ML20127P587
| ML20127P587 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/31/1984 |
| From: | Hess R, Martin T, Moersfelder CYGNA ENERGY SERVICES |
| To: | |
| Shared Package | |
| ML20127P579 | List: |
| References | |
| DC-5, NUDOCS 8505240031 | |
| Download: ML20127P587 (9) | |
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Job No. 84056 Doc. No. DC-5 Rev. 1 j
INDEPENDENT ASSESSENT PROGRAM l ELECTRICAL SYSTEM REVIEW CRITERIA FOR COMANCHE PEAK STEAM ELECTRIC STATION TEXAS UTILITIES SERVICES, INCORPORATED PHASE IV Prepared by I M/#P/W T. R. Martin Date -
eY $[W A.E.Moerfelder M 29F'B 4 Date Approved by N , W , 7,4 4f- I/3//['/
Date f
R. W. Hess 1
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l CYGNA ENERGY SERVICES 101 California Street, Suite 1000 San Francisco, California 94111 August 1984 8505240031 840429 PDR ADOCK 05000445 A PDR Texas Utilities Electric Company 4 M, Comanche Peak Steam Electric Station Electrical Design Review Criteria; Job No. 84056; DC-5; Rev. I
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. Table of Contents ;
i Section Pm i
1.0 INTRODUCTION
1 2.0 SCOPE 1 3.0 CODES, STANDARDS, AND REFERENCES 2 3.1 10CFR50 Appendix A - General Design Criteria 2 for Nuclear Generating Plants 3.2 10CFR50Section55a(h)-CriteriaforProtection 3 Systems for Nuclear Generating Stations 3.3 NRC Regulatory Guides 3 3.4 Branch Technical Positions 3 3.5 Westinghouse Guidelines 3 3.6 IEEE Standards 4 3.7 CPSES Final Safety Analysis Report 4 3.8 Safety Evaluation Report 5 3.9 Industry Standards 5 4.0 REVIEW CRITERIA 5 l
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i Texas Utilities Electric Company i Mi Comanche Peak Steam Electric Station Electrical Design Review Criteria; Job No. 84056; DC-5; Rev.1
1.0 INTRODUCTION
i The purpose of this document is to provide the criteria to be used for i the design review of the Component Cooling Water System's (CCWS) safeguards portion of Train A and its isolation from the non-safeguards portion.
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2.0 SCOPE ;
The electrical power, instrumentation, and control circuit designs l
-included in this review are those functions associated with the 1 4 following major components of Train A of the CCWS. The review of the i power circuits will extend to the source breakers supplying power for i the CCWS' operation. !
o CCW Surge Tank (CP1-CCATST-01) level control; control room level l indication, annunciation, and recording; vent valve control; and 1 domineralized water supply valve control will be assessed. Designs l for the domineralizer water system and reactor water makeup system will not be assessed since they are not directly interlocked with the ;
surge tank controls. ,
o CCW Pump (CP1-CCAPCC-01) power and control; control room pressure indication; and redundant CCW and Station Service Water (SSW) pump
, interlocks will be assessed.
e CCW Heat Exchanger (CPI-CCAHHX-01) control room outlet temperature indication; control room CCWS total flow indication; control room CCW pump recirculation flow indication; and interlocks to CCW pump recirculation control valve will be assessed. Thermowells TW-4529 TW-4531, and local temperature indication will not be assessed since they do not perform active system functions.
f e NuclearChilledWaterSystemCondenser(CP1-CHCICE-05)controlroom t- outlet flow indication will be assessed. Local inlet temeperature indication will not be assessed since it does not perform an active ,
system function.
e Control Room A/C Condensers (CPX-VAACCR-01 and CPX-VAACCR-02) control l room combined outlet flow indication will be assessed. Local outlet temperature indication will not be assessed since it does not perfom an active system function.
l l e Residual Heat Removal Heat Exchanger (TBX-RHAHRS-01) discharge flow
- and discharge temperature will be assessed. Thermowells TW-4564 and l TW-4565 will not be assessed since they do not perform active system functions.
