ML18141A454
| ML18141A454 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/31/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 053, 53, NUDOCS 8402070382 | |
| Download: ML18141A454 (49) | |
Text
- ,. \.. ~"*.
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR 0PEBATI0N9 January 31, 1984 Mr. Harold R. Denton, Director Serial No: 053 Office of Nuclear Reactor Regulation PSE/PJT:jdm:1106B Attn: Mr" Darrell G. Eisenhut, Director Docket Nos: 50-280 Division of Licensing 50-281 U.S. Nuclear Regulatory Commission License Nos: DPR-32 Washington, D. C. 20555 DPR-37 Gentlemen:
VIRGINIA ELECTIRC AND POWER COMPANY SURRY/UNITS 1 & 2 COMPLIANCE WITH REGULATORY GUIDE 1.97 Vepco has performed a comparison study to evaluate the compliance of Surry Power Station's design basis to Regulatory Guide 1. 97 as required by NUREG 0737, Supplement _j_.J The study was performed to the criteria of Regulatory Guide 1.97, Revision 3 in accordance with Section D, "Applicability."
Enclosed is the report of this study.
All modifications identified in the enclosure will be completed by the end of the second refueling after July, 1985 for Units 1 and 2, respectively.
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W. L. Stewart Enclosure cc: Mr. James P. O'Reilly Regional Administrator Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing
-8402070382 840131 .*
e VIRGINIA. ELECTRic AND PoWER CoMPANY To Mr. Harold R. Denton Mr. J. Don Neighbors Surry Project Manager Mailstop 438 7920 Norfolk Ave.
USNRC Bethesda, MD 20014 Mr. D. J. Burke NRC Resident Inspector Surry Power Station
f-~-.
e VEPCO SURRY POWER STATION REG. GUIDE 1.97 REVIEW
- *ses/1106B/5
TABLE OF CONTENTS Title Page Introduction l Variable List 2 Notes and Justifications 31 Attachments I. Indicator Table 35 II. Category I Recorders 38 III. Regulatory Guide 1.97 Review Basis 40 ses/1106B/6
I .
e e INTRODUCTION A review of instrumentation installed at Virginia Electric and Power Company's Surry Power Station has been performed to determine if the existing instrumentation complies with the intent of the range, redundancy, power supply, seismic qualification and environmental qualification requirements of Regulatory Guide 1.97, Rev. 3 <R.G. l.97), 11 Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident. 11 Contained herein are the results of that review.
Also contained is the Variable List for Surry 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.
Attachment II provides a similar summary for recorders.
In initiating the review of existing instrumentation, a baseline set of criteria was developed. To establish these criteria, the Regulatory Guide l .97 - Revision 3 recommended design and qualification criteria were compared to the Surry Power Station design basis. Although the Surry Power Station design basis was effectively established prior to the issuance of many of the Regulatory Guides referenced in Regulatory Guide l .97, the design conforms to the intent of the Regulatory Guides as shown by the comparison in Attachment III. Attachment III lists the required and recommended design documents of Regulatory Guide l .97 and provides a comparison to the applicable Surry Power Station design basis.
r"l\<' /11.")C.Q/;
e e VARIABLE LIST GUIDE
- 1. The following terminology applies for the Surry Power Station Variable List:
N/R - Not Required N/A - Not Applicable YES - Complies with the intent of Reg. Guide 1.97.
NO Does not comply with the intent of Reg. Guide l .97.
- Justification is stated.
- 2. Control Room Display - Reg. Guide 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, written or verbal, and logged.
ses/1106B/8
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALi FI CATI ON QUALi FI CATI ON REDUNDANCY A-1 Steam Generator l Yes Yes Yes No Narrow Range Level A-2 Steam Generator 1 Yes Yes Yes No Pressure A-3 Core Exit Temperature 1 No No No No e
A-4 RCS Cold Leg 1 Yes No No Yes Water Temperature A-5 RCS Hot Leg 1 Yes No No Yes Water Temperature A-6 RCS Flow 1 Yes No No Yes A-7 RCS Wide Range 1 Yes No No Yes Pressure A-8 H.P.S.I. Flow 1 Yes No No No Condensate Storage Yes Yes Yes Yes A-9 Tank Water Level 1
. e A-10 Refueling Water 1 Yes Yes Yes Yes Storage Tank Level A-11 PORV Position 1 Yes No No No Indication_
A-12 Pressurizer 1 Yes No No No Liquid Temp.
