ML20080M847

Forwards Rev 2 to 830414 Response to Suppl 1 to NUREG-0737, Including Rept on Review of Reg Guide 1.97

ML20080M847
Person / Time
Site:	Catawba
Issue date:	09/26/1983
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8310040287
Download: ML20080M847 (91)

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e P DUKE POWER GOMPANY P.O. HOx 33180 CHAMLOTTE, N.C. 28242 IIAL II. TUCKER Tztzenown V9CE rarSIDENT (704) 373-4331

=== = r o--- September 26, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4

Subject:

Duke Power Company Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Sir:

Please find attached five copies of Revision 2 to the Duke Power Company Response to Supplement 1 to NUREG-0737 for Catawba Nuclear Station. This document was originally submitted as an enclosure to my letter of April 14, 1983.

In accordance with the previously submitted schedule for Catawba Nuclear Station, the attachment includes the Duke report on the review of Regulatory Guide 1.97 for Catawba Nuclear Station.

Instructions for inserting Revision 2 into the Catawba document are included as part of the attachment.

Very truly yours, ._,

<td k st- --

Hal B. Tucker l JSW:scs Attachments 8310040287 830926 Yg I PDR ADOCK 05000413 F PDR L

.- ~6 Mr. Harold R. Denton, Director Page Two September 26, 1983 cc: Mr. J. P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Robert Guild, Esq., Attorney-at-Law P. O. Box 12097 Charleston, South Carolina 29412 Dr. K. N. Jabbour NRC Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition 943 Henly Place Charlotte, North Carolina 28207 Palmetto Alliance 2135 1/2 Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley 7

Carolina Environmental Study Group l 854 Henley Place Charlotte, North Carolina 28207 Mr. P. K. Van Doorn NRC Resident Inspector Catawba Nuclear Station I'

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Mr. Harold R. Denton, Director Page Three September 26, 1983 bec: R. L. Brown R. O. Sharpe H. L. Davenport K. S. Canady H. R. Lowery D. W. Murdock G. D. Gilbert T. C. McMeekin C. C. Rolfe R. E. Hall B. C. Moore S. R. Frye J. W. Hampton W. H. Rasin G. B. Swindlehurst C. A. Little N. A. Rutherford R. M. Glover J. W. Cox M. R. Crews Group File GS-801.01 Group File CN-801.01

DUKE POWER COMPANY

,m CATAWBA NUCLEAR STATION

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\' i Pesponse to Supplement 1 to NUREG-0737 Document Revision Transmittal Revision No. 2 Instruction Sheet Revise Volume 1 as Described Below:

Remove Table of Contents Insert Table of Contents Page 1, Revision 1 Page 1, Revision 2 Remove Table of Contents Insert Table of Contents Page 11, Revision 1 Page 11, Revision 2 Insert Table of Contents Page 111, Revision 2 Revise Volume 2 as Described Below:

Remove Table of Contents Insert Table of Contents Page 1, Revision 1 Page 1, Revision 2 I \

\ _/ Remove Table of Contents Insert Table of Contents Page 11, Revision 1 Page 11, Revision 2 Insert Table of Contents Page 111, Revision 2 Remove Pages 5-1, 5-2, and 5-3 Insert Pages 5-1 thru 5-84, Revision 2

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TABLE OF CONTENTS O

SECTION PAGE VOLUME 1 1 INTRODUCTION 1-1 1.1 Purpose 1-1

1. 2 Scope 1-1

1. 3 Background 1-3

1. 4 Definitions 1-4 2 INTEGRATED IMPLEMENTATION PLAN AND SCHEDULE 2-1 2.1 Overview 2-1 2.2 Integrated Schedule 2-5 3 CONTROL ROOM REVIEW 3-1 3.1 Control Room Review Status (Through April 1, 1983) 3-1 3.2 Duke Power Nuclear Stations Control Room Review Plan Tab 3.2 3.3 Control Room Review Final Report Tab 3.3 3.4 Control Room Review Supplemental Report, Unit 1 Tab 3.4 VOLUME 2 4 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) 4-1 4.0 Introduction 4-1 4.1 SPDS Implementation Plan 4-1 4.2 SPDS System Description 4-6 4.3 SPDS Safety Analysis 4-13 4.4 SPDS Current Status 4-14 5 REGULATORY GUICE 1.97 5-1 5.1 Introduction 5-1

5. 2 Background 5-1 CNS i Revision 2 Y

TABLE OF CONTENTS (cont'd)

SECTION PAGE 5.3 Scope 5-2 5.4 Plan Description 5-2 5.5 Ouke Power Company Position on Accident 5-4 Monitoring Instrumentation 5.5.1 Accident Monitoring Instrumentation 5-4 5.5.1.1 Type A Variables 5-4 5.5.1.2 Type B and C Variables 5-5 5.5.1.3 Design and Qualification Criteria 5-7 5.5.1.3.1 Design and Qualification Criteria 5-7 Category 1 5.5.1.3.2 Design and Qualification Criteria 5-10 Category 2 5.5.1.3.2.1 Class 1E (QA1) Category 2 Instrumentation 5-10 5.5.1.3.2.2 Non-Class 1E (Non-QA1) Category 2 5-10 Instrumentation 5.5.1.3.2.3 All Category 2 Instrumentation 5-11 5.5.1.3.3 Design and Qualification Criteria Category 3 5-12 5.5.1.4 Additional Criteria for Categories 1 and 2 5-12 5.5.1.5 AdditionalCriteriaforAjlCategories 5-13 5.5.2 System Operation Monitoring (Type D) and 5-15 Effluent Release Monitoring (Type E)

Instrumentation 5.5.2.1 Definitions 5-15 5.5.2.2 Operator Usage 5-15 CNS ii Revision 2

3 TABLE OF CONTENTS (cont'd)

O SECTION PAGE 5.5.2.3 Design and Qualification Criteria - 5-15 Types D and E 5.6 Regulatory Guide 1.97 Comparison 5-16 6 EMERGENCY OPERATING PROCEDURE UPGRADE PROGRAM 6-1 6.1 Introduction 6-1 6.2 Plant Specific Technical Guidelines And 6-1 Emergency Procedure Development Process 6.3 Writer's Guide For Emergency And Abnormal 6-4 Procedures 6.4 Emergency Procedure Verification Program 6-5 6.5 Emergency Procedure Validation Program 6-6 6.6 Emergency Procedure Training Program 6-7 Description j 6.7 Emergency Procedure Upgrade Program Status 6-8 7 EMERGENCY RESPONSE FACILITIES 7-1 7.1 Technical Support Center 7-1 7.2 Operational Support Center 7-2 7.3 Emergency Operations Facility 7-3 i

7.4 Safety Parameter Display System 7-4 l 7.5 Nuclear Data Link 7-4 7.6 Data Acquisition and Transmission 7-4 lO CNS iii Revision 2

5. REGULATORY GUIDE 1.95, REVISION 2 - REVIEW FOR CATAWBA NUCLEAR STATION

5.1 INTRODUCTION

This Duke Power Company response addressing Regulatory Guide 1.97, Revision 2 for Catawba Nuclear Station has been formulated as an integral part of the overall company plan to respond to Nuclear Regulatory Commission Generic Letter 82-33, which transmitted Suppleiaent 1 to NUREG-0737 " Requirements for Emergency Response Capability." The overall company plan, as described in Section 2, consists of the following task areas in addition to Regulatory Guide 1.97:

- Control Room Review (CRR)

- Safety Parameter Display System (SPDS)

- Emergency Procedure (EP) upgrade

- Emergency Response Facilities These other task areas are described in detail in the appropriate section of p this response. Figure 2-1 (of Section 2) illustrates the interfaces and b^ relationships between the Regulatory Guide 1.97 Revision 2 review effort and the other task areas in the overall integrated plan.

The Technical Support Center (TSC) and Emergency Operations Facility (EOF) are described in Section 7.0 of this response and are not specifically addressed in this Regulatory Guide 1.97 section.

5.2 BACKGROUND

Duke Power Company began developing a formal review plan to address Revision 2 of Regulatory Guide 1.97 in January,1982. This plan is part of the' larger integrated plan originated to respond to Nuclear Regulatory Commission Generic Letter 82-33. The formal Regulatory Guide 1.97 Revision 2 review plan was

) established in June, 1982.

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This document contains Duke < Power'foppany's report on the' compliance of Catawba

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Nuclear Station with-NUREG 0737 Sapplement 1 which rgferences.U. S. Nuclear

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Regulatory Ccmmissian Regulatory, Guide 1.97, Revision 2 issued'in December

< l l 1980. Included in the. report are descriptions of ~the Duke Power Company .

accidentmonitoringinstrumentationpositionandadstalledcomparisontable as requested in Supplement 1 to NUSEG 0737.

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i 5.4 PLAN DESCRIPTION /

The plan for addressing Re'ghlatcry Guide 1.-97, Revision 2 for the Catawba i

Nuclear Station design consists of t.he following three phases:

• Review 4

• Assessment- ,

• Implementation

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The Review phase co'nsisted of the establishment of plant specific accident a

monitoring instrumentation requirements and a' detailed review of existing instrumentation versus these requirements. The p? ant specific accident monitoring instrumentation criteria and clarifications .are established in- a Duke- Power position statement (see Section 5.5) in additicn to Section 7.5 of the Catawba Final Safety Analysis Report (FSAR).

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The Station Emergency Procedures and Safety Parameter Display System (SPDS)

Critical Safety Functions, both of which are undergoing final development and review as part of the overall Emergency Response Capability effort, served as inputs for variable selectior., Both of these documents were derived from the p) Catawba plant specific version of the Westinghouse Owners Group Emergency 5-2 Revision 2 i'

1 Response Guidelines and associated Critical Safety Function Status Trees.

Modifications in either the Emergency Response Guidelines or the associated Critical Safety Function Status Trees will be incorporated as appropriate into the Regulatory Guide 1.97 accident monitoring instrumentation in accordance with the integratec plan for addressing Supplement 1 to NUREG 0737.

Emergency Procedures provide the lead guidance for selection of Type A variables.

The SPOS Critica! Safety Functions as derived from the Critical Safety Function Status Trees form the basis for selection of the Type B and C variables. The Type D and E variables are selected on the basis of individual plant specific system design requirements.

