not considered to be 1

l part of the protection system and does not require all of the testing 1

specified in IEEE 388-75. The plant equipment being tsed for l

compliance with Regulatory Guide 1.97 - Revision 3 has been designed to incorporate testing capabilities with testing frequencies being in l accordance with the applicable Technical Specifications.

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2. Quality Assurance Regulatory Guides The Vepco Topical Report. Quality Assurance Program Operations Phase.

VEP-1-4A previously approved by the NRC, addresses the conformance of Vepco Operational Quality Assurance Program t'o Quality Assurance Standards, Requirements and Guides.

a. Regulatory Guide 1.28 " Quality Assurance Program Requirements (Design and Construction)".

This Regulatory Guide is not considered a part of the Quality Assurance program. This guide and the standard it endorses have been superseded by R. G. 1.33 (Rev. 2, 2/78) and ANSI N18.7 - 1976.

b. Regulatory Guide 1.30 " Quality Assurance Requirements for the Installation Inspection, and Tescing of Instrumentation and Electric Equipment" (8/72). The Vepco 0.A. Program complies with the requirements of 'tegulatory Guide 1.30 and ANSI N45.2.4-1972-Installaf ton, Inspe: tion and Testing Requirements of j

I Instrumentation and Ekctrical Equipment during the Construction of Nuclear Power Generating Stations with the clarifications contained in Table 17.2.0 of the Topical Report.

I

c. Regulatory Guide 1.38 " Quality Assurance Requirements for j

Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-cooled Nuclear Power Plants (Rev. 2, 5/77)".

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The Vepco Q.A. Program conforms to the requirements of Regulatory Guide 1.38 and ANSI N45.2.2 --1972 - Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants during the Construction phase. Clarifications are contained in Table 17.2.0 of the Topical Report.

d. Regulatory Guide 1.58 " Qualification of Nuclear Power Plant i Inspection, Examination, and Testing Personnel" (Rev. 1, 9/80).

Vepco's program complies with this quide end ANSI N45.2.6 - 1978 -

" Qualification of Inspection, Examination and Testing Personnel for the Construction Phase of Nuclear Power Plants." Clarifications are contained in Table 17.2.0 of the Topical Report.

e. Regulatory Guide 1.64 - Quality Assurance Requirements for the Design l

cf the Nuclear Power Plants (Rev. 2, 6/76). The Vepco Q. A. Program l

conforms to the requirements of Regulatory Guide 1.64 and ANSI N45.2.11 - 1974 - Quality Assurance Requirements for the Design of Nuclear Power Plants. Clarifications are contained in Table 17.2.0 of the Topical Report.

f. Regulatory Guide 1.74 - Quality AssurJ.nce Terms and Definitions (2.74). The Vepco Q. A. Program conforms to the requirements of Regulatory Guide 1.74 and ANSI N45.2.10 - 1973 - Quality Assurance Terms and Definitions. Clarifications are contained in Table 17.2.0 l of the Topical Report.

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g. Regulatory Guide 1.88 - Collection Storage and Maintenance of Nuclear Power Plant Quality Assurance Records (Rev. 2,10/76). The Vepto Q. A. progral.i compiles with this guide and ANSI N45.2.9-1974 Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Records for Nuclear Poder Plants as clartfled in Table 17.2.0 of the Topical Report.
h. Regulatory Guide 1.123 - Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants (Rev.

1, 7/77). The Vepco Q. A. Program conforms to the requirements of Regulatory Guide 1.123 and ANSI N45.2.13 - 1976 - Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants. Clarifications are contained in Table 17.2.0 of the Topical Report.

1. Regulatory Guide 1.144 - Auditing of Quality Assurance Programs for Nuclear Power Plants (Rev. 1, 9/80). The Vepco, Q. A. Program conforms to the requirements of Regulatory Guide 1.144 and ANSI N45.2.12 - 1977 - Requirements for Auditing of Quality Assurance l Programs of Nuclear Power Plants. Clarifications are contained in l

Table 17.2.0 of the Topical Report.

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j. Regulatory Guide 1.146 - Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (Rev. O, 8/80). The Vepco Q. A. Program conforms to the requirements of Regulatory Guide 1.146 and ANSI N45.5.2.23 - 1978 - Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants. Clarifications are contained in Table 17.2.0 of the Topical Report.

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