PAGE 1 OF 28
VIRGINIA ELECTRIC AND ruw~R UUM.l'ANY REG. GUIDE 1,97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION -
A-1 Yes Yes Yes Yes Acceptable; Note l A-2 Yes Yes Yes Yes Acceptable; Note l A-3 Yes Yes Yes Yes System to be upgraded.
A-4 Yes Yes Yes Yes Yes Yes Yes RTD's to be replaced RTD's to be replaced e
A-5 Yes A-6 Yes Yes Yes Yes Notes l and 2 A-7 Yes Yes , Yes Yes Note l A-8 Yes Yes Yes Yes Relocate and replace transmitters above submergence level.
Separation of flow channels required.
A-9 Yes Yes Yes Yes Acceptable A-10 Yes Yes Yes Yes Note l A-11 No Yes Yes Yes System to be upgraded.
A-12 Yes Yes Yes Yes Replace present RTD with qualified dual element RTD, install a second channel.
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2 OF 28 VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC . ,
NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY A-13 Pressurizer Level l Yes Yes Yes Yes A-14 Containment l Yes Yes Yes Yes Hydrogen Concentration A-15 Containment Intermediate Range Pressure l Yes Yes Yes No e
A-16 Indicators l Yes Reference Reference N/R Attachment I Attachment l A-17 Recorders l Yes Reference Reference N/R Attachment II Attachment I 8-1 Neutron Flux 1 Yes No No Yes B-2 Control Rod 3 Yes N/R N/R N/R Position B-3 RCS Soluble Boron 3 Yes N/R N/R N/R Concentration B-4 RCS Cold Leg Water 3 Refer to Item A-4 e
Temperature B-5 RCS Hot Leg Water l Refer to Item A-5 Temperature B-6 RCS Cold Leg Water l Refer to Item A-4 Temperature PAGE 3 OF 28 VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER 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 Note 1 A-16 N/A Yes Yes
- Yes Reference Attachment I; Note 1 e A-17 N/A Yes Yes Yes Reference Attachment II; Note 1 8-1 Yes Yes Yes Yes Install new excore flux
( monitoring system 8-2 N/R Yes Yes Yes Acceptable 8-3 N/R Yes Yes Yes The boron concentration can be determined by the manual grab sample and/or post-accident sampling system.
8-4 Refer to Item A-4 8-5 Refer to Item A-5 e 8-6 Refer to Item A-4 PAGE 4 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALi FI CATION REDUNDANCY B-7 RCS Pressure l Refer to Item A-7 B-8 Core Exit 3 Refer to Item A-3 Temperature B-9 Coolant Level l Yes Yes Yes Yes B-10 in reactor Degrees of 2 Yes Yes N/R N/R e
Subcooling
B-128 Containment Sump l Yes Yes Yes Yes Water Level (Wide)
B-13 Containment l Yes Yes Yes Yes Pressure B-14 Containment Isolation l Yes Yes Yes Yes e Valve Position PAGE 5 OF 28 VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION
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ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION B-7 Refer to Item A-7 B-8 Refer to Item A-3 B-9 Yes Yes Yes Yes Acceptable; Note 1 B-10 B-11 Yes Yes Yes Yes Acceptable Refer to Item A-7 e
B-12A Yes Yes Yes Yes Acceptable B-12B Yes Yes Yes Yes Acceptable B-13 Yes Yes Yes Yes Acceptable B-14 Yes. Yes Yes Yes Acceptable e
PAGE 6 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALi FI CATI ON QUALIFICATION REDUNDANCY B-15 Canta inment 1 Yes Yes Yes Yes Pressure C-1 Core Exit 1 Refer to Item A-3 Temperature C-2 Radioactivity Concentration or Radiation Level in Circulating 1 Yes No No Yes Primary Coolant C-3 Analysis of 3 Yes N/R N/R N/R Primary Coolant (Gamma Spectrum)
C-4 RCS Pressure 1 Refer to Item A-7 C-5 Containment 1 Yes Yes Yes Yes Pressure C-6A Containment 2 Refer to Item B-12 ..