The station Emergency Procedures and the Safety Parameter Display System are G discussed in more detail in Sections 4.0 and 6.0 of this response.

The Review phase provided the basis for the Duke position statement on accident monitoring and a listing of variances of installed accident monitoring instrumen-tation versus the plant specific needs. These variances were reviewed by the appropriate parties as provided for in_the interfaces set up by the integrated plan described in Section 2.0, " Integrated Plan and Schedule."

The Assessment phase utilized the input generated during the Review phase and consisted of an evaluation of all identified variances in accident monitoring instruments to determine what further action was merited. Guidance from the l

NUTAC committee's June 1983 draft of Regulatory Guide 1.97 (Accident Monitoring Instrumentation) Implementation Guideline was considered in development of the

] comparison sheets. Control Room and operator interfaces were coordinated with

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-the Control Room Review as described in Section 2. The Assessment phase o

produced two primary and products, specifically, the results of the evaluation described above and this response report for submittal to the NRC.

The Implementation phase of the plan consists of designing and installing those modifications to accident monitorirg instrumentation as identified in the Assessment phase. This phase is an integrated effort to insure effective orderly implementation of all Control Room Review, SPDS and RG 1.97 modifica-tions or additions.

Duke Power Company is an active participant in the Nuclear Utility Task Action Committee on Emergency Response Capability, and. resultant NUTAC guidance has been considered and utilized in the review, assessment, and implementation phases of our review plan.

5.5 DUKE POWER COMPANY POSITION ON ACCIDENT MONITORING INSTRUMENTATION 5.5.1 Accident-Monitoring Instrumentation The criteria and requirements contained in ANSI /ANS-4.5-180, " Criteria for Accident Monitoring Functions in Light-Water Cooled Reactors," are considered by Duke Power to be generally acceptable for providing instrumentation to monitor variables for accident conditions subject to the clarifications defined below. -

5. 5.1.1 TYPE A Variables Type A variables are defined as those variables which are monitored to provide the' primary information required to permit the Control Room operator to take O

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T specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accidents. Primary information is defined as that which is essential for the direct accomplishment of the specified safety functions; it does not include those variables associated with contingency actions which may also be identified in written procedures.

The following variables are those determined to be Type A for Catawba Nuclear Station, as defined above:

• Reactor Coolant System Pressure

• Core Exit Temperature

• Reactor Coolant System Hot Leg Water Temperature

• Reactor Coolant System Cold Leg Water Temperature

• Pressurizer Level

• Degrees of Subcooling

• Steam Generator Narrow Range Level

• Steam Line Pressure

• Refueling Water Storage Tank Level

5. 5.1. 2 TYPE B and C Variables Type B and C variable selection is based on the SPDS Critical Safety Functions. The SPDS is provided as an aid to the Control Room operating crew in monitoring the status of the Critical Safety Functions. The <

Critical Safety Functions monitored are those defined in the Westinghouse Owners Group Critical Safety Function Status Trees. The SPDS provides continuous status updated at regular intervals of the Critical Safety Functions as defined in the Emergency Response Guidelines (ERG).

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l Since these Critical Safety Functions constitute the basis of the Catawba  ;

q SPDS and the emergency operating procedures, it is Duke Power's position that j they should also be identified as the plant safety functions for accident monitoring (i.e., the basis for Type B & C variable selection).

Using the SPOS Critical Safety Functions as the basis for defining the accident monitoring instrumentaticn incorporatas the concept of monitoring the multiple barriers to the release of radioactive material. The Critical Safety Functions monitored are those which assure the integrity of these barriers.

The Status Tree provides an explicit, systematic mechanism for organizing the plant data required to evaluate a Critical Safety Function. The prioritization of the Critical Safety Functions is consistent with the cor. cept of multiple barriers to radiation release.

O V The Critical Safety Functions are:

• Subcriticality The subcriticality status tree monitors the reactor core to assure that it is maintained in a subcritical condition following a successful reactor trip.

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• Core Cooling The core cooling status tree monitors those variables necessary to evaluate the status of fuel clad heat removal.

• Reactor Coolant System Integrity The Reactor Coolant System integrity status tree monitors the pressure-temperature relationship of the Reactor Coolant System with respect to various regions of the pressure-temperature curves.

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• Heat Sink The heat sink status tree monitors the ability to transfer energy from the reactor coolant to an ultimate heat sink.

• Containment The containment status tree monitors those variables which would indicate a threat to containment integrity or other undesirable conditions within contain-ment.

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• Inventory The inventory status tree monitors for indict:tions of off-normal quantities of reactor coolant in the primary system.

5.5.1.3 Design and Qualification Criteria Design and qualification criteria used by Duke Power Company for plant instrumen-tation are provided below. The category designations are provided for reference to the Regulatory Guide 1.97 (Revision 2) document.

5.5.1.3.1 Design and Qualification Criteria - Category 1 Accident monitoring instrumentation which comprise this design and qualification category are considered by Duke Power to be Nuclear Safety Related and thus are classified as Quality Assurance Condition 1 (QA1).

a. QA1 instrumentation is environmentally qualified in accordance with IEEE 323-1971 as described in the FSAR Section 3.11 and in the Duke Power Company NUREG 0588 submittal. Seismic qualification is in accordance with IEEE 344-1971 as described in the FSAR Section 3.10. Instrumentation is qualified to read within the required accuracy following, but not necessarily during a safe shutdown earthquake.

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Most of the 0A1 instrumentation loops are provided as part of the Process n 5 Control System (PCS) Protection Cabinets. These cabinets are supplied as (Q:v' nuclear safety related equipment. Each qualified instrument loop has output isolation devices which provide signals to a control board display and/or a strip chart recorder, and the plant operator-aid computer. The location of the output isolation device is such that it is accessible for maintenance during accident conditions.

b. No single failure within either the accident monitoring instrumentation, '

its auxiliary supporting features, or its power sources, concurrent with the failures that are a condition or result of a specific accident, will prevent the operators from being presented the information necessary to determine the safety status of the plant and to bring the plant to and maintain it in a safe condition following that accident. Where failure of one accident-monitoring p channel results in information ambiguity (i.e., the redundant displays disagree) that could lecd operators to defeat or fail to accomplish a required safety function, additional information is provided to allow the operators to deduce the actual conditions in the plant. This is accomplished by providing additional independent channels of information of the same variable (an identical channel) or by providing an independent channel to monitor a different variable that bears a known relationship to the multiple channels (a diverse channel).

l The information provided to the operator to eliminate ambiguity between redundant I

channels is needed only during a failure of one of the instrument loops.

(- Therefore, it is considered acceptable to use installed instrumentation of equal i

design and qualification category, installed instrumentation of a lesser design l and qualification category, temporary or portable instrumentation, or sampling i

to allow the operators to deduce the actual conditions in the plant. Redundant

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QA1 channels are electrically' independent and physically separated from each

/ other per the Catawba Final Safety Analysis Report Paragraphs 7.5.3.3.3, 7.5.3.3.7, and 7.5.3.3.8.

At least one channel of QA1 instrumentation is displayed on a direct-indicating or recording device, (Note: Within each redundant division of a safety system, redundant monitoring channels are not needed.)

c. The instrumentation is energized from Class 1E Power sources (as described in Chapter 8 of the FSAR) as provided in Regulatory Guide 1.32,

" Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants,"

and are backed by batteries where momentary interruption is not tolerable.

d. The instrumentation channel will be available prior to an accident except as provided in Paragraph 4.11, " Exception," as defined in IEEE Standard 279-1971 or as specified in Technical Specifications.

U e. The following documents pertaining to quality assurance are applicable:

• Duke 1 Duke Power Company Topical Report, " Quality Assurance Program"

• Catawba Chapter 17, " Quality Assurance" Nuclear Station Final Safety Analysis Report l

l f. Continuous indication display is provided. Where two or more instruments are needed to cover a particular range, overlapping of instrument span is provided.

g. Recording of instrumentation readout information is provided for at least one of the redundant channels. Where direct and immediate trend or I transient information is essential for operator information or action, the i

recording is continuously available on dedicated recorders. Otherwise, it O

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may be continuously updated, stored in computer memory, and displayed on demand. Intermittent displays such as data loggers and scanning recorders may be used if no significant transient response information is likely to be lost by such devices.

5.5.1.3.2 Design and Qualification Criteria - Category 2 5.5.1.3.2.1 Class 1E (QA1) Category 2 Instrumentation For instrumentation loops that are installed as Class 1E (QA1), environmental qualification is provided per the methodology described in the Catawba NUREG 0588 submittal and the FSAR Section 3.11. Seismic qualification is in accordance with IEEE 344-1971 as described in Section 3.10 of the Catawba FSAR. Quality Assurance in the design, procurement, and installation of these QA Condition 1 Instrumentation Systems is provided as described in the Duke Power Company n Topical Report " Duke 1" and FSAR Chapter 17. These instruments are powered U from Class IE Power sources (as described in Chapter 8 of the FSAR) and are backed by batteries where a momentary power' interruption is not tolerable.

5.5.1.3.2.2 Non-Class 1E (Non-QA1) Category 2 Instrumentation For instrumentation loops of lesser importance which are not Class 1E (QA1),

appropriate qualification is provided. The intent is to provide reasonable assurance that this non-Class 1E instrumentation can be expected to be operable for accident monitoring and analysis. It is Duke's position that such assurance j does not need to be as rigorous as for Category 1 and, thus, practical approaches employing equipment design ratings, similarity to qualified equipment, or i other engineering judgments are acceptable. Full harsh environment withstand rating may not be provided where an engineering evaluation determines that j

other environmentally qualified diverse or alternate instrumentation provides U

an adequate backup reading. Additionally, Category 2 instrumentation which is 5-10 Revision 2

of primary use during one phase of an accident need not be qualified for all phases of the event. For example, an instrument of primary importance prior to attaining the recirculation mode need not be demonstrated to withstand post-recirculation radiation.

For non-Class 1E (non-QA1) Category 2 instrumentation, seismic qualification is not required unless seismic induced failure of the instrumentation would unacceptably degrade a safety system.

These instrumentation systems are designed, procured, and installed per Duke Power Company standard practices. Duke Power considers that this is adequate to assure the quality of the subject instrumentation.

Isolation devices are provided to interface between Class 1E and non-Class 1E portions of any of the subject instrumentation loops.