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e ContainmentSprayHeatExchanger(CP1-CTANCS-01) discharge'flowand discharge temperature will be assessed. Thernowells TW-4568 and TW-4569 will not be assessed since they do not perform active system functions.
' e Power and control circuits for the following valves will be assessed:
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- Recirculation flow control valve FV-4536.
- Containment Spray Heat Exchanger outlet valve HV-4574.
- Residual Heat Removal Heat Exchanger outlet valve HV-4572.
- Train A Separation valves HV-4512 and HV-4514.
- - Train A Non-Safeguards Loop Isolation valves HV-4524 and HV-4526.
e CCW Header Radiation Monitor (RE-4509) control room annunciation and CCW surge tank atmospheric vent valve interlocks will be assessed.
3.0 CODES. STANDARDS. AND REFERENCES This section lists the regulatory codes, guidelines, industry standards, i
and references that were applicable during the design phase of this project. These codes, standards, and references contain the criteria against which the design of the CCWS will be evaluated.
I 3.1 1DCFR50 Appendix A - General Design Criteria for Nuclear Generating Plants
- a. Criterion 1 Quality Standards and Records
- b. Criterion 2 Design Bases for Protection against Natural Phenomena
- c. Criterion 3 Fire Protection
- d. Criterion 4 Environmental and Missile Design Bases
- e. Criterion 5 Sharing of Structures, Systems, and Components
- f. Criterion 13 Instrumentation and Control .
- g. Criterion 17 Electric Power Systems j h. Criterion' 19 Control Room 4
Texas Utilities Electric Company 2 M3 m Comanche Peak Steam Electric Station Electrical Design Review Criteria; Job No. 84056; DC-5; Rev.1
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3.2 10CFR50 Section 55afh) - Criteria for Protection Systems for Nuclear Generating Stations 3.3 NRC Regulatory Guides
- a. 1.6 Independence between Redundant Standby (0nsite) Power Sources and between their Distribution Systems
- b. 1.29 SeismicDesignClassification(Revision 1,8/73)
- c. 1.32 Use of IEEE Standard 308-1971, " Criteria for Class IE Electric Systems for Nuclear Power Generating Stations" (8/11/72)
- d. 1.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems
- e. 1.53 Application of the Single Failure Criterion to Nuclear Power Plant Protection Systems (6/73)
- f. 1.75 Physical Independence of Electric Systems (Revision 1, 1/75)
- g. 1.97 Instrumentation for Light Water Cooled Nuclear Power Plants to Access Plant Conditions During and Following an Accident
- h. 1.105 Instrument Spans and setpoints
- 1. 1.106 Thermal Overload Protection for Electric Motors on Motor-Operated Valves 3.4 Branch Technical Positions
- a. ICSB 18 Application of Single Failure Criteria
- b. ICSB 21 Guidance for Application of R.G. 1.47 3.5 Westinghouse Guidelines Functional Requirements and Design Criteria, Standard Single and Twin Units 212, 312, and 412 Plants, Component Cooling Water System.
Identification No. BOP FR-1 Rev. 3 dated 6/75.
3 Texas Utilities Electric Company M3 lunipalmilillil Comanche Peak Steam Electric Station Electrical Design Review Criteria; Job No. 84056; DC-5; Rev. I
3.6 IEEE Standards
- s. 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations (Revision 1)
- b. 308-1971 Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
- c. 323-1974 Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
^ d. 334-1974 Standard for T p Tests of Continuous Duty Class 1E Motors for Nuclear Power Generating Stations e.