Sump Water Level (Narrow) e C-68 Canta inment 1 Ref er to Item B-12 ~
Sump Water Level (Wide)
C-7 . Canta inment 3 Refer to Item E-1 Area Radiation PAGE 7 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION B-15 Yes Yes Yes Yes Acceptable C-1 Refer to Item A-3.
C-2 No Yes Yes Yes Note 4 C-3 C-4 N/R Yes Yes Yes Acceptable Refer to Item A-7 e
C-5 Yes Yes Yes Yes Acceptable C-6A I Refer to Item B-12A C-68 Refer to Item B-12B C-7 Refer to Item E-1 e
PAGE 8 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALi FI CATI ON QUALIFICATION REDUNDANCY C-8 Effluent Radio- 3 Refer to Item E-6 activity Noble and E-7
' Gas Effluent from Condenser Air Removal System Exhaust C-9 RCS Pressure 1 Refer to Item A-7 e
C-10 Containment l Refer to Item A-14 Hydrogen Concentration C-11 Containment 1 . Yes Yes Yes Yes Pressure C-12 Containment 2 Yes Yes N/R N/R Effluent Radioactivity -
Noble Gases from Identified Release Points e
PAGE 9 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION -
C-8 Function covered by Item E-6
&E-7 C-9 Refer to Item A-7 C-10 Refer to Item A-14 C-11 Yes Yes Yes Yes Acceptable e C-12 Yes Yes Yes Yes Acceptable I
e PAGE 10 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUAL! FI CATI ON QUALIFICAnON REDUNDANCY C-13 Radiation Exposure 2 Yes Yes N/R N/R Rate (inside
. buildings or areas, e.g.,
auxiliary building, reactor shield building annulus, fue 1 hand 1ing e
building, which are in direct contact with primary containment where penetrations and hatches are located)
C-14 Effluent Radio- Refer to item E-7 activity Noble Gases (from buildings as indicated in C-13)
D-1 RHR System Flow 2 Yes No N/R N/R e D-2 RHR Heat Exchanger 2 Yes No N/R N/R Outlet Temperature D-3 Accumulator: 2 No No N/R N/R Tank Level PAGE 11 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION -
C-13 Yes Yes Yes Yes Acceptable C-14 Provided by Item E-7 D-1 Yes Yes Yes Yes Consider Category 3 variable. See Note 9 D-2 Yes Yes Yes Yes Consider Category 3 variable. See Note 9 e D-3 Yes Yes Yes Yes Consider Category 3. See Note -10
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e PAGE 12 OF 28 VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALI FI CATI ON REDUNDANCY D-4 Accumulator 2 Yes No N/R N/R Tank Pressure D-5 Accumulator 2 Yes N/R N/R N/R Isolation Valve Position D-6 Boric Acid 2 Yes No N/R N/R e Charging (Flow}
D-7 Flow in HPI 2 Refer to Item A-8 System D-8 Flow in LPI 2 Yes Yes N/R N/R System D-9 Refueling Water 2 Refer to Item A-10 Storage Tank Level D-10 Reactor Coolant 3 Yes N/R N/R N/R Pump Status e
-.15- PAGE 13 OF~
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION -
D-4 Yes Yes Yes Yes Consider Category 3. See Note 10 D-5 Yes Yes Yes Yes Consider Category 3. See Note 10 Yes Transmitter to be replaced D-6 D-7 Yes Yes Yes Refer to Item A-8 e
D-8 Yes Yes Yes Yes Acceptable D-9 (
Refer to Item A-10 D-10 N/R Yes Yes Yes. Acceptable e
PAGE-14-OF VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION
- r ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY D-1 l Primary System 2 Refer to Item A-11 Safety Relief
' Valve Position (including PORV valves}
D-12 Pressurizer Level l No Yes Yes No e 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
- 0~15 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 l Yes No No Yes D-18
. D-19 Level Steam Generator Pressure Safety-Relief l
2 No Refer to Item A-2 No N/R N/R Valve Positions D-20
- Ma in Feedwater 3 Yes N/R N/R N/R Flow PAGE 15 OF 28
VIRGINIA ELECTRIC ANU l'UWt;l{ CUM.t'AN'.i REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION D-11 Refer to Item A-11 D-12 Yes Yes Yes Yes Add density compensation to reduce error and expand range of transmitters to full range allowed by taps. Note 7 D-13 Yes Yes Yes Yes Note 5 e D-14 N/R Yes Yes Yes Acceptable. Existing range covers approximately 90% of tank height.