The instrumentation is energized from a high-reliability power source, not necessarily Class 1E Power, and is backed by batteries where momentary interrup-tion is not tolerable.

5.5.1.3.2.3 All Category 2 Instrumentation For both Class 1E and non-Class 1E Category 2 instrumentation:

The out-of-service interval should be based on normal Technical Specification requirements for the system it serves where applicable or where specified by other requirements.

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The instrumentation signal may be displayed on an individual instrument or it O

O may be processed for display on demand by a CRT or by other appropriate means.

The method of display may be by dial, digital, CRT, or stripchart recorder indication. Effluent radioactivity monitors and meteorology monitors will be recorded. Where direct and immediate trend or transient information is essential for operator information or action, the recording is continuously available on dedicated recorders. Otherwise, it may be continuously updated, stored in computer memory, and displayed on demand.

5.5.1.3.3 Design and Qualification Criteria - Category 3 These instruments do not play a key role in the management of an accident but they do add depth to the Category 1 and 2 instrumentation to the extent that p they remain operable. The instrumentation is of high quality commerical 1

grade and is selected to withstand the normal power plant service environment.

The method of display may be by dial, digital, CRT, or stripchart recorder indication.

Effluent radioactivity monitors and meteorology monitors will be recorded.

Where direct and immediate trend or transient information is essential for operator information or action, the recording is continuously available on dedicated recorders. Otherwise, it may be continuously updated, stored in l

l computer memory, and displayed on demand.

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5. 5.1. 4 Additional Cr#teria for Categories 1 and 2 In addition te the criteria of Duke Position 5.5.1.3, the following criteria i

j apply to Categories 1 and 2:

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• For Nuclear safety related (Class IE) signals which are transmitted to non-safety related (non-Class 1E) equipment, isolation devices are utilized.

• Dedicated control board displays for the instruments designated as Types A, B, and C, Category 1 or 2 and qualified for use throughout all phases of an accident will be specifically identified on the control panels so that the operator can discern that they are available for use under accident conditions.

5.5.1.5 Additional Criteria for All Categories In addition to the above criteria, the following criteria apply to all instruments identified in this document:

• Servicing, testing, and calibration programs are specified to maintain m the capability of the monitoring instrumentation. For those instruments where the required interval between tests will be less than the normal time interval between generating station shutdowns, the capabilit.y for testing during power operation is provided.

• Whenever means for removing channels from service are included in the i

I design, the design facilitates administrative control of the access to such removal means.

• The design facilitates administrative control of the access to all setpoint adjustments, module calibration adjustments, and test points.

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• The monitoring instrumentation design minimizes the development of (9

V conditions that would cause meters, annunciators, recorders, alarms, etc., to give anomalous indications which are potentially confusing to the operator. Human factors guidelines are used in determining type '

and location of displays. The Duke Control Room Review Team will make recommendations as to the type and location of displays for added instrumentation.

• To the extent practicable, the instrumentation is designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.

• To the extent practicable, monitoring instrumentation inputs are from

, sensors that directly measure the desired variables.

• To tie extent practicable, the same instruments are used for accident monitoring as are used for the normal operations of the plant to enable the operators to use, auring accident situations, instruments with which they are most familiar. However, where the required range of monitoring instrumentation results in a loss of necessary sensitivity in the normal operating range, separate instruments are used.

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• Periodic checking, testing, calibration, and calibration verification are in accordance with the applicable portions of the Catawba FSAR Chapter 7, " Instrumentation and Controls."

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5.5.2- System Operation Monitoring (Type 0) and Effluent Release Monitoring A

(Type E) Instrumentation

5. 5. 2.1 Definitions Typo D: those variables that provide information to indicate the operation of individual safety systems.

Type E: those variables to be monitored as required for use in determining the 4

magnitude of the release of radioactive materials and in continually assessing such releases.

5.5.2.2 Operator Usage The plant design has included variables and information display channels required to enable the Control Room operating personnel to:

• Ascertain the operating status of each individual safety system to the extent necessary to determine if each system is operating or can be placed in operation to help mitigate the consequences of an accident.

• Monitor the effluent discharge paths to ascertain if there have been significant releases (planned or unplanned) of radioactive materials and to continually assess such releases.

• Obtain required information through a backup or diagnosis channel where a single channel may be likely to give ambiguous indication.

5.5.2.3 Design and Qualification Criteria - Types D and E The design and qualification criteria for safety system operation monitoring (Type 0) and effluent release monitoring (Type E) instrumentation are provided in Paragraphs 5.5.1.3, 5.5.1.4, and 5.5.1.5 of this guide.

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5.6' REGULATORY GUIDE 1.97 COMPARIS0N

-l The following accident-monitoring variable sheets are the r2sult of the c Assessment phase of the Regulatory Guids 1.97 Revision 2 review plan.

. Each sheet contains information regarding the comparison of the particular variable with the recommendations of the Regulatory Guide. . Instrument ranges, d? sign, environmental qualification, type of display, and position statements 4

are provided for each variable named in Table 2, "PWR Variables," of Regulatory Guide 1.97 Revision 2. An implementation schedule is also provided if any

- modifications are planned.

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CATAWBA NUCLEAR STATION

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CATAWBA NUc' CAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW FORMAT FOR COMPARISON TABLE Variable: This is the variable as listed in Table 2 of RG 1.97, Rev. 2. (The Duke variable name may be shown parenthetically.)

B-16, This gives the Table 2 of RG 1.97, Rev. 2 variable C-15 type and sequence number. Type A variables are those listed in Section 5.5.1.1 of this document.

Range: This is the Table 2 of RG 1.97, Rev. 2 listed range.

Category: This is the Table 2 of RG 1.97, Rev. 2 listed category.

Existing Design: This is a description of the present Catawba design O Compliance:

for the instrumentation.

This is a statement concerning compliance to Duke's interpretation of the recommendations of RG 1.97, Rev. 2.

Display: This lists the Control Room indications available to the operator.

Position: This is a statement regarding the instruments' adequacy for the intended monitoring function.

Implementation Schedule: This lists any schedule information concerning a change to the existing design.

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-1, Variable: RCS Pressure B-7, B-11, Range: 0 to 3000 psig C-4, C-9 Category: 1 Existing Design: Catawba has two redundant, QA Condition 1 channels of Wide Range RCS pressure instrumentation. Each transmitter feeds a different channel of the PCS and is powered by that channel's associated Class 1E buss. The indicated range is 0 to 3000 psig.

Redundant / diverse indication is provided by control grade RCS pressure instrumentation provided for

, the auxiliary shutdown panels and the ste.ndby ,

shutdown facility, as well as the QA Condition 1 pressurizer pressure instrumentation. Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in f3 the Catawba FSAR, Section 3.10.

("/ Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Two Control Room indicators Two channels on the computer Two channels recorded Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-2, Variable: Core Exit Temperature B-8, C-1 Range: 200 F to 2300*F Category: 1 Existing Design: The QA Condition 1 Core-Exit Thermocouple System for accident monitoring will consist of at least 20 thermocouples The primary display will be the plant computer, with a Class 1E backup display device. Inputs to the plant computer will be through qualified Class 1E isolation devices.

Power for the Class 1E portion of the system will be from Class 1E busses, and power for the non-safety portion will be a highly reliable battery

, backed control buss. Redundancy / diversity is provided by the Hot and Cold Leg RCS temperature instrumentation. Environmental qualification for the Class 1E portion will be per the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG-0588 (o'j submittal. Seismic qualification will be described in the Catawba FSAR, Section 3.10. The existing incore thermocouples will be assumed to be environmentally and seismically qualified as allowed by NUREG 0737 II.F.2 Attachment 1.

The plant computer and backup display are installed in a mild environment. Range of the system is 200 F to 2300 F.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Primary display will be the plant computer CRTs in l the Control Room. Backup display will be a Class 1E indicator in the Control Room.

Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: The qualified, in containment portion of the core exit thermocouple system will be installed prior to fuel load for each Unit. The Class 1E backup display will be added during the first refueling O shutdown of each Unit.

5-20 Revision 2

t CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-3, Variable: RCS Hot Leg Water Temperature B-5 Range: 50*F to 750*F Category: 1 Existing Design: Each of the four reactor coolant loops employ a QA Condition 1 Hot Leg Water Temperature measurement (Ts ). Two of the Tsinstruments feed into one PCS chMnnel and are powWred from the associated Class 1E buss. The other two Th instruments feed into a redundent PCS channel and are powered from the associated Class 1E buss. The indicated range is 0*F to 700*F. The environmental qualification of this instrumentation is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. The seismic qualification is described in the Catawba FSAR, Section 3.10. Redundancy / diversity is provided by monitoring T h n all four loops p along with monitoring of T on all four loops and monitoringofincoretherm6 couples.

Compliance: The existing design does not comply with the recommendation of RG 1.97, Rev. 2 because the range does not conform to RG 1.97, Rev. 2 range of 50 F to 750*F.

Display: Two Control Room indicators Four channels on the computer

, Four channels recorded Position: The installed instrumentation is adequate for the

, intended monitoring function. No range change is t

required as the installed range is adequate for a i Westinghouse NSSS System. Also note, the present j range meets the recommendation of RG 1.97, Rev. 3.

Implementation Schedule: Not Applicable.

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V 5-21 Revision 2 l

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CATAWBA NUCLEAR STATION

REGULATORY GUIDE 1.97, REV. 2 REVIEW A-4, Variable: RCS Cold Leg Water Temperature B-4, B-6 Range: 50*F to 750*F Category: 1 Existing Design: Each of the four reactor coolant loops employ a QA Condition 1 Cold Leg Water Temperature measurement (T All four T 's feed into the same qualified chEn)n.

el of the PCS and are powered from the associated Class 1E buss. The indicated range is 0 F to 700*F.

Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Additional redundancy / diversity is provided by the Hot Leg Water Temperature (T s ) instruments, the incore thermocouples, and stWam pressure indication.

,-~ Compliance: The existing design is not in full compliance with

/ RG 1.97, Rev. 2 in the following areas: 1) the instrumetation is not totally redundant, and 2) the range does not conform to RG 1.97, Rev. 2 recommenda-tions.

