ML18141A454

Forwards Comparison Study to Evaluate Facility Design Basis Compliance to Reg Guide 1.97,per NUREG-0737,Supp1 1.Mods Identified in Encl Will Be Completed by End of Second Refueling After Jul 1985 for Each Unit

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 Office of Nuclear Reactor Regulation Attn: Mr" Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTIRC AND POWER COMPANY SURRY/UNITS 1 & 2 COMPLIANCE WITH REGULATORY GUIDE 1.97 Serial No: 053 PSE/PJT:jdm:1106B Docket Nos: 50-280 50-281 License Nos: DPR-32 DPR-37 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. the (All modifications identified in the enclosure will be completed by the end of second refueling after July, 1985 for Units 1 and 2, respectively.

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 .* PDR ADOCK 05000280 F PDR W. L. Stewart 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-~-. -*ses/1106B/5 VEPCO SURRY POWER STATION REG. GUIDE 1.97 REVIEW e

,. 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

. ITEM NUMBER VARIABLE A-1 Steam Generator Narrow Range Level ' A-2 Steam Generator Pressure A-3 Core Exit Temperature A-4 RCS Cold Leg Water Temperature A-5 RCS Hot Leg Water Temperature A-6 RCS Flow A-7 RCS Wide Range Pressure A-8 H.P.S.I. Flow A-9 Condensate Storage Tank Water Level A-10 Refueling Water Storage Tank Level A-11 PORV Position Indication_

A-12 Pressurizer Liquid Temp. VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALi FI CA TI ON l Yes Yes 1 Yes Yes 1 No No 1 Yes No 1 Yes No 1 Yes No 1 Yes No 1 Yes No 1 Yes Yes 1 Yes Yes 1 Yes No 1 Yes No SEISMIC QUALi FI CA TI ON REDUNDANCY Yes No Yes No No No e No Yes No Yes No Yes No Yes No No Yes Yes e . Yes Yes No No No No PAGE 1 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY A-1 Yes Yes A-2 Yes Yes A-3 Yes Yes A-4 Yes Yes A-5 Yes Yes A-6 Yes Yes A-7 Yes Yes A-8 Yes Yes A-9 Yes Yes A-10 Yes Yes A-11 No Yes A-12 Yes Yes VIRGINIA ELECTRIC AND ruw~R UUM.l'ANY REG. GUIDE 1,97 VARIABLE LIST SURRY POWER STATION -TSC EOF REMARKS LOCATION LOCATION -Yes Yes Acceptable; Note l Yes Yes Acceptable; Note l Yes Yes System to be upgraded.

Yes Yes RTD's to be replaced Yes Yes RTD's to be replaced Yes Yes Notes l and 2 , Yes Yes Note l Yes Yes Relocate and replace transmitters above submergence level. Separation of flow channels required.

Yes Yes Acceptable Yes Yes Note l Yes Yes System to be upgraded.

Yes Yes Replace present RTD with qualified dual element RTD, install a second channel. PAGE 2 OF 28 ----e

. ITEM NUMBER VARIABLE A-13 Pressurizer Level A-14 Containment Hydrogen Concentration A-15 Containment Intermediate Range Pressure A-16 Indicators A-17 Recorders 8-1 Neutron Flux B-2 Control Rod Position B-3 RCS Soluble Boron Concentration B-4 RCS Cold Leg Water Temperature B-5 RCS Hot Leg Water Temperature B-6 RCS Cold Leg Water Temperature VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALIFICATION l Yes Yes l Yes Yes l Yes Yes l Yes Reference Attachment I l Yes Reference Attachment II 1 Yes No 3 Yes N/R 3 Yes N/R 3 Refer to Item A-4 l Refer to Item A-5 l Refer to Item A-4 SEISMIC . , QUALIFICATION REDUNDANCY Yes Yes Yes Yes Yes No e Reference N/R Attachment l Reference N/R Attachment I No Yes N/R N/R N/R N/R e PAGE 3 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY A-13 Yes Yes A-14 Yes Yes A-15 Yes Yes A-16 N/A Yes A-17 N/A Yes 8-1 Yes Yes 8-2 N/R Yes 8-3 N/R Yes 8-4 8-5 8-6 VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF REMARKS LOCATION LOCATION -Yes Yes Acceptable Yes Yes Acceptable Yes Yes Note 1 Yes