I D-15 N/R Yes Yes Yes Note 6 D-16 N/R Yes Yes Yes Acceptable D-17 Yes Yes Yes Yes Transmitters to be replaced.
Notes 1 and 3 D-18 Refer to Item A-2 D-19 No No No No Install position detector and indicator Acceptable e
D-20 N/R Yes Yes Yes PAGE 16 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1. 97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALi FI CATI ON QUALIFICATION REDUNDANCY D-21 Auxiliary or 2 Yes Yes N/R N/R Emergency
' Feedwater Flow D-22 Condensate 1 Refer to Items A-9 Storage Tank D-23 Level Containment 2 No No N/R N/R e
Spray Flow D-24 Heat Removal by 2 No No N/R N/R the Canta inment Fan Heat
. Removal System D-25 Containment 2 No No N/R N/R Atmosphere 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 e
D-28 Letdown Flow-Out 2 ,Yes No N/R N/R D-29 Volume Control 2 No No N/R N/R Tank Level PAGE 17 OF _1L
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION -
D-21 Yes Yes Yes Yes Acceptable D-22 Refer to Item A-9 D-23 No No - - Note 8 D-24 No No Yes Yes Add qualified flow transmitters and temperature elements.
e D-25 Yes Yes Yes Yes Replace with qualified RTD and Rescale I
D-26 Yes Yes Yes Yes Note 11 D-27 Yes Yes Yes Yes Replace with qualified transmitter D-28 Yes Yes Yes Yes Replace with qualified transmitter D-29 Yes Yes Yes Yes Replace with qualified transmitters; Note 12 e
PAGE 18 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY D-30 Component Cooling 2 No No N/R N/R Water Temperature
' to ESF Systems D-31 Component Cooling 2 No No N/R N/R Water Fl ow to ESF Systems D-32 High-Level 3 Yes N/R N/R N/R e
Radioactive Liquid Tank Level D-33 Radioactive Gas 3 No N/R N/R N/R Holdup Tank Pressure D-34 Emergency 2 No No N/R N/R Ventilation Damper Position I
D-35A 4160 Emergency 2 Yes Yes No N/R Bus-Availability D-35B 480 V Emergency Bus-Availability 2 No No No N/R e D-35C 125VDC Status 2 Yes Yes Yes N/R D-35D . 120 VAC Vital 2 Yes Yes Yes N/R Bus Status_
D-35E 120 VAc' Semi- 2 Yes Yes Yes N/R Vital Bus Status PAGE 19 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION D-30 No No Yes Yes Install temperature channel to monitor operation at the charging pump cooling system D-31 No Yes Yes Yes Install flow channel to monitor charging pump cooling system D-32 N/R Yes Yes Yes Acceptable e
D-33 Yes Yes Yes Yes Rescale existing instruments D-34 Yes No I Yes Yes Install Limit switches D-35P Yes Yes Yes Yes For items D-35A - D35 F control room displays will be available once the Multiplex systems is installed.