Display: Two Control Room indicators Four channels on the computer Four channels recorded Position: Redundancy / diversity is provided by the Hot Leg RTDs, the incore thermocouples and steam pressure l instrumentation. No range change is required as l the installed range is adequate for Westinghouse NSSS Systems. Also note, the present range meets L

the recommendation of RG 1.97, Rev. 3. Therefore, Duke considers the installed instrumentation adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

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'J 5-22 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-5, Variable: Pressurizer Level 0-11 Range: Bottom to Top Category: 1 Existing Design: This station has three redundant, QA Condition 1 channels of pressurizer level instrumentation.

Each transmitter feeds a different channel of the PCS and is powered from that channel's associated Class IE buss. The indicated range is 0% to 100%

corresponding to an approximate volume of 5% to 95%. Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.10 and the NUREG 0588 submittal. Seismic qualification described in the Catawba FSAR, Section 3.10.

Compliance: The range of the instrumentation is slightly less than the recommendation of RG 1.97, Rev. 2.

Display: Three Control Rcom indicators (one per channel)

Three channels on the computer Two channels recorded Position: The installed range of the instrumentation is consistent with Westinghouse NSSS requirements and Duke considers this instrumentation to be adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

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U 5-23 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW i

A-6, Variable: Degrees of Subcooling i B-10 Range: 200'T Subcooling to 35'F Superheat Category: 2 Existing Design: This variable is a computer calculated value using various inputs from the Primary System. A graphic display over the required range gives the operator a representation of primary system conditions compared to various curves of importance (saturation, NDT, etc.). The computer is powered by highly reliable battery backed control power. The computer processing ano CRT display are located in a mild

environment. Primary inputs to this graphic display are provided from QA Condition 1 instruments which have been isolated for input to the computer.

Additional inputs of lesser qualification are used, when available and within valid ranges, to provide additional accuracy. A procedure to manually calculate subcooling margin, using QA Condition 1 instruments for information, exists as a backup to the graphic display.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Se'ction 5.5.

Display: Control Room - Computer graphic on demand.

i

' Position: Due to the mild environment maintained in the Computer Room, the projected high availability of the computer and the backup procedure to calculate l this variable, Duke Power considers that the l installed instrumentation is adequate for the intended monitoring function.

l Implementation Schedule: Not Applicable.

l 5-24 Revision 2 L.

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW

A-7 Variable

Steam Generator Narrow Range Level Range: Plant Specific Category: 1 Existing Design: The station has four redundaat, QA Condition 1 channels of Stenm Generator Narrow Range Level per Steam Generator. Instrumentation is powered by Class 1E busses. The indicated range is 0 to 100% corresponding to 333 inches above the tece-sheet (438 inches above for Unit 2) to the separators (or, approximately 60 to 100% of the wide range scale for Unit 1, 77 to 100% for Unit 2). The taps on the Unit 2 steam generator are not the same as Unit 1 because the Unit 2 steam generator is a different model and operates with a constant level program as opposed to a programmed level based on reactor power.

Environmental qualification is described in the 4

Catawba Nuclear Station FSAR, Section 3.11 and the I

NUREG 0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: All channels are indicated in the Control Room (16 indicators)

All channels on the computer (16 points)

Four channels (of 8 selectable channels) recorded Position: The installed instrumentation is adequate for the intended monitoring function, implementation Schedule: Not Applicable.

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'g1 5-25 Revision 2 t

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-8, Variable: Steam Line Pressure 0-17 Range: Atmospheric pressure to 20% above lowest safety valve setting.

Category: 1 Existing Design: Each steam generator has three redundant, QA Condition 1 channels of staat generator pressure instrumentation. Each transmitter feeds a different channel of the PCS and is powered from that channel's associated Class 1E buss. The indicated range is 0 to 1300 psig corresponding to 10% above the lowest safety valve setting and 6% above the highest safety valve setting. The instrumentation is located in a mild environment. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: The range is not in compliance with the recommenda-tion of RG 1.97 Rev. 2.

Display: Per Steam Generator; Three Control Room indicators (one per channel)

Three channels on the computer One channel recorded Position: Maximum system pressure during the worst postulated loss of heat sink accident is 1304 psig. Thus the range of the installed . instrumentation is adequate for the Catawba design and Duke considers this instrumentation to be adequate for the intended monitorir.g function.

Implementation Schedule: Not Applicable.

O 4

h 5-26 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-9, Variable: Refueling Water Storage Tank Level 0-8 Range: Top to Bottom Category: 1 Existing Design: The instrumentation far this variable provides continuous display of refueling water storage tank level. Fcur separate, QA Condition 1 channels provida redundant indication. The indicated range

, is 0 to 100% corresponding to 20 inches above the The four tank baseplate to the overflow line.

independent loops are powered from Class 1E busses.

The instruments are located in a mild environment.

Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

O- Display: Four Control Room indicators Four channels on the computer Two channels recorded Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

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5-27 Revision 2 l

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW B-1 Variable: Neutron Flux Range: 10-8% to 100% Full Power Category: 1 Existing Design: Catawba has two redundant, QA Condition 1 channels of neutron flux for bota the source and intermediate ranges. Four redundant, QA Condition 1 chsanels of neutron flux exist for the power rarge. The

. indicated ranges are; 100 to 108 counts per second, source range; 10- " to 10-8 amps, intermediate range; O to 120%, power range. The instrumentation is powered from Class 1E busses. The equipment is designed for the normal containment environment for the safety function of overpower reactor trip. The instrumentation is not environmentally qualified for post accident operation. Seismic qualification for the power range instrumentation only is described in Catawba FSAR, Section 3.10. The other instrumen-tation is not seismically qualified.

Compliance: The instrumentation is not in total compliance with the RG 1.97, Rev. 2 recommendations for environmental or seismic qualification.

Display: Eight Control Room indicatars (Two source, Two intermediate, Four power)

Eight channels on the computer Eight channels recorded i Position: Two new, redundant, QA Condition 1 channels of full range neutron flux instrumentation will be added for post accident monitoring. The indicated range of the new instruments is to be 10-8% to 100% full power. The instrumentation will be powered from Class 1E busses. Environmental qualification will be described in the Catawba FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification will be described in the Catawba FSAR, Section 3.10.

< This instrumentation will comply with Duke's interpreta-tion of RG 1.97, Rev. 2 as clarified in Section 5.5.

Implementation The new neutron flux instrumentation is to be Schedule: installed for Unit 1 by the end of the second i refueling outage. Installation of the equipment-for Unit 2 will be by the end of the first refueling outage.

5-28 Revision 2

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() CATAWBA NUCLEAR STATION REGULATORY GUIDE-1.97, REV. 2 REVIEW 8-2 Variable: Control Rod Position Range: Full in or not full in

! Category: 3 Existing Design: Each control rod's positien is indicated on a digitial display. The indicated range is Full In to Full Out in 42 increments.

Compliance: This instrumentation is in compliance with Duke's

,- interpretation of RG 1.97, Rev. 2 as clarified in l

Section 5.5.

Display

A Control Room digital display indicating all control rods One multiplexed computer point 1

Position: The installed instrumentation is adequate for the intended monitoring function.

)

Implementation 4

- Schedule: Not Applicable.

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5-29 Revision 2

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CATAWBA NUCLEA,R STATION REGULATORY GUIDE 1.97, REV. 2 REVIEli B-3 Variable: RCS Soluble Boron Concentration Range: 0 to 6000 ppm Category: .3 Existing Design: This instrumentation has dual indication with ranges of 0 to 1250 ppm and 0 to 5000 ppm.

Compliance: The range is not in total compliance with the recommendations of RG 1.97, Rev. 2.

Display: Dual range on a Control Room recorder One computer point Position: The range of the installed instrumentation is adequate for anticipated concentrations of boron, with sampling and analysis available to provide backup information.

Inplementation Schedule: Not Applicable.

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, 5-30 ,, Revision 2

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) CATAWBA NUCLEAR STATION )

REGULATORY GUIDE 1.97, REV. 2 REVIEW B-9 : Variable: Coolant Level in Reactor .

Range: Core bottom to vessel top Category: 1-Existing Design: This system consists of two redundant QA Condition 1 channels powered ~from Class 1E busses. Each

, channel consists of 3 dp transmitters and a micro- i processor to calculate true vessel level or relative void content of the primary coolant. Instrument

taps will be located at the head vent, hot legs and-the seal table for narrow and wide range level transmitters. RTDs on the impulse lines for these transmitters provide data to the microprocessor to compensate'for temperature variations between these impulse lines in containment. This instrumentation 4

will be used to detect the presence of a gas bubble or void in the reactor vessel, detect the approach to inadequate core cooling (ICC) and indicate void

' O formation in the RCS during forced flow conditions.

~

Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.11 and the i NUREG~0588 submittal. Seismic qualification'is described in the Catawba FSAR, Section 3.10.

Diversity-is provided by the incore thermocouples.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified.in Section 5.5.

Display: Three Control Room indicators per channel:

• Upper head level (64 to 120%)

• Narrow range level'(0 to 70%)

• Wide range level (0 to 120%)

Two channels on the computer One channel recorded l' Position: The installed instrumentation is adequate for the i

intended monitoring function.

Implementation

!' , Schedule: Not Applicable.

d 5-31 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW B-12, Variable: Containment Sump Water Level Narrow Range C-6 Range: Narrow Range Level Category: 2 Existing Design: Four instruments monitor the containment sump water level from 0 to 18 inches, corresponding to approxi-mately 1 to 19 inches depth in the sump. The instrumentation is powered from a highly reliable battery backed control buss. Qualified backup indication is provided by the Wide Range Sump Level Instrumentation.

Compliance: This instrumentation is not in compliance with the RG 1.97, Rev. 2 recommendations for environmental qualification.

Display: Two indicators in the Control Room

, Two computer points Position: Instrumentation is adequate for the intended monitoring function. The wide range sump level instruments provide backup for this function, and therefore full environmental qualification of narrow range level is not necessary.

Implementation Schedule: Not Applicable.

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'w 5-32 Revision 2

l CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW B-12, Variable: Containment Sump Water Level C-6 Range: Wide Range (bottom of containment to 600,000 gal.

level)

Category: 1 Existing Design: Two redundant, QA Condition 1 level transmitters measure containment sump water level from six inches above the bottom to more than seven feet above the 600,000 gal. level. The indicated range is 0 to 20 feet. Redundancy / diversity is provided by the Refueling Water Storage Tank Level instrumen-tation and the narrow range. sump level instrumentation.