• Yes Reference Attachment I; Note 1 Yes Yes Reference Attachment II; Note 1 Yes Yes Install new excore flux ( monitoring system Yes Yes Acceptable Yes Yes The boron concentration can be determined by the manual grab sample and/or post-accident sampling system. Refer to Item A-4 Refer to Item A-5 Refer to Item A-4 PAGE 4 OF 28 e e

. ITEM NUMBER VARIABLE B-7 RCS Pressure B-8 Core Exit Temperature B-9 Coolant Level in reactor B-10 Degrees of Subcooling

• B-11 RCS Pressure B-12A Containment Sump Pump Level (Narrow) B-128 Containment Sump Water Level (Wide) B-13 Containment Pressure B-14 Containment Isolation Valve Position -VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALIFICATION l Refer to Item A-7 3 Refer to Item A-3 l Yes Yes 2 Yes Yes l Refer to Item A-7 2 Yes Yes l Yes Yes l Yes Yes l Yes Yes SEISMIC QUALi FI CATION REDUNDANCY Yes Yes e N/R N/R N/R N/R Yes Yes Yes Yes Yes Yes e PAGE 5 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY B-7 B-8 B-9 Yes Yes B-10 Yes Yes B-11 B-12A Yes Yes B-12B Yes Yes B-13 Yes Yes B-14 Yes. Yes VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION TSC EOF REMARKS LOCATION LOCATION -Refer to Item A-7 Refer to Item A-3 Yes Yes Acceptable; Note 1 Yes Yes Acceptable Refer to Item A-7 Yes Yes Acceptable Yes Yes Acceptable

' Yes Yes Acceptable Yes Yes Acceptable -1 . e e PAGE 6 OF 28

. ITEM NUMBER VARIABLE B-15 Canta inment Pressure C-1 Core Exit Temperature C-2 Radioactivity Concentration or Radiation Level in Circulating Primary Coolant C-3 Analysis of Primary Coolant (Gamma Spectrum)

C-4 RCS Pressure C-5 Containment Pressure C-6A Containment Sump Water Level (Narrow) C-68 Canta inment Sump Water Level (Wide) C-7 . Canta inment Area Radiation VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALi FI CA TI ON 1 Yes Yes 1 Refer to Item A-3 1 Yes No 3 Yes N/R 1 Refer to Item A-7 1 Yes Yes 2 Refer to Item B-12 .. 1 Ref er to Item B-12 3 Refer to Item E-1 SEISMIC QUALIFICATION REDUNDANCY Yes Yes No Yes -N/R N/R Yes Yes e PAGE 7 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY B-15 Yes Yes C-1 C-2 No Yes C-3 N/R Yes C-4 C-5 Yes Yes C-6A C-68 C-7 VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF REMARKS LOCATION LOCATION -Yes Yes Acceptable Refer to Item A-3. Yes Yes Note 4 Yes Yes Acceptable Refer to Item A-7 Yes Yes Acceptable Refer to Item B-12A I Refer to Item B-12B Refer to Item E-1 e e PAGE 8 OF 28 ----

. ITEM NUMBER VARIABLE C-8 Effluent Radio-activity Noble ' Gas Effluent from Condenser Air Removal System Exhaust C-9 RCS Pressure C-10 Containment Hydrogen Concentration C-11 Containment Pressure C-12 Containment Effluent Radioactivity

-Noble Gases from Identified Release Points -VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALi FI CA TI ON 3 Refer to Item E-6 and E-7 1 Refer to Item A-7 l Refer to Item A-14 1 . Yes Yes 2 Yes Yes SEISMIC QUALIFICATION REDUNDANCY e Yes Yes N/R N/R e PAGE 9 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY C-8 C-9 C-10 C-11 Yes Yes C-12 Yes Yes VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF LOCATION LOCATION REMARKS -Function covered by Item E-6 & E-7 Refer to Item A-7 Refer to Item A-14 Yes Yes Acceptable Yes Yes Acceptable I ' PAGE 10 OF 28 . -e e