D-35E Yes Yes Yes Yes D-35( Yes Yes Yes Yes D-35[
D-35E Yes Yes Yes Yes Yes Yes Yes Yes e
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VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY D-35F Emergency Diesel 2 Yes Yes No N/R Generator Watts Status E-1 Containment l Yes Yes Yes Yes Area Radiation E-2 Radiation Exposure Rate (inside 3 Yes N/R N/R N/R e buildings or areas where access .I is required to service equipment important to safety)
E-3 Containment or 2 N/R N/R N/R N/R Purge Effluent E-4 Reactor Shields 2 N/R N/R N/R N/R Buildings Annulus (if in design)
E-5 Auxiliary Building (including any building containing primary system 2 Yes Yes N/R N/R gases, e.g.,
waste gas decay tank) -
E-6 Condenser Air 2 N/R N/R N/R N/R Removal System Exhaust PAGE 21 OF
-28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF . REMARKS DISPLAY LOCATION LOCATION D-35F Yes Yes Yes Yes E-1 Yes Yes Yes Yes Acceptable E-2 Yes Yes Yes Yes Acceptable E-3 N/R N/R N/R N/R Delete - Effluent discharge E-4 N/R N/R N/R N/R through common plant vent Delete - Effluent discharges e
through common plant vent E-5 Yes Yes Yes Yes Acceptable E-6 N/R N/R ' N/R N/R Delete - Effluent discharges through common EJant vent e
PAGE22._0F--21L.
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUAL I FI CAT I ON QUALi FI CATI ON REDUNDANCY E-7 Common Plant 2 Yes Yes N/R N/R Vent or Multi-purpose Vent Discharging Any of Above Release
( if containment purge is included)
E-8 Vent from Steam 2 Yes Yes N/R N/R e
Generator Safety Relief Valves or Atmospheric Dump Valves E-9 All Other None I entified Identified Release Points E-10 Al 1 Identified 3 Yes N/R N/R N/R Plant Release Points (except steam generator safety relief valves or atmospheric steam dump valves and condenser air removal system exhaust).
Sampling with Onsite Analysis Capability.
PAGE 23 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION -
E-7 Yes Yes Yes Yes Acceptable E-8 Yes Yes Yes Yes Acceptable E-9 None Identified E-10 N/R Yes Yes Yes Acceptable e
I e
PAGE 24 OF 28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALi FI CATI ON QUALI FI CATI ON REDUNDANCY E-11 Airborne Radio- 3 Yes N/R N/R N/R halogens and
' Particulates (portable sampling with onsite analysis E-12 capability)
Plant and 3 No N/R N/R N/R e
Environs Radiation (portable instrumentation)
E-13 Plant Environs 3.
- Yes N/R N/R N/R Radioactivity (portable instrumentation)
E-14 Wind Direction 3 Yes N/R N/R N/R E-15 Wind Speed 3 Yes N/R N/R N/R E-16 Estimation of Atmospheric Stability 3 Yes N/R N/R N/R PAGE2 5 OF 28
V1KG 1N iA ELEC'l'KlC AN!J 1'UW~K CUM.I:' Al'H.
REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION -
E-11 N/R For Item* E E-1~, Acceptable Manual d< cumented re* ults E-12 N/R are avai able to the operator. Purchase additional portable instrumentation to cover range to 104 R/Hr (common to both units).
E-13 N/R Acceptable e E-14 N/R Yes Yes Yes Acceptable E-15 N/R Yes Yes Yes Acceptable
(
E-16 N/R Yes Yes Yes Acceptable e
PAGE26
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28
VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM ENVIRONMENTAL SEISMIC NUMBER VARIABLE CATEGORY RANGE QUALIFICATION QUALIFICATION REDUNDANCY E-17 Primary Coolant 3 Yes N/R N/R N/R and Sump Sampling and Analysis E-18 Containment 3 Yes N/R N/R N/R Air Sample e
e PAGE 27 OF 28
VIRGINIA ELECTRIC AND POWER CUM.l'ANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ITEM POWER CONTROL NUMBER SOURCE ROOM TSC EOF REMARKS DISPLAY LOCATION LOCATION E-17. N/R Yes Yes Yes Acceptable E-18 N/R Yes Yes Yes Acceptable e
I PAGE 28 OF 28 VARIABLE LIST SURRY POWER STATION NOTES AND JUSTIFICATIONS Note l: 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. The data for each channel will be accessible to the operator via call-up from CRT s in the Control Room.