The instruments are powered from Class 1E busses.

Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3,11 and the NUREG 0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Two Control Room indicators Two channels on the computer

, One channel recorded Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

k 5-33 Revision 2

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(j CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW B-13, Variable: Containment Pressure 8-15, C-5, Range: -5 to 60 psig C-11 Category: 1 Existing Design: This station has two sets of instrumentation for monitoring containment pressure. One set consists of four redundant, QA Condition 1 channels of instrumentation. The equipment is powered from Class 1E busses. Indicated range is -5 to 5 psig.

The other set of instrumentation consists of two redundant, QA Condition 1 channels. This equipment is also powered from Class 1E busses. Indicated range is -5 to 60 psig. For both sets of instrumen-tation, environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

(j Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: -5 to 5 psig indication, Four Control Room indicators Three channels on the computer Two channels recorded

-5 to 60 psig indication, Two Control Room indicators Two channels on the computer Two channels recorded Position: The installed instrumentation is adequate for the intended monitoring function.

l Implementation

! Schedule: Not Applicable.

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5-34 Revision 2

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW B-14 Variable: Containment Isolation Valve Position Range: Closed - Not Closed Category: 1 Existing Design: All containment isolation valves are provided sith control switches on the main control boards.

Actual valve position is provided by QA Connition 1 limit switches on the valves which operate both Closed-Not Closed, and Open-Not Open control switch indicating lights. These valves and their control switch indicating lights are powered from Class 1E busses. Additional indications are provided on monitor lights and by the computer. Redundancy is not necessary on a per valve basis since redundant containment isolation valves are provided. Environ-mental qualification of the limit switches is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic O.

qualification of the limit switches is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Control Room control switch indicating lights Monitor lights Computer points Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

C) 5-35 Revision 2

-[qj CATAWBA NUCLEAR STATION v

REGULATORY GUIDE 1.97, REV. 2 REVIEW C-2 Variable: Radiation Level in Primary Coolant Range: 1/2 Tech spec limit to 100 times te-5 spec limit.

Category: 1 Existing Design: Catawba has one channel of primary coolant radiation level instrumentation. This channel is powered from a highly reliable battery backed buss. The indicated range is 101 to 107 counts per minute corresponding to 10-2 to 103 pCi/ml Ba-133.

Compliance: This monitor was not installed as a Category 1 (QA Condition 1) instrument. RG 1.97, Rev. 2 range is not met. Refer to the Duke position below.

Display: One Control Room indicator One channel recorded l

Position: This monitor was not installed to quantify accident O,' conditions and cannot be assured flow following an accident. Information for this variable is obtained by sampling and analysis which is considered .

adequate for the intended monitoring function.

( Implementation Schedule: Not Applicable.

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ud l 5-36 Revision 2

(g CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW C-3, Variable: Analysis of Primary Coolant

E-18, Accident Sampling Capability, Primary Coolant E-19 and Sump, Containment Air

! Range: 10 pCi/gm to 10 Ci/gm or TID 14844 source term in

coolant volume Grab Sample Category

3 l Existing Design: The existing design of the sampling system for the primary coolant, the containment sump (sample taken i from RHR pump discharge) and containment air allows samples to be taken for laboratory analysis, i Capabilities for making the recommended measurements are provided. Information concerning the laboratory equipment available for radiological analysis is contained in the Catawba FSAR, Section 12.5.2.

Additional information concerning this parameter is (3

(,/

in the Catawba FSAR, Requests for Additional Information, question 471.5.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Not Applicable.

Position: Available equipment is adequate for the intended analyses.

Implementation Schedule: Not Applicable.

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5-37 Revision 2

0 Q CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW C-7, Variable: Containment Area Radiation - High Range E-1 Range: 1 to 107 R/hr Category: 1 Existing Design: Catawba has two redundant QA Condition 1 channels of containment high range radiation instrumentation.

Each channel is powered from a Class 1E Buss. The indicated range is 1 to los R/hr. Diversity is provided by portable instrumentation or sampling and analysis. Environmental qualification is described in the Catawba Nuclear Station FSAR, 4

Section 3.11 and the NUREG 0588 Submittal.

Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: Duke considers this instrumentation to be in compliance with the recommendations of RG 1.97, O Rev. 2 as clarified in Section 5.5.

V Display: Two Control Room indicators (one per channel)

Two channels on the computer One channel recorded Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

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O 5-38 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW C-8, Variable: Condenser Air Ejector Effluent Radioactivity E-6, Containment Effluent Radioactivity C-12, Effluent Radioactivity (from buildings in contact C-14, with the containment)

E-3, Containment Purge Effluent Radioactivity E-4, Annulus Effluent Radioactivity E-5, Auxiliary Building Effluent Radioactivity E-9 Other Identified Release Point Effluent Radioactivity Range: Various - from 10-8 to 10-2 pCi/cc to 10-6 to 105 pCi/cc Category: 2 Existing Design: Airborne process radiation monitors exist for monitoring ventilation exhausts and the condenser air ejector exhaust (see the Catawba FSAR, Section 11.5 and Table 11.5.1-2). However, in accordance with RG 1.97. Rev. 2 these monitors are not required

' /G for accident monitoring due to the fact that

(/ ventilation systems and the condenser air ejector exhaust to the common unit vent (see variable sheet E-7 on the unit vent radiation monitor).

i Compliance: Not Applicable.

Display: Not Applicable.

Position: Individual radiation monitors are not needed for compliance to the recommendations of RG 1.97, Rev.

2 due to effluents exhausting to the common unit vent.

Implementation Schedule: Not Applicable.

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5-39 Revision 2

( ) CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW C-10 Variable: Containment Hydrogen Concentration Range: 0 to 30% Hydrogen Category: 1 Existing Design: Two redundant channels of QA Condition 1 instrumantation monitor containment hydrogen concentration. The indicated range is from 0 to 30% concentration.

Both channels are powered from Class 1E busses.

These instruments are installed in a mild environment.

Seismic qualification is described in Catawba FSAR, Section 3.10. Diversity and backup is provided by manual sampling capabilities.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display:

Two Control Room indicators

( ,, Two channels recorded Two computer points Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

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U 5-40 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW C-13,. Variable: Area Radiation E-2 Range: 10-1 R/hr to 104 R/hr Category: 2 Existing Design: Catawba has an extensive Area Radiation Monitoring System installed for personnel protection. Channel detector locations were selected based on areas normally having free access and low radiation dose rates with 4 the potential of becoming high radiation areas. Range selections were based on normal background radiation levels to allow reasonable monitoring and alarm settings for keeping personnel exposures ALARA. All of these channels, with the exception of the monitors adjacent to the Reactor Coolant filters, have an indicated range of 10 1 to 104 mR/hr. The indicated range _of the Reactor Coolant filter area monitors is 10 1 to 104 R/hr.

Redundant indication is provided by portable instrumenta-tion. The channels are powered from a highly reliable O battery backed control buss. The instrumentation is rated to withstand the temperatures for normal and accident conditions. However, maximum radiation dose withstand information is not presently available for the detectors.

See the Catawba FSAR, Section 12.3 for additional infor-mation concerning the Area Radiation Monitoring System.

Compliance: The range of most of the instrumentation, the environ-mental qualification and the absence of recording is not in compliance with the recommendations of RG 1.97, Rev. 2.

Display: One Control Room indicator per channel. ,

j Position: The installed range of the instrumentation is l preferred for the intended function of personnel protection. The functions of detection of releases, release assessment and surveillance are performed through Health Physics Procedures with supplemental information provided by the effluent process Radiation

, Monitoring System. The qualification is within the L guidance provided for Category 3 instrumentation which Duke considers adequate for the intended monitoring function. Also note, this is in compliance with the

! recommendations of R.G. 1.97 Rev 3. Recording is not l required for the intended monitoring function.

Implementation Schedule: Not Applicable.

5-41 Revision 2

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V CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-1, Variable: Flow in Low Pressure Injecticn System (RHR System Flow)

D-7 Range: 0 to 110% Design Flow Category: 2 Existing Design: The existing design provides a separate display for each of the two RHR trains. The power is provided by highly reliable battery backed busses. Indicated range is 0 to 4500 GPM with a design flow of 3000 GPM. This instrumentation is installed.in a mild environment.

l Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Two Control Room indicators Two channels on the computer Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

L 5-42 Revision 2

4 CATAW8A NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-2 Variable: RHR Heat Exchanger Outlet Temperature

>- Range: 32*F to 350*F

+'

. Category: 2 Existing Design: Each train of the Catawba Residual Heat Removal System contains instrumentation to monitor RHR 4 . return temperature. The range for this instrumen-

[ tation is 50*F to 400*F and the power supply is a highly reliable battery backed control buss. .The

, RHR instrumentation is located in a mild temperature environment but is subject to post accident radiation.

Compliance: Documentation is'not available to verify the instrumentation will withstand the anticipated maximum post accident recirculation radiation dose i-for its location. The Duke range is 50*F - 400*F, whereas the recommended range is 32*F - 350*F.

l Display: Two channels recorded in the Control Room Two channels on the computer i Position: The Duke range for this instrumentation is suited to the operating and accident temperature' expected in the Residual Heat Removal System and is therefore

• considered, acceptable. Radiation withstand information is being researched for this instrumentation. If the instrument is not found to be rated to withstand the post accident recirculation phase radiation, it will be replaced with one having this radiation withstand capability.

Implementation Schedule: If it is determined that a replacement is appropriate it will be performed at the first refueling outage.

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5-43 Revision 2

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fv) CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-3 Variable: Accumulator Tank Pressure (Cold Leg Accumulator)

Range: 0 to 750 psig Category: 2 Existing Design: Catawba has two channels of accumulator tank pressure instrumentation on each of four accumulator tanks.

Power for these channels is provided from two different highly reliable battery backed busses.

The indicated range is 0 to 700 psig. The tanks are pressurized to 450 psig under normal operating conditions. The rating of the instrument is not adequate to prove survivability for the in containment accident environment or post accident radiation exposure.

Compliance: The range of this instrumentation is not in total compliance with the recommendations of RG 1.97, Rev. 2. The equipment is not rated to assure

( survivability for the in containment accident environment or post accident radiation exposure.