-ITEM NUMBER VARIABLE C-13 Radiation Exposure Rate (inside . buildings or areas, e.g., auxiliary building, reactor shield building annulus, fue 1 hand 1 ing building, which are in direct contact with primary containment where penetrations and hatches are located) C-14 Effluent Radio-activity Noble Gases (from buildings as indicated in C-13) D-1 RHR System Flow D-2 RHR Heat Exchanger Outlet Temperature D-3 Accumulator:

Tank Level VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE Q UAL! FI CA TI ON 2 Yes Yes Refer to item E-7 2 Yes No 2 Yes No 2 No No SEISMIC QUALIFICAnON REDUNDANCY N/R N/R e N/R N/R e N/R N/R N/R N/R PAGE 11 OF 28 ---__ . ---, ___ J ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY C-13 Yes Yes C-14 D-1 Yes Yes D-2 Yes Yes D-3 Yes Yes VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION . TSC EOF REMARKS LOCATION LOCATION -Yes Yes Acceptable Provided by Item E-7 Yes Yes Consider Category 3 variable.

See Note 9 Yes Yes Consider Category 3 variable.

See Note 9 Yes Yes Consider Category 3. Note 10 -( . , . e See e PAGE 12 OF 28

. ITEM NUMBER VARIABLE D-4 Accumulator Tank Pressure D-5 Accumulator Isolation Valve Position D-6 Boric Acid Charging (Flow} D-7 Flow in HPI System D-8 Flow in LPI System D-9 Refueling Water Storage Tank Level D-10 Reactor Coolant Pump Status -VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALIFICATION 2 Yes No 2 Yes N/R 2 Yes No 2 Refer to Item A-8 2 Yes Yes 2 Refer to Item A-10 3 Yes N/R -.15-SEISMIC QUALI FI CA TI ON REDUNDANCY N/R N/R N/R N/R N/R N/R e N/R N/R N/R N/R e PAGE 13 OF~

ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY D-4 Yes Yes D-5 Yes Yes D-6 Yes Yes D-7 D-8 Yes Yes D-9 D-10 N/R Yes VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION TSC EOF LOCATION LOCATION Yes Yes Consider Note 10 -REMARKS -Category 3. Yes Yes Consider Category 3. Note 10 -See See Yes Yes Transmitter to be replaced Refer to Item A-8 Yes Yes Acceptable Refer to Item A-10 ( Yes Yes. Acceptable e e PAGE 14 OF 28 ----

-ITEM NUMBER VARIABLE D-1 l Primary System Safety Relief ' Valve Position (including PORV valves} D-12 Pressurizer Level D-13 Pressurizer Heater Status D-14 Quench Tank Level

• 0~15 Quench Tank Temperature D-16 Quench Tank Pressure D-17 Steam Generator Level D-18 Steam Generator Pressure . D-19 Safety-Relief Valve Positions D-20

• Ma in Feedwater Flow VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALIFICATION 2 Refer to Item A-11 l No Yes 2 No No 3 Yes N/R 3 No N/R 3 Yes N/R l Yes No l Refer to Item A-2 2 No No 3 Yes N/R

• r SEISMIC QUALIFICATION REDUNDANCY Yes No e N/R N/R N/R N/R N/R N/R N/R N/R No Yes -N/R N/R N/R N/R PAGE 15 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY D-11 D-12 Yes Yes D-13 Yes Yes D-14 N/R Yes D-15 N/R Yes D-16 N/R Yes D-17 Yes Yes D-18 D-19 No No D-20 N/R Yes VIRGINIA ELECTRIC ANU l'UWt;l{ CUM.t'AN'.i REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF REMARKS LOCATION LOCATION -Refer to Item A-11 Yes Yes Add density compensation to reduce error and expand range of transmitters to full range allowed by taps. Note 7 Yes Yes Note 5 Yes Yes Acceptable.