1 The CRTs
- will be capable of receiving data from either of two redundant computer systems which are fed by a redundant qualified 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 0-575 11 HzO. This range covers from 14 11 above the tube sheet to the separators which is 97.6% of the required range which meets the intent of R.G. 1.97.
Page _l_ of _!_
e e Note 4: Two independent and redundant systems are available 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-218, 219, 118, 119 and the new Post Accident System are the systems to be used 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.
Note 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 rupture disk will provide a relief path to the containment atmosphere. Therefore, any relief from the pressurizer 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 guide once temperature compensation is added. Present instrumentation covers 390 of the 500 height of the pressurizer.with only the curvature 11 11 portions of the vessel not being covered.
Page - 2 of - 4
,;~i;/l 106B/38
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- e Note 8: Existing instrumentation is considered adequate. A pressure switch is installed on the discharge side of each Containment Spray Pump to monitor low pressure with annunciator alarm available in the control room.
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 9.3.2.2. 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 i.s required to obtain the accuracy needed to meet technical specification conditions and meet the intent of R.G. 1.97. Variables D-3, D-4 and D-5 are located below the flood plane after accident and environmentally qualified only for the environment that they see during normal plant operations. During power operations, the power to the accumulator isolation valve, which is open, is removed with the breaker being verified locked open by Technical Specification during start-up procedure. Therefore, accumulator pressure, level and valve position indication serve as a Page _L of _..1_
ses/ll06B/39
/f/1
- means to determine accumulator status during normal operations and to ensure their capability to perform their automatic accident function which is independent of electrical signals and strictly mechanical in nature. Therefore, these variab1es should be classified as Category 3 and considered qualified for their intended normal operati*ng environment functions.
Note 11: The containment sump temperature indication is not required based on the regulatory position delineated in Safety Guide 1 Net Positive 11 Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps. 11 Vepco s Emergency Core Cooling and Containment Heat 1
Removal System pumps which take suction from the containment sump when the refueling water storage tank is empty were analyzed under LOCA condition in section 6.3 of the UFSAR to.ensure sufficient NPSH to 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 tank volume. This range is satisfactory to monitor the operating range of the variable which meets the intent of R.G. 1.97.
Page _i_ of _i_
ses/11068/40 .....
- ATTACHMENT I UNIT l INDICATORS SURRY POWER STATION e
ITEM NO. MARK NO. MANUFACTURER TYPE A-1 LI-1474, 1484, 1494 Hagan 107 LI-1475, 1485, 1495 LI-1476, 1486, 1496 A-2 Pl-1474, 1484, 1494 Hagan 107 PI-1475, 1485, 1495 PI-1476, 1486, 1496 A-3 Thermocouple Indicators Honeywell System To Be Replaced A-6 FI-1414, 1415, 1416 Hagan 107 FI-1424, 1425, 1426 Hagan 107 FI-1434, 1435, 1436 Hagan 107 A-7 PI-1402, 1402-1 Westinghouse VX-252*