Display: Eight Control Room indicators (2 indicators per accumulator tank)

Position: The primary function of this instrumentation is to

• monitor the preaccident status of the accumulators to assure that this passive safety system is prepared to serve its safety function. This instrumentation plays no significant role in the subsequent management of an accident. Therefore, a design and qualification Category of 3 is adequate for this function. The installed system meets the Duke interpretation of Category 3 recommendations as clarified in Section 5.5. Duke Power considers the range and environmental and radiation withstand capability adequate to meet the intended monitoring function.

Implementation Schedule: Not Applicable.

O V

5-44 Revision 2

h J CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-3 Variable: Accumulator Tank Level (Cold Leg Accumulator)

Range: 10% to 90% volume Category: 2 Existing Design: Catawba has two channels of accumulator tank level instrumentation on each of the four accumulator tanks. Power for these channels is provided from two different highly reliable battery backed busses.

The indicated range is 0% to 100%, which corresponds to approximately 23% to 95% of the accumulator tank volume. The rating of the instrument is not adequate to prove survivability for the in containment accident environment or post accident radiation exposure.

Compliance: The range of this instrumentation is not in total compliance with the recommendations of RG 1.97, Rev. 2. The equipment is not rated to assure survivability for the in containment accident g environment or post accident radiation exposure.

Display: Eight Control Rcom indicators (2 indicators per accumulator tank)

Position: The primary function of this instrumentation is to monitor the preaccident status of the accumulators to assure that this passive safety system is prepared to serve its safety function. This instrumentation plays no significant role in the subsequent management of an accident. Therefore, a design and qualification Category of 3 is adequate for this function. The installed system meets the Duke interpretation of Category 3 recommendations as clarified in Section 5.5. Duke Power considers the range and environmental and radiation withstand capability adequate to meet the intended monitoring function.

V 5-45 Revision 2

- O) CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-3 Variable: Accumulator Level (UHI Accumulator)

Range: No specific listing for UHI accumulators Category: 2 Existing Design: Catawba employs a UHI accumulator in addition to Cold Leg accumulators. This system employs an accumulator tank in conjunction with a surge tank.

The accumulator is kept water solid by maintaining water level in the surge tank. Two water level channels are provided for monitoring the level in the surge tank. The range covers 16.5% to 84% of the surge tank volume. The instrumentation is powered from highly reliable battery backed busses and is located in a mild environment.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Two Control Room indicators Position: The RG 1.97, Rev. 2 range is assumed to be directed toward Cold Leg accumulators, not UHI accumulators.

The range of this level instrumentation is adequate to assure the availability of the UHI accumulators to perform their safety function. Duke considers the installed instrumentation to be adequate for the intended monitoring. function.

Implementation Schedule: Not Applicable, i

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5-46 Revision 2

CATAWBA NUCLEAR STATION l

REGULATORY GUIDE 1.97, REV. 2 REVIEW '

l D-3 Variable: Accumulator Pressure (UHI Accumulator)

Range: No specific listing for UHI Accumulator Category: 2 Existing Design: Two independent pressure channels monitor the UHI Accumulator Surge Tank pressure. The range is 800 to 1800 psig. The instrumentation is powered from highly reliable battery backed busses and is located in a mild environment.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Two Control Room indicators Position: The RG 1.97, Rev. 2 range is assumed to be directed toward Cold Leg Accumulators, not UHI accumulators.

O Duke considers installed instrumentation to be adequate for the intended monitoring function.

Instrumentation Schedule: Not Applicable.

O V

5-47 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-4 Variable: Cold Leg Accumulator Isolation Valve Position Range: Closed or Open Category: 2 Existing Design: The cold leg accumulator isolation valves are provided with control switches on the main control boards. Actual valve position is provided by QA Condition 1 limit switches on the valves to operate both Closed-Not Closed, and Open-Not Open control switch indicating lights. These valves and their control switch indicating lights are powered from Class 1E busses. Additional indications are provided by monitor lights and by the computer. Environmental qualification of the limit switches is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification of the limit

[N switches is described in the Catawba FSAR, Section

(,) 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Control Room control switch indicating lights Computer points Monitor lights Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

i 5-48 Revision 2

. -. -_ - .- _ . - . . - . _ . . - - _ = . - - . .

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW Variable:

4. D-4 UHI Accumulator Isolation Valve Position

[ Range: Closed or Open Category: 2 Existing Design: The UHI accumulator isolation valves are provided with control switches on the Hydraulic Service Panel located in the Control Room. Actual valve position i

is provided by QA Condition 1 limit switches on the valves to operate both Closed-Not Closed, and Open-Not Open control switch indicating lights.

These valves and their control switch indicating lights are powered from Class 1E busses. Additional indications are provided by monitor lights.

Seismic qualification of the limit switches is described.in the Catawba FSAR, Section 3.10. The limit switches are located in a mild environment.

4 7- Compliance: This instrumentation is-in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in t

Section 5.5.

Display: Control Room control switch indicating lights l

Monitor lights Position: The installed instrumentation is adequate forLthe l

j. intended monitoring function.

l Implementation Schedule: Not Applicable.

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l 5-49 Revision 2 l

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1

( CATAWBA NUCLEAR STATION i

-REGULATORY GUIDE 1.97, REV. 2 REVIEW D-5 Variable: Boric Acid Charging Flow Range: 0 to 110% Design Flow i Category: 2 Existing Design: The existing instrumentation provides continuous monitoring of centrifugal charging pump flow through b

the NI System directly into the reactor coolant cold legs. The loop range is 0 - 1000 gallons per minute with a design flow of approximately 700 GPM.

This instrument loop is powered from a highly reliable battery backed control buss and is installed in a mild environment.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display

One Control Room indicator.

, One computer point.

Position: The installed instrumentation is adequate for the intended monitoring fuction.

Implementation Schedule: Not Applicable.

t 5-50 Revision 2

1

/9 v CATAWBA NUCLEAR STATION REGULATORY GUIDE'1.97, REV. 2 REVIEW D-6 Variable: Flow in HPI System (Safety Injection System Flow)

Range: 0 to 110% of Design Flow Category: 2 Existing Design: One set of instrumentation per train measures the flow from 0 - 800 GPM with a design flow of 425 GPM. Power is provided from highly reliable battery backed busses. This instrumentation is installed in a mild environment.

Compliance: This' instrumentation is in compliance with Duke's '

interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Two Control Room indicators (one per train)

Position: The installed instrumentation is adequate for the Implementation Schedule: Not Applicable.

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5-51 Revision 2 l

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CATAWBA NUCLEAR STATION s

REGULAT07.Y GUIDE 1.97, REV. 2 REVIEW D-9 Variable: Reactor Coolant Pump Status Range: Motor Current Category- 3

-Existing Design: The indicated range for RCP motor current is from 0 to 800 amps. The instrumentation derives power from the monitored source.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Four Control Room ammeters Four computer points Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation l

Schedule: Not Applicable.

l

's 5-52 Revision 2

i O CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-10 Variable: Primary System Safety Relief Valve Positions (Power Operated Relief Valves)

Range: Closed - Not Closed Category: 2 Existing Design: The Power Operated Relief Valves are provided with conrol switches on the main control boards.

Actual valve position is provided by QA Condition 1 limit switches on the valves to operate both Closed-Not Closed, and Open-Not Open control switch indicating lights. These valves and their control switch indicating lights are powered from Class 1E busses. Additional indications are provided by the computer. Environmental qualification of the limit switches is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification of the limit switches is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Control Room control switch indicating lights, Computer Points Position: The installed instrumentation is adequate for the

! intended monitoring function.

l- Implementation Schedule: Not Applicable.

O 5-53 Revision 2

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-10 Variable: Primary System Safety Relief Valve Positions (Code Valves)

Range: Closed - Not Closed Category: 2 Existing Design: A QA Condition 1 Acoustic Detection System is provided to monitor the position of these valves.

Indicator lights and a monitor light indicate valve (closed - not closed) position. The Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal contain information on the environ-mental qualification of the Acoustic Detection System. Seismic qualification is described in Catawba FSAR, Section 3.10. The instrumentation is powered from a Class 1E buss.

Compliance: This instrumentation is in compliance with Duke's s interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Control Room indicating lights Monitor light Position: The installed instrumentation is adequate for the intended monitoring function.

l Implementation Schedule: Not Applicable.

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5-54 Revision 2 l

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, CV. 2 REVIEW 1

0-12 Variable: Pressurizer Heater Status Rang 3: Electric Current Category: 2 Existing Design: Each of the four pressurizer heater groups have instrumentation for monitoring current. The range is 0 to 600 amps. Power for the transducers is derived from the sources they monitor. The computer readout is powered by highly reliable battery backed busses. This instrumentation is installed in a mild environment.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: On demand display by the plant computer.

Control Room-monitor light to indicate heater j operation.

Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation l Schedule: Not Applicable.

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l 5-55 Revision 2 i

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CATAW8A NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-13 Variable: Quench Tank (Pressurizer Relief Tank) Level Range: Top to Bottom Category: 3 Existing Design: The indicated range of Pressurizer Relief Tank Level is from 0 to 100% corresponding to tank volume of approximately 3% to 97%.

Compliance: The range is not in compliance with RG 1.97 recommenda-tions.

Display: One Control Room indicator One computer point Position: The range of the installed instrumentation is adequate for the intended monitoring function. No changes are planned.

Implementation Schedule: Not Applicable.

t l

l 5-56 Revision 2 L

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-14 Variable: Quench Tank (Pressurizer Relief Tank) Temperature Range: 50 F to 750*F Category: 3 Existing Design: The indicated range of Pressurizer Relief Tank temperature is from 50*F to 300*F.

Compliance: The range is not in compliance with the RG 1.97, Rev. 2 recommendation.

' Display: One Control Rocm indicator One computer point Position: The instrument range is'to be expanded to 350*F, in accordance with the recommendations of the Catawba Control Room Design Review, to cover the range of saturation temperatures up to the tank rupture disc pressure of 100 psig. This range will be adequate for the intended monitoring function.

i Implementation Schedule: The range will be changed by the end of the first refueling outage.

l lO i 5-57 Revision 2 '

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, REGULATORY GUIDE-1.97, REV. 2 REVIEW ^' .