344-1975 Reconnended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations
- f. 379-1972 Guide for the Application of the Single Failure Criterion to Nuclear Power Generating Station Protection Systems
- g. 382-1972 (ANSI N41.6) Guide for Type Test of Class 1 Electric Valve Operators for Nuclear Power Generating Stations
- h. 383-1974 Type Test of Class IE Electric Cables, Field Splices,-
and Connections for Nuclear Power Generating Stations
- i. 384-1974 Trial-Use Standard Criteria for Separation of Class IE Equipment and Circuits
- j. 420-1973 Trial-Use Guide for Class 1E Control Switchboards for Nuclear Power Generating Stations
- k. 494-1974 Standard Method for Identification of Documents Related to Class 1E Equipment and Systems for Nuclear Power Generating Stations 3.7 CPSES Final Safety Analysis Report
- a. Section 7.0 Instrumentation and Controls
- b. Section 8.0 Electric Power
- c. Section 9.2.2 Component Cooling Water System 1
Texas Utilities Electric Company 4 Comanche Peak Steam Electric Station Electrical Design Review Criteria; Job No. 84056; DC-5; Rev.1
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3.8 Safety Evaluation Report Safety Evaluation Report for Comanche Peak Steam Electric Station, Units 1 8: 2. NUREG-0797.
3.9 , Industry Standards All applicable NEMA, NFPA, ANSI, and IPCEA (Insulated Power Cable EngineersAssociation).
4.0 REVIEW CRITERIA This review will assess that the design:
o Complies with the Codes, Standards, and References of Section 3.0.
e Implements the mechanical process requirements.
e Is properly documented.
e Is completely and a:curately presented in the equipment c specifications.
4.1 Verify that the electrical power circuit design: .
e Maintains electrical and physical separation of redundant power sources for motors, valves, instrumentation and control circuits performing redundant functions.
1 e Provides amergency power during loss of normal and off-site power.
e Provides acceptable voltage for the pump valves, instrumentation, and control circuits.
e Were based on the appropriate voltage drop, short circuit, cable sizing and protective relaying calculations and is incorporated into
- equipment specifications.
4.2 Verify that the selection and application of instrumentation:
e Matches process ranges to the appropriate mechanical design inputs.
p Texas Utilities Electric Company 5 M Comanche Peak Steam Electric Station Electrical Design Review Criteria; Job No. 84056; DC-5; Rev.1
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4.3 Verify that instrumentation is provided as required by FSAR Section 9.2.2 for:
.e Control room indication of:
- CCW pump discharge pressure, recirculation flow and total flow.
- CCW heat exchanger outlet temperature.
- Containment spray heat exchanger outlet temperature and flow.
- Residual heat renoval heat exchanger outlet temperature and flow.
- CCW surge tank level.
e Control room annunciation of:
- CCW heat exchanger high temperature.
- Low flow alarms for RHR and Containment Spray heat exchangers, and the CCW pump recirculation flow and total flow.
- High and low-low CCWS surge tank level.
- High CCWS radiation.
- Local control of equipment at the Hot Shutdown panels.
e Recording of:
- CCW pump total flow.
- CCW surge tank level.
4.4 Verify that the control circuit design:
e Maintains isolation of safety-related control circuits from non-safety-related control circuits.
e Addresses the concerns of the applicable Regulatory Guides and Branch Technical Positions.
Texas Utilities Electric Company 6 i
M3 Comanche Peak Steam Electric Station Electrical Design Review Criteria; Job No. 84056; DC-5; Rev.1
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4.5 Verify that the following modulating and on-off control functions are provided as required in FSAR Section 9.2.2:
o CCW pumps and remote-operated valves are controlled from the control room, that the valves have open and closed indicating lights with l both illuminated in the intermediate position, and that these control i circuits have isolation and local control switches at the Hot i Shutdown panel. j e The redundant CCW and Station Service Water (SSW) pumps automatically start on low pressure in the operating train of the CCWS or SSWS.
e Surge tank makeup inlet valves automatically open on surge tank low-low level and automatically close on surge tank high level.
e CCW pump recirculation valve automatically opens when CCWS total flow decreases below the minimum total flow setpoint and automatically closes when flow increases above the minimum flow setpoint. The recirculation valve also automatically closes upon receipt of an "S" signal.
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e An "S" signal starts the CCW pumps, closes the recirculation valve, i and partially opens the RHR heat exchanger valve.
j e A "P" signal opens the RHR and Containment Spray heat exchanger valves and closes the safeguards loop isolation valves. ,
- e A high-radiation signal for the CCWS return header will close the CCW surge tank atmospheric vent valves.
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Electrical Design Review Criteria; Job No. 84056; DC-5; Rev.1 EMNNNNNNNNNNN
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