A-8 FI-1940, 1943 Hagan 107 FI-1932, 1933, 1960 Hagan 107 FI-1961, 1962, 1963 Hagan 107 A-9 LI-CN-100, l 01 Sigma 9270 A-10 LI-CS- l OOA , 1008 Hagan 107 LI-CS- 1OOC, 1000 Westinghouse VX-252*
A-11 YI-VMSl 01 A, B Sigma I 11 . System to be upgraded A-12 TI-1453 Hagan 107 A-13 LI-1459, 1460, 1461 Hagan 107 A-14 H2I-GW-104-l, 104-2 . Hagan 107 A-15 PI-LM-lOOA, 1008 Hagan 107 PI-LM-lOOC, 1000 B-1 NI-1-418, 428, 438 Hagan 107 NI-1-448 NI-l-41C, 42C, 43C NI-l-44C NI-1-318, 328, 358 NI-1-368 NI-1-318, 320, 350 NI-l-36D
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ATTACHMENT I (CONT'D>
UNIT l e
INDICATORS SURRY POWER STATION ITEM NO. MARK NO. MANUFACTURER TYPE B-9 LI-1-1310, 1311, Westinghouse VX-252*
LI-1-1312, 1320, LI-1-1322, 1321 B-12B LI-RS-151A, l51B Westinghouse VX-252*
C-2 RM-CH- 118, 11 9 Victoreen 844-18 C-11 PI-LM-lOlA, 1018 Westinghouse VX-252*
UNIT 2 ITEM NO. MARK NO. MANUFACTURER TYPE A-1 LI-2474, 2484, 2494 Hagan 107 LI-2475, 2485, 2495 LI-2476, 2486, 2496 A-2 PI-2474, 2484, 2494 Hagan 107 PI-2475, 2485, 2495 PI-2476, 2486, 2496 A-3 Thermocouple Indic~tors Honeywe 11 System To Be Replaced A-6 FI-2414, 2415, 2416 Hagan 107 FI-2424, 2425, 2426 Hagan l 07 FI-2434, 2435, 2436 Hagan 107 A-7 PI-2402, 2402-1 Westinghouse VX-252*
A-8 FI-2940, 2943 Hagan 107 FI-2932, 2933, 2960 Hagan 107 FI-2961, 2962, 2963 Hagan 107 A-9 LI-CN-200 ~ l 01 Sigma 9270 A-10 LI-CS-200A, 1008 Hagan 107 LI-CS-200C, lOOD Westinghouse VX-252*
A-11 YI-VMS201A, B Sigma Ill. System to be upgraded
- Qualifi~d Indicators Page _2_ of _J_
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- ATTACHMENT I (CONT'D)
UNIT 2 INDICATORS SURRY POWER STATION e
ITEM NO. MARK NO. MANUFACTURER TYPE A-12 TI-2453 Hagan 107 A-13 LI-2459, 2460, 2461 Hagan 107 A-14 H2I-GW-204-1, 204-2 Hagan 107 A-15 PI-LM-200A, 200B Hagan 107 PI-LM-200C, 2000 B-1 NI-2-41B, 42B, 43B Hagan 107 NI-2-44B NI-2-41C, 42C, 43C NI-2-44C NI-2-31B, 32B, 35B NI-2-36B NI-2-31B, 320, 350 NI-2-360 B-9 LI-2-1310, 1311 , Westinghouse VX-252*
LI-2-1312, 1320, LI-2-1322, 1321 B-128 LI-RS-251A, 251B Westinghouse VX-252*
C-2 RM-CH-218, 219 Victoreen 844-18 C-11 PI-LM-201A, 201B Westinghouse VX-252*
- Qualified Indicators Page _L of _3_
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... . e e ATTACHMENT II UNIT 1 RECORDERS SURRY POWER STATION ITEM NO. MARK NO. MANUFACTURER TYPE A-4 TR-1413 Westinghouse Optimac 101 TR-1423 Westinghouse Optimac 101 TR-1433 Westinghouse PAM recorder A-5 Uses same recorders as Item A-4 A-13 LR-1459 Westinghouse Optimac 101 A-14 HzR-GW-104 Westinghouse PAM recorder B-9 LR-1-1310 Westinghouse Optimac 101 C-11 PR-LM-lOlA Westinghouse PAM recorder D-17 LR-1477 Westinghouse Opti mac l 01 E-1 RR-RMS 127 Westinghouse PAM recorder RR-RMS 128 Page _l_ of -1._
ses/11066/44
- ~- e ATTACHMENT II (CONT'D)
UNIT 2 RECORDERS SURRY POWER STATION ITEM NO. MARK NO. MANUFACTURER TYPE A-4 TR-2413 Westinghouse Optimac l 01 TR-2423 Westinghouse Opti mac 101 TR-2433 Westinghouse PAM recorder A-5 Uses same recorders as Item A-4 A-13 LR-2459 Westinghouse Optimac 101 A-14 HzR-GW-204 Westinghouse PAM recorder B-9 LR-1-2310 Westinghouse Optimac 101 C-11 PR-LM-201A Westinghouse PAM recorder D-17 LR-2477 Westinghouse Opti mac 101 E-1 RR-RMS 227 Westinghouse PAM recorder RR-RMS 228 Page _2_ of _.L ses/1106B/45
I I
I ATTACHMENT III REGULATORY GUIDE 1.97 REVIEW BASIS SURRY POWER STATION
- 1. Electrical Regulatory Guide
- a. Reg. Guide l .89 - 11 Qualification of Class IE Equipment for Nuclear Power Plants.