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t 0-15 Variable: Quench Tank (Pressurizer Re,ie{f Tank) Pressi/e '

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Range: 0 to design pressure. *

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J Category: 3 -

if ExistjngDesign

The indicateo' range of the Pressurizer' Relief Tank ,

pressure is from 0 to 100 psig. Jhe tank rupture disc pressure is 100 psig.

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Compliance: 'This instrumentation is in compTian:e with Duke's

, interpretation of RG 1.97,i.ev. 2'as clarified in '

Section 5.5. 4' f ,

Display: One Control Room indicator ,/

One computer point 5 ,

Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation' ',

j Schedule: [ Not Applicabla " ,

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5-58 ,

I Revision 2 4

i CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-16 Variable: Wide Range Steam Generator Level ,

Range: From tube-sheet to separators Category: 1 Existing Design: Catawba has four (one per steam generator) redundant, QA Condition 1 channels of wide range steam generator level instrumentation. Each transmitter feeds a different channel of the PCS and is powered from that channel's associated Class 1E buss. The indicated range is 0 to 100% corresponding to nine inches above the tube-sheet to the separators. Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: 'The range of the instrumentation is slightly less than the recommendation of RG 1.97, Rev. 2.

• Display: Four Control Room indicators (one per steam generator)

Four channels on the computer Four channels recorded Position: The installed range is adequate for measuring. wide range steam generator level and Duke considers the installed instrumentation adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

O 5-59 Revision 2

I l CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-18 Variable: Main Steam Flow (or, Safety Relief Valve Position)

Range: No range listed in RG 1.97, Rev. 2 Category: 2 Existing Design: This station has two redundant, QA Condition 1 channels of main steam flow instrumentation on each of four steam generators. Each (of two per steam generator) transmitter feeds a different channel of the PCS and is powered from the associated Class 1E buss. The indicated range is 0 to 120%

with 100% flow corresponding to normal 100% power maximum flow. Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's O interpretation of RG 1.97, Rev. 2 as clarified in Sectin 5.5.

< Display: Eight Control Room indicators Eight cofnputer points Eight channels recorded Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

5-60 Revision 2

_-_ _____ ._ \

CATAWBA NUCLEAR STATION REGULATORY CUIDE 1.97, REV. 2 REVIEW

D-19 Variable

Main Feedwater Flow Range: 0 - 110% Design Flow Category: 3 Existing Design: Catawba has eight main feedwater flow channels, two channels per steam generator feedline. The indicated range for this variable is 0 to 120%.

This corresponds to 4.556x108 lbs/hr which is 120%

of design flow.

Compliance: This instrumentation is in compliance ith Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Eight Control Room indicators Eight channels on the computer Four channels recorded (Selectable, one of two per feedline)

Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

l O /

5-61 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-20 Variable: Auxiliary Feedwater Flow Range: 0 - 110% Design Flow Category: 2 Existing Design: Catawba has four QA Condition 1 auxiliary feedwater ficw transmitters, one per steam generator, monitoring flow from all auxiliary feedwater pumps to each steam generator. The indicated range is 0-600 GPM for a system design flow of 500 GPM. This instrumentation is powered from Class 1E busses.

Environmental qualification is described in the Catawba FSAR, Section 3.11 and the NUREG 0588 submittal. Seirmic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Four Control Room indicators Four computer points Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

.f3

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5-62 Revision 2

m CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-21 Variable: Auxiliary Feedwater Condensate Storage Tank Level, Or Auxiliary Feedwater Assured Source Range: Plant Specific Category: 1 Existing Design: Catawba's Auxiliary Feedwater System (CA) draws Condensate grade suction from the following three sources:

1. CA Condensate Storage Tank

2. Upper Surge Tanks

3. Condenser Hotwell The safety related source for CA System suction is the Nuclear Service Water (RN) System. This system is QA Condition 1 and is the assured source of secondary side inventory. It is automatically A aligned to the suction of the CA pumps by redundant QA Condition 1 pressure switches which monitor suction pressure. When 2/3 pressure switches in either redundant train detect low suction pressure, the CA System will align to the Nuclear Service Water System. Operator confirmation of the supply or availability of RN as the assured safety source of water to the CA pumps is provided by:

1. QA Condition 1 indication of RN pump operational status. This instrumentation is seismically l qualified and located in a mild environment.

2. QA Condition 1 indication of the RN & CA l suction supply source isolation valves. Valve

! operators, limit switches, indicating lights are seismically and environmentally qualified.

3. QA Condition 1 indication of CA pumps flow to the steam generators. (See variable 0-20).

Additional Category 3 indication is available for

! further confirmation of transfer of the CA pump suc-l tion to the assured source. This indication includes:

1. RN pump header discharge flow.

2. CA pumps suction pressure.

, s 3. CA pumps discharge pressure.

! , I 4. Individual CA pump discharge flows.

U 5-63 Revision 2 l

L

C' b) CATAWSA NUOLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-21 Variable: Continued These monitoring instruments are-located in a mild environment.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: - RN Pump Status:

Two operational status indicating lights per pump One computer point per pump. .

One monitor light per pump.

- RN & CA Suction Supply Valves' Positions Two valve position indicating lights per valve.

Two computer points per valve.

m

) - CA Pumps Flow to the Steam Generators Four Control Poom indicators (1 per S/G).

Four computer points. This variable is also covered in D-20.

- RN Pump header discharge flow (Category 3)

Two Control Room indicators (1 per pump)

- CA Pumps Suction Pressure (Category 3)

Three Control Room indicators (1 per pump)

.CA Pumps Discharge Pressure (Category 3)

Three Control Room indicators (1 per pump)

- Individual CA Pump Discharge Flows (Category 3)

Three Control Room indicators (one per pump)

Position: The installed instrumentation is adequate for the intended monitoring function.

O Implementation V Schedule: Not Applicable.

5-64 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-22 Variable: Containment Spray Flow Range: 0 to 110% Design Flow Category: 2 Existing Design: The containment spray instrumentation provides an indicated range of 0 to 4000 gpm for containment spray flow. Design flow is approximately 3400 gpm, and the power supply is a highly reliable battery backed control buss. One channel is provided for each of two containment spray pumps.

The containment spray flow instrumentation is located in a mild temperature environment.

Compliance: The transmitters for this variable are not rated to withstand the anticipated maximum design basis accident radiation dose for the installed location.

Display: Two Control Room indicators (one per train)

V Position: The transmitters will be replaced with units having the required radiation withstand capability, or the existing transmitters will be moved to a location having a radiation environment suited to their withstand capability.

Implementation Schedule: All modifications will be completed by the end of the first refueling outage.

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i 5-65 Revision 2

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i CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW

0-23 Variable: Heat Removal.by the Containment Fan Heat Removal. System ,

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{ This variable does not apply to Catawba Nuclear Station design.

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5-66 Revision 2 r

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/ CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 . REVIEW 0-24 Variable: Containment Atmosphere Temperature Range: 40 F to 400 F Category: 2 Existing Design: Four RTDs are provided to monitor upper containment temperature, and eight RTDs are provided to monitor lower containment temperature. Two of the upper containment and four of the lower containment RTDs provide control board indication and computer analog read-out over the range of 40 to 200*F. The remaining two upper containment and four lower containment RTDs provide computer analog indication over the range of 32 to 212*F. The instrument loops that provide Control Room indication are powered from an auxiliary power buss.

Compliance: The range and the environmental qualification of O the instrumentation is not in compliance with the recommendations of R.G. 1.97 Rev. 2.

Display: Six Control Room indicators (two upper and four lower containment).

Twelve computer points (four upper and eight lower containment).

Position: Two upper and two lower containment temperature measurement channels will be provided which will withstand post accident environmental conditions.

The instrumentation will be powered by a highly reliable battery backed buss and will have the capability of being displayed on the computer CRT. In accordance with the recommendations of the Catawba Control Room Design Review the range for the lower containment instrumentation will be 32 to 400*F and the upper containment instrumentation will be 32 to 212 F. The worst case upper containment post accident temperature is 180 F.

Implementation Schedule: These instruments will be provided by the end of the first refueling outage.

v S-67 Revision 2

-. . . .. . _ _ - . . -- . . . - . _ . . - . - . . . - = . . . - ._.

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l CATAWBA NUCLEAR SfATION l i

REGULATORY GUIDE 1.97, REV. 2 REVIEW i 1 0-25 Variable: Containment Sump Water Temperature For the Catawba design, this variable is not utilized in the management of a design basis accident and therefore is not provided.

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1 5-68 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-26 Variable: CVCS Makeup Flow Range: 0 to 110% Design Flow Category: 2 Existing Design: The existing instrumentation for this variable provides continuous monitoring of reactor coolant charging flow. The loop range is 0 to 200 gallons per minute. Design flow is 75 GPM. This instrument loop is powered from a highly reliable battery-backed buss. The instrumentation is located in a mild temperature environment.

Compliance: The transmitter for this variable is not rated to withstand the anticipated maximum design basis accident radiation dose for the installed location.

Display: One Control Room indicator One computer point Position: The installed instrumentation is adequate for the intended monitoring function. For accidents in which harsh environments are a result, the system containing this instrumentation (letdown and charging portion of the CVCS) is not required in the mitigation of these accidents and is automatically isolated upon an ESF Actuation. The level of environmental qualification provided for the instrumentation in this system is consistent with the performance expectations of the system and meets the recommendations of Category 3 in Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Implementation o Schedule: -

Not Applicable.

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5-69 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-27 Variable: CVCS Letdown Flow Range: 0 to 110% Design Flow Category: 2 Existing Design: The existing instrumentation for this variable provides continuous monitoring of reactor coolant letdown flow. The loop range is 0 to 200 gallons per minute with a design flow of approximately 75 GPM. This instrument loop is powered from a highly reliable battery-backed buss. The instrumentation is located in a mild temperature environment.

Compliance: The transmitter for this variable is not rated to withstand the anticipated maximum design basis accident radiation dose for the installed location.

Display: One Control Room indicator n One computer point Position: The installed instrumentation is adequate for the intended monitoring function. For accidents in which harsh environments are a result, the system containing this instrumenation (Letdown and charging portion of the CVCS) is not required in the mitigation of these accidents and is automatically isolated upon an ESF actuation. The level of environmental qualification provided for the instrumentation in this system is consistent with the performance expectations of the system and meets the recommendations of Category 3 in Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Implementation Schedule: Not Applicable.

b A.)

l 5-70 Revision 2

O V

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-28 Variable: Volume Control Tank Level

?