Existing range covers approximately 90% of tank height. I Yes Yes Note 6 Yes Yes Acceptable Yes Yes Transmitters to be replaced.

Notes 1 and 3 Refer to Item A-2 No No Install position detector and indicator Yes Yes Acceptable

' PAGE 16 OF 28 e e

. ITEM NUMBER VARIABLE D-21 Auxiliary or Emergency

' Feedwater Flow D-22 Condensate Storage Tank Level D-23 Containment Spray Flow D-24 Heat Removal by the Canta inment Fan Heat . Removal System D-25 Containment Atmosphere D-26 Containment Sump Water Temperature D-27 Makeup Flow-in D-28 Letdown Flow-Out D-29 Volume Control Tank Level -VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1. 97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALi FI CA TI ON 2 Yes Yes 1 Refer to Items A-9 2 No No 2 No No 2 No No 2 Yes No 2 Yes No 2 ,Yes No 2 No No SEISMIC QUALIFICATION REDUNDANCY N/R N/R e N/R N/R N/R N/R N/R N/R N/R N/R N/R N/R e N/R N/R N/R N/R PAGE 17 OF _1L ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY D-21 Yes Yes D-22 D-23 No No D-24 No No D-25 Yes Yes D-26 Yes Yes D-27 Yes Yes D-28 Yes Yes D-29 Yes Yes VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF LOCATION LOCATION REMARKS -Yes Yes Acceptable Refer to Item A-9 --Note 8 Yes Yes Add qualified flow transmitters and temperature elements.

Yes Yes Replace with qualified RTD and Rescale I Yes Yes Note 11 Yes Yes Replace with qualified transmitter Yes Yes Replace with qualified transmitter Yes Yes Replace with qualified transmitters; Note 12 PAGE 18 OF 28 ----e e

. ITEM NUMBER VARIABLE D-30 Component Cooling Water Temperature

' to ESF Systems D-31 Component Cooling Water Fl ow to ESF Systems D-32 High-Level Radioactive Liquid Tank Level D-33 Radioactive Gas Holdup Tank Pressure D-34 Emergency Ventilation Damper Position D-35A 4160 Emergency Bus-Availability D-35B 480 V Emergency Bus-Availability D-35C 125VDC Status D-35D . 120 VAC Vital Bus Status_ D-35E 120 VAc' Semi-Vital Bus Status VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALIFICATION 2 No No 2 No No 3 Yes N/R 3 No N/R 2 No No I 2 Yes Yes 2 No No 2 Yes Yes 2 Yes Yes 2 Yes Yes I .. SEISMIC QUALIFICATION REDUNDANCY N/R N/R N/R N/R N/R N/R e N/R N/R N/R N/R No N/R No N/R e Yes N/R Yes N/R Yes N/R PAGE 19 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY D-30 No No D-31 No Yes D-32 N/R Yes D-33 Yes Yes D-34 Yes No D-35P Yes Yes D-35E Yes Yes D-35( Yes Yes D-35[ Yes Yes D-35E Yes Yes VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF REMARKS LOCATION LOCATION Yes Yes Install temperature channel to monitor operation at the charging pump cooling system Yes Yes Install flow channel to monitor charging pump cooling system Yes Yes Acceptable Yes Yes Rescale existing instruments Yes Yes Install Limit switches I Yes Yes For items D-35A -D35 F control room displays will be available once the Multiplex systems is installed.

Yes Yes Yes Yes Yes Yes Yes Yes PAGE__!{?__OF *' , e e

. ITEM NUMBER VARIABLE D-35F Emergency Diesel Generator Watts Status E-1 Containment Area Radiation E-2 Radiation Exposure Rate (inside buildings or areas where access is required to service equipment important to safety) E-3 Containment or Purge Effluent E-4 Reactor Shields Buildings Annulus (if in design) E-5 Auxiliary Building (including any building containing primary system gases, e.g., waste gas decay tank) -E-6 Condenser Air Removal System Exhaust VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALIFICATION 2 Yes Yes l Yes Yes 3 Yes N/R 2 N/R N/R 2 N/R N/R 2 Yes Yes 2 N/R N/R SEISMIC QUALIFICATION REDUNDANCY No N/R Yes Yes N/R N/R e .I N/R N/R N/R N/R N/R N/R -N/R N/R PAGE 21 OF 28 -

ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY D-35F Yes Yes E-1 Yes Yes E-2 Yes Yes E-3 N/R N/R E-4 N/R N/R E-5 Yes Yes E-6 N/R N/R VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF . REMARKS LOCATION LOCATION -Yes Yes Yes Yes Acceptable Yes Yes Acceptable N/R N/R Delete -Effluent discharge through common plant vent N/R N/R Delete -Effluent discharges through common plant vent Yes Yes Acceptable

' N/R N/R Delete -Effluent discharges through common EJant vent ,. PAGE22._0F

--21L. . ' e e

. ITEM NUMBER VARIABLE E-7 Common Plant Vent or Multi-purpose Vent Discharging Any of Above Release ( if containment purge is included)

E-8 Vent from Steam Generator Safety Relief Valves or Atmospheric Dump Valves E-9 All Other Identified Release Points E-10 Al 1 Identified 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.

VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE Q UAL I FI CAT I ON 2 Yes Yes 2 Yes Yes None I entified 3 Yes N/R I I SEISMIC QUALi FI CATI ON REDUNDANCY N/R N/R N/R N/R e N/R N/R -PAGE 23 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY E-7 Yes Yes E-8 Yes Yes E-9 E-10 N/R Yes VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION TSC EOF LOCATION LOCATION Yes Yes Acceptable Yes Yes Acceptable REMARKS -None Identified Yes Yes Acceptable I e e PAGE 24 OF 28

. ITEM NUMBER VARIABLE E-11 Airborne Radio-halogens and ' Particulates (portable sampling with onsite analysis capability)

E-12 Plant and Environs Radiation (portable instrumentation)

E-13 Plant Environs Radioactivity (portable instrumentation)

E-14 Wind Direction E-15 Wind Speed E-16 Estimation of Atmospheric Stability . VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALi FI CA TI ON 3 Yes N/R 3 No N/R 3.

• Yes N/R 3 Yes N/R 3 Yes N/R 3 Yes N/R SEISMIC Q UALI FI CA TI ON REDUNDANCY N/R N/R e N/R N/R N/R N/R N/R N/R N/R N/R N/R N/R -PAGE2 5 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY E-11 N/R For Item* Manual d< E-12 N/R are avai E-13 N/R E-14 N/R Yes E-15 N/R Yes E-16 N/R Yes V 1KG 1N iA ELEC'l'KlC AN!J 1'UW~K CUM.I:' Al'H. REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION -TSC EOF LOCATION LOCATION E-11 -E-1~, cumented re* ults able to the operator.

Yes Yes Yes Yes ( Yes Yes REMARKS -Acceptable Purchase additional portable instrumentation to cover range to 104 R/Hr (common to both units). Acceptable Acceptable Acceptable Acceptable

' PAGE26 OF 28 ----e e ITEM NUMBER VARIABLE E-17 Primary Coolant and Sump Sampling and Analysis E-18 Containment Air Sample -VIRGINIA ELECTRIC AND POWER COMPANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION ENVIRONMENTAL CATEGORY RANGE QUALIFICATION 3 Yes N/R 3 Yes N/R SEISMIC QUALIFICATION REDUNDANCY N/R N/R N/R N/R e e PAGE 27 OF 28 ITEM POWER CONTROL NUMBER SOURCE ROOM DISPLAY E-17. N/R Yes E-18 N/R Yes VIRGINIA ELECTRIC AND POWER CUM.l'ANY REG. GUIDE 1.97 VARIABLE LIST SURRY POWER STATION TSC EOF LOCATION LOCATION Yes Yes Acceptable Yes Yes Acceptable I ' REMARKS e -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 1 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 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 11 of the 500 11 height of the pressurizer.with only the curvature portions of the vessel not being covered. Page 2 of 4 ---32-,;~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 11 Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps.11 Vepco 1 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 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