The Surry review basis is IEEE-323-71 and 344-71 (as applicable> with the environmental and seismic conditions referenced in the test reports for existing equipment. Items addressed were reviewed under IE Bulletin 79-0lB requirements.
The new equipment review basis is IE Bulletin 79-0lB Category I requirements referenced in the test report or where fully qualified equipment is unavailable, the best available equipment was obtained.
- b. Reg. Guide 1.100 - 11 Seismic Qualification of Electric Equipment for Nuclear Power Plants. 11 The Surry review basis is IEEE-344-71 or seismic conditions referenced in the test reports for existing equipment.
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- c. Reg. Guide 1.75, "Physical Independence of Electric Systems. 11 The Surry electric systems do not conform to the recommendations in Reg. Guide 1.75 since this was not in the original design criteria.
New equipment will be integrated into our existing separation provisions.
- d. Reg. Guide 1.32, "Criteria for Safety Related Electric Power Systems for Nuclear Power Plants. 11 The Surry review basis is IEEE Std. 308-71, Criteria for Class IE 11 Electric Systems for Nuclear Power Generating Stations. 11
- e. Reg. Guide l .118 - Periodic Testing of Electric. Power and Protection 11 Systems. 11 This Regulatory Guide invokes the requirements of IEEE 388-75, which are applicable to protection systems. The display information required by Regulatory Guide 1.97 is not considered to be part of the protection system and does not require all of the testing specified in IEEE 388-75. The plant equipment being used for compliance with Regulatory Guide l .97 - Revision 3 has been designed to incorporate testing capabilities with testing frequencies being in accordance with the applicable Technical Specifications.
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..* ... e e
- 2. Quality Assurance Regulatory Guides The Vepco Topical Report, Quality Assurance Program Operations Phase, VEP-1-44 previously approved by the NRC, addresses the conformance of Vepco Operational Quality Assurance Program to Quality Assurance Standards, Requirements and Guides.
- a. Regulatory Guide 1.28 - Quality Assurance Program Requirements 11
<Design and Construction> 11 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. l .33 (Rev. 2, 2/78) and ANSI Nl8.7-1976.
- b. Regulatory Guide 1.30 - Quality Assurance Requirements for the 11 Installation Inspection, and Testing of Instrumentation and Electric Equipment (8/72).
11 The Vepco Q.A. Program complies with the requirements of Regulatory Guide 1.30 and ANSI N45.2.4-1972-Installation, Inspection and Testing Requirements of Instrumentation and Electrical Equipment during the Construction of Nuclear Power Generating Stations with the clarifications contained in table 17.2.0 of the Topical Report.
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c.
Regulatory Guide 1.38 - "Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-cooled Nuclear Power Plants <Rev. 2, 5/77) 11
- 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 Inspection, Examination, and Testing Personnel" (Rev. 1, 9/80).
Vepco's program complies with this guide and 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 of the Nuclear Power Plants (Rev. 2, 6/76). The Vepco Q. A. Program conforms to the requirements of Regulatory Guide l .64 and ANSI N45.2.ll - 1974 - Quality Assurance Requirements for the Design of Nuclear Power Plants. Clarifications are contained in Table 17.2.0 of the Topical Report.
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411 **
f.
e -
Regulatory Guide l .74 - Quality Assurance 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 of the Topical Report.
- g. Regulatory Guide 1.88 - Collection Storage and Maintenance of Nuclear Power Plant Quality Assurance Records <Rev. 2, 10/76}. The Vepco Q. A. program complies with this guide and ANSI N45.2.9-1974 Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Records for Nuclear Power Plants as clarified 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.
l, 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.
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i.
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 Programs of Nuclear Power Plants. Clarifications are contained in Table 17.2.0 of the Topical Report.
- j. Regulatory Guide 1. 146 - Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants <Rev. 0, 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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