Range: Top to Bottom Category: 2 Existing Design: The existing instrumentation for this variable provides continuous monitoring of volume control tank level. The loop range is 0 to 100% of tank level which covers the linear portion of the tank (approximately 17 to 82% of tank volume). This instrument loop is powered from a highly reliable battery backed buss. This instrumentation is located in a mild environment.

Compliance: The range of the instrumentation is not in compliance with the RG 1.97, Rev. 2 recommendation.

Display: One Control Room indicator One computer point d Position: The range of the installed instrumentation is adequate for the intended monitoring function.

Minimum and maximum tank levels are maintained within the range of the instrument. Extending the range into the domed portions of this tank would result in nonlinear readings at each extreme of the scala.

Implementation Schedule: Not Applicable.

1 5-71 Revision 2

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CATAWBA NUCl. EAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-29 Variable: Component Cooling Water Temperature to ESF System Range: 32 F to 200 F Category: 2 Existing Design: The water temperature to the ESF Systems is monitored at the outlet of each train of the Component Cooling Water Heat Exchangers. The power for this instrumentation is a highly reliable battery backed buss, Range for the read out is O'F to 367 F. This instrumentation is installed in a mild environment.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Two computer points (one per Component Cooling train)

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Position: The installed instrumentaticn is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

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5-72 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-30 Variable: Component Cooling Water Flow to ESF Systems Range: 0 to 110% Design Flow Category: 2 Existing Design: The installed QA Condition 1 instrumentation indicates flow in each of two redundant Component Cooling headers. Indicated range is 0 to 11,000 GPM for a system design flow of 10,000 GPM.

The instrumentation is powered from Class 1E busses. Environmental qualification is described in the Catawba Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

4 Display: Two Control Room indicators Two computer peints Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation

( Schedule: Not Applicable.

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5-73 Revision 2-

h v CATAWBA NUCLEAR STATION

' REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-31 Variable: High Level Radioactive Liquid Tank Level Range: . Top to Bottom Category: 3 Existing Design: The indicated range for this variable is 0 to 100%

for each of two tanks. The indication corresponds

.to the tank volume of approximately.2 to 90%.

Compliance: The range is not in compliance with the recomendation of RG 1.97, Rev. 2.

Display: Two computer points Position: The tap to tap range of the installed instruments is adequate to provide tank level information. No change is planned.

Implementation O Schedule: Not Applicable.

i 5-74 Revision 2

K i

I CATAWBA NUCLEAR STATION

.O REGULATORY GUIDE 1.97, REV. 2 REVIEW 1 0-32 Variable: Radioactive Gas Holdup Tank Pressure

. Range: 0 to 150% Design Pressure Category: 3 Existing Design: Catawba utilizes six tanks for radioactive waste gas storage. .The maximum operating pressure for

. these tanks is approximately 100 psig (per the Catwba FSAR, Section 11.3). The' indicated range is

0 to 150 psig for each tank. '

Compliance: This instrumentation is in compliance with Duke's 4

interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Six computer points. i Position: The installed instrumentation is adequate for the  ;

intended monitoring function.

Implementation Schedule: Not Applicable, i

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O 5-75 Revision 2

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.[% CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW 0-33 Variable: Emergency Ventilation Damper Position Range: Open-Closed Status Category: 2 Existing Design: All active emergency ventilation dampers which are actuated under design-basis accident conditions and whose failure could result in a radioactive release to atmosphere have position indication or indication that the required emergency system alignment has been achieved in the Control Room.

At least one channel per damper is provided, and this instrumentation is powered from Class 1E busses. Environmental qualification of the position indication limit switches is described in the Catawba FSAR, Section 3.11 and the NUREG-0588 submittal. Seismic qualification is described in the Catawba FSAR, Section 3.10.

Compliance: Some emergency ventilation dampers do not meet the range recommendations of RG 1.97, Rev 2. Those dampers not in compliance have positive indication that the required emergency system alignment has been achieved but no individual Open-Closed status. Positive indication may be provided by system flows, pressures, etc.

Display: Control Room control switch indicating lights Analog indicators Monitor lights Position: .The installed instrumentation is adequate for the intended monitoring function since the operator is always provided with positive indication that emergency dampers have achieve their safety mode alignment during and after an accident.

Implementation Schedule: Not applicable, u

5-76 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW D-34 Variable: Status of Standby Power and Other Energy Sources Important to Safety Range: Voltages, currents, pressures Category: 2 Existing Design: All QA Condition 1 (Class 1E) or battery backed control busses have undervoltage alarms in the Control Room with local diagnostic capabilities to enable an expedient assessment of abnormal situations.

In addition, the 125 VDC distribution centers have analog indicators of voltage level in the Control Room. All of the Control Room alarms are on highly reliable battery backed busses. All of the sensing relays and alarm electronics are located in a mild temperature and radiation environment.

Compliance: This instrumentation is in compliance with Duke's p interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Control Room annunciators Control Room analog indicators Computer digital peints Position: The installed instrumentation is adequate for the intended nionitoring fuction.

Implementation Schedule: Not applicable 5-77 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW E-7 Variable: Common Plant Vent Radioactive Discharge Range: 10-8 pCi/cc to 104 pCi/cc Category: 2 Existing Design: Catawba has a high range, mid range and low range channel of unit vent radioactivity instrumentation.

These channels are powered from a highly reliable battery backed buss. The indicated range is 1 to 108 R/hr gross gamma for the high range and 10 to 107 cpm and 10 to 108 cpm corresponding to 10-8 to 5 x 103 pCi/mi Kr-85 for the low and mid-range monitors. This instrumentation is installed in a mild environment.

Compliance: This instramentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: Three control room indicators Three computer points Three channels recorded Position: The installed instrumentation is adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

O 5-78 Revision 2

~') CATAWBA NUCLEAR STATION (O REGULATORY GUIDE 1.97, REV. 2 REVIEW E-8 Variable: Rodiation Monitoring for the Vent from Steam Generator Safety Relief Valves or Atmospheric Dump Valves Range: 10-1 pCi/cc to 103 pCi/cc Mass of Steam Released Category: 2 Existing Design: Area radiation monitors will be located adjacent to the main steam lines and upstream of the main steam isolation valves to detect secondary side radiation.

Correlation curves will allow conversion of the monitor readings in R/hr to pCi/cc. The indicated range will be 10-2 to 103 R/hr. Steam releases will be calculated on the plant computer with the information being printed on the alarm typer. The instrumentation will be powered from highly reliable battery backed control busses. This instrumentation is rated to withstand the environ-h) mental conditions that would exist during accidents in which it is intended to operate. A steam line break in the vicinity of this instrumentation may cause the environment to exceed the rated temperature, however, the instrument is not required to remain functional for this event.

, Compliance: This instrumentation is in compliance with Duke's

! interpretation of RG 1.97, Rev. 2 as clarified in l

Section 5.5.

, Display: Four Control Room indicators Four computer points Four channels recorded Position: The installed instrumentation is adequate for the intended monitoring function.

l Implementation Schedule: Not Applicable.

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V 5-79 Revision 2

CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW E-10 Variable: Plant Airborne and Area Radiation (sampling with E-12 onsite analysis, portable instrumentation)

E-13 E-14 Range: Various ranges as listed in RG 1.97, Rev. 2 Category: 3 Existing Design: Equipment and facilities exist at Catawba for making the measurements and analyses recommended by RG 1.97, Rev. 2. Information concerning these capabilities is in the Catawba FSAR, ection 12.5.

Compliance: Some instrumentation may have ranges which differ from the recommendations of RG 1.97, Rev. 2.

Display: Not Applicable.

Position: The instrumentation has been selected using the considerations shown in the Catawba FSAR, Section 12.5. Evaluation of the equipment has determined it to be adequate for the intended functions.

Implementation Schedule: Not Applicable.

0 V-5-80 Revision 2

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CATAWBA NUCLEAR STATION ,

REGULATORY GUIDE 1.97, REV. 2 REVIEW I. '

E-11 Variable: Radiation Exposure Meters This variable is not required based on information given in Supplement 1 to NUREG 0737 Section 6.1-b j

and the Errata sheet to RG 1.97, Rev. 2 dated May, 1981.  :

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5-81 Revision 2 .

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CATAWBA NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW i

E-15 Variable: Wind Direction i Range: 0* to 360* -

Category: 3 Existing Design: Catawba has two channels of wind direction instrumen-tation. The indicated range is 0* to 540*.

Compliance: This instrumentation is in compliance with Duke's

. interpretation of RG 1.97, Rev. 2 as clarified in j Section 5.5. -

Display: Two channels on the computer.

Two channels recorded.

Position: This instrumentation was specified to have a sensitivity of 0.60 MPH and an instantaneous accuracy of 15* which is considered adequate for the intended monitoring l Implementation Schedule: Not Applicable, l

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5-82 Revision 2

CATAWBA NUCLEAR STATION ,

REGULATORY GUIDE 1.97, REV. 2 REVIEW E-16 Variable: Wind Speed Range: 0 - 67 mph Category: 3 Existing Design: Catawbt has two channels of wind speed instru-mentation. The indicated range is 0 - 60 mph.

Compliance: Range is not in compliance with RG 1.97, Rev. 2 recommendations.

1 Display: Two channels on the computer.

Two channels recorded Position: This instrumentation was specified to have a sensitivity of 0.6 MPH, a precision of 0.5 MPH from 0.6 to 30 MPH and a time averaged accuracy of 10.5 MPH, which is considered adequate for the intended monitoring function.

The range of the installed instruments are adequate for Catawba site meteorological conditions. Also note, present range exceeds the recommendation of RG 1.97, Rev. 3.

Implementation Schedule: Not Applicable.

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5-83 Revision 2 l

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. CATAWBA N'ICLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW E-17 Variable: Atmospheric Stability Range: -5 to 10*C Category: 3 Existing Design: The indicated range for atmospheric stability is

-4 to 8*C for a 30 meter interval.

Compliance: This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.

Display: One computer point.

One channel recorded Position: This instrumentation was specified to have an accuracy of 10.1*C which is considered adequate for the intended monitoring function.

Implementation Schedule: Not Applicable.

O 5-84 Revision 2

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