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ITEM NO. A-1 A-2 A-3 A-6 A-7 A-8 A-9 A-10 A-11 A-12 A-13 A-14 A-15 B-1 -ATTACHMENT I UNIT l INDICATORS SURRY POWER STATION e MARK NO. MANUFACTURER LI-1474, 1484, 1494 Hagan LI-1475, 1485, 1495 LI-1476, 1486, 1496 Pl-1474, 1484, 1494 Hagan PI-1475, 1485, 1495 PI-1476, 1486, 1496 Thermocouple Indicators Honeywell FI-1414, 1415, 1416 Hagan FI-1424, 1425, 1426 Hagan FI-1434, 1435, 1436 Hagan PI-1402, 1402-1 Westinghouse FI-1940, 1943 Hagan FI-1932, 1933, 1960 Hagan FI-1961, 1962, 1963 Hagan LI-CN-100, l 01 Sigma LI-CS-l OOA , 1008 Hagan LI-CS-1 OOC, 1000 Westinghouse YI-VMSl 01 A, B Sigma I 11 . TI-1453 Hagan LI-1459, 1460, 1461 Hagan H2I-GW-104-l, 104-2 . Hagan PI-LM-lOOA, 1008 Hagan PI-LM-lOOC, 1000 NI-1-418, 428, 438 Hagan 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 *Qualified Indicators ses/11068/41 TYPE 107 107 System To Be Replaced 107 107 107 VX-252* 107 107 107 9270 107 VX-252* System to be upgraded 107 107 107 107 107 Page _l_ of 3 ITEM NO. B-9 B-12B C-2 C-11 ITEM NO. A-1 A-2 A-3 A-6 A-7 A-8 A-9 A-10 A-11 ATTACHMENT I (CONT'D> UNIT l INDICATORS SURRY POWER STATION e MARK NO. LI-1-1310, 1311, LI-1-1312, 1320, LI-1-1322, 1321 LI-RS-151A, l51B RM-CH-118, 11 9 PI-LM-lOlA, 1018 MARK NO. LI-2474, 2484, 2494 LI-2475, 2485, 2495 LI-2476, 2486, 2496 PI-2474, 2484, 2494 PI-2475, 2485, 2495 PI-2476, 2486, 2496 UNIT 2 Thermocouple Indic~tors FI-2414, 2415, 2416 FI-2424, 2425, 2426 FI-2434, 2435, 2436 PI-2402, 2402-1 FI-2940, 2943 FI-2932, 2933, 2960 FI-2961, 2962, 2963 LI-CN-200 l 01 LI-CS-200A, 1008 LI-CS-200C, lOOD YI-VMS201A, B MANUFACTURER Westinghouse Westinghouse Victoreen Westinghouse MANUFACTURER Hagan Hagan Honeywe 11 Hagan Hagan Hagan Westinghouse Hagan Hagan Hagan Sigma Hagan Westinghouse Sigma Ill. *Qualifi~d Indicators ses/ll06B/42 TYPE VX-252* VX-252* 844-18 VX-252* TYPE 107 107 System To Be Replaced 107 l 07 107 VX-252* 107 107 107 9270 107 VX-252* System to be upgraded Page _2_ of _J_

-ATTACHMENT I (CONT'D) e .. UNIT 2 INDICATORS SURRY POWER STATION 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, 1 311 , 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_ ses/11068/43

.--* 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.

Page _1_ of _6_ ses/11066/46

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 11 IEEE Std. 308-71, Criteria for Class IE Electric Systems for Nuclear Power Generating Stations.11 e. Reg. Guide l .118 -11 Periodic Testing of Electric.

Power and Protection 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.

Page _1__ of_§_ ** ses/Tl06B/47

..* 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 -11 Quality Assurance Program Requirements

<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 -11 Quality Assurance Requirements for the Installation Inspection, and Testing of Instrumentation and Electric Equipment 11 (8/72). 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. Page _3_ of __§_ -ses/H06B/48

.. -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. Page...!._

of_§_ -ses/1106B/49 411 ** e -f. 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. Page _j_ of _6_

• se-s/11068/50

• 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. Page_§_ of -se~/ll06B/5l