ML20127P612

From kanterella
Jump to navigation Jump to search
Rev 1 to DC-4, Independent Assessment Program Mechanical Design Review Criteria for Comanche Peak Steam Electric Station,Texas Util Svcs,Inc,Phase 4
ML20127P612
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 08/29/1984
From: Foley J, Hess R, Rainey P
CYGNA ENERGY SERVICES
To:
Shared Package
ML20127P579 List:
References
DC-4, NUDOCS 8505240036
Download: ML20127P612 (10)
v • d • e


Text

__ . _ _ _ _ _ _ _ - _ _

Jtb No. 84056 Doc. No. DC-4 Rev. 1 l

l INDEPENDENT ASSESSMENT PROGRAM MECHANICAL DESIGN REVIEW CRITERIA FOR j COMANCHE PEAK STEAM ELECTRIC STATION TEXAS UTILITIES ELECTRIC COMPANY PHASE 4 Prepared by 8 '6/6/

Folei '

Date

!" % ;"!;"' O . 9 c.. % &lules P. Rainey Date Approved by ,d. M f/2 f((Y R. Hess Date Cygna Energy Services 101 California Street, Suite 1000 San Francisco, CA 94111 May 1984 8505240036 850429 PDR A

ADOCK 05000445 PDR Texas Utilities Electric Company

( 6 a Comanche Peak Steam Electric Station RNNNINNNNNNNNNNI Mechanical Design Review Criteria; Job No. 84056; DC-4; Rev. I l

TABLE F CONTENTS Page Section

1.0 INTRODUCTION

................................................... 2 2

2.0 SC0PE..........................................................

3.0 CODES, STANDARDS, AND REFERENCES............................... 4 3.1 NRC REGULATORY GUIDES..................................... 4 3.2 10 CFR 50 APPENDIX A - GENERAL DESIGN CRITERIA............ 4 FOR NUCLEAR PLANTS 3.3 CPSES FINAL SAFETY ANALYSIS REP 0RT........................ 5 3.4 SAFETY EVALUATION REP 0RT.................................. 5 3.5 WESTINGHOUSE GUIDELINES................................... 5 5

3.6 INDUSTRY STANDARDS........................................

6 4.0 REVIEW CRITERIA................................................

l Texas Utilities Electric Company . 1 L% ( 6 a Comanche Peak Steam Electric Station Mechanical Design Review Criteria; Job No. 84056; DC-4; Rev.1

1.0 INTRODUCTION

This document provides the criteria for the mechanical review of selectea portions of the component cooling water system for the Connianche Peak Steam Electric Station.

2.0 SCOPE The sechanical review of the Unit 1 component cooling water (CCW) system will include components located in the major flowpaths described below.

The physical boundaries for the review say vary somewhat to permit an effective review of the system design.

e Flowpath from the CCW surge tank to the Unit 1 CCW pump suction.

. Flowpath from the outlet of the CCW neat exchanger to the inlet of the nuclear chilled water system condenser and the control room A/C condenser.

e Recirculation flowpath from the CCW pump discharge through the CCW heat exchanger to the suction of the CCW pump.

  • Flowpath from the CCW heat exchanger outlet to tlie inlet of reactor coolant pump TBX-RCP CPC-01 lube oil coolers ( apper and lower),

thernal barrier cooler, and motor air coolers.

  • Flowpath from the CCW heat exchanger to the inlet of the ventilation l chillers CPX-CHCICE-01.

Texas Utilities Electric Company 2 Comanche Peak Steam Electric Station g g g Mechanical Design Review Criteria; Job No. B4056; DC-4; Wev.1 WilllllilllHillllNilllil

- The major components in this ruview will include the CCW pump, CCW heat l l I exchanger, CCW surge tank, and valves and orifices in the designated flowpaths. The review will not include the design of Westinghouse ;

supplied components or engineering data as these will be considered )

inputs to the G&H design. Figure 2-1 illustrates the scope of the j l

- review.

{

Texas utilities Electric Company 3 Comanche Peak Steam Electric Station )

a Mechanical Design Review Criteria; Job No. B4056; DC-4; Rev.1

. untillil

3.0 CODES, STANDARDS, AND REFERENCES 3.1 NRC REGULATORY GUIDES

, s. 1.26 Quality Group Classifications and Standards for Water, Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants.

b. 1.29 Seismic Design Classification.
c. 1.141 Containment Isolation Provisions for Fluid Systems.

3.2 10 CFR 50 APPENDIX A - GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS

a. Criterion 2 Design Bases for Protection Against Natural Phenomena.
b. Criterion 3 Fire Protection
c. Criterion 4 Environmental and Missile Design Bases
d. Criterion 5 Sharing of Structures, Systems and Components.
e. Criterion 44 Cooling Water.
f. Criterion 45 Inspection of Cooling Water System.
g. Criterion 46 Testing of Cooling Water System.
h. Criterion 54 Piping Systems Peretrating Containment.
1. Criterion 56 Primary Containment Isolation. l f

Texas Utilities Electric Company 4 b k A hN!a Nsh*IchlNNith Dob No. 84056; DC-4; Rev.1

L.

. ..=._._. 2. . .

~

j. Criterion 57 Closed System Isolation Valves.

3.3 CPSES FINAL SAFETY ANALYSIS REPORT

a. Section 3.2.1 Seismic Classification.
b. Section 3.2.2 System Quality Group Classification.
c. Section 3.6.1 Plant Design for Protection against Postulated Piping Failures in Fluid Systems Outside Containment.
d. Section 3.11 Environmental Qualification of Mechanical and Electrical Equipment. l
e. Section 9.2.2 Component Cooling Water System.

3.4 SAFETY EVALUATION REPURT Safety Evaluation Report for Comanche Peak Steam Electric Station, Units 1 and 2. NUREG-0797. 1 3.5 WESTINGHOUSE' GUIDELINES l

.a. Functional Requirements and Design Criteria Standard Single and Twin l Units 212, 312, and 412 Plants, Component Cooling System.

Westinghouse identification No. BOP FR-1 Rev. 3 dated 6/75.

1 l

~

3.6 INDUSTRY STANDARDS All designs will be reviewed to ensure that appropriate indust ry standards have been incorporated where applicable. These standards will consist of:

Wg MNNNNNININNNNNN a

Texas utilities Electric Company Comanche Peak Steam Electric Station Mechanical Design Review Criteria; Job No. 84Ub6; UC-4; Nev.1 b

a. Standards of Tubular Exchanger Manufacturers Association - TEMA
b. Hydraulic Institute Standards - HI

, c. Crane Technical Paper #410

d. American National Standards Institute - ANSI
e. American Society of Mechanical Engineers - ASME 4.0 REVIEW CRITERIA CCWS components described in the scope of work, Section 2.0, will be reviewed using the documents listed in the codes, standards and references section (Section 3.0). This review will assess if the design:

o Complies with FSAR requirements.

e Complies with NRC requirements.

  • Results in a CCW system that will meet all its design criteria.
  • Is completely and accurately presented in the design ,

documents and procurement specifcations. l 4.1 The system arrangement shall be in accordance with Westinghouse document i l

BOP FR-1 and NRC requirements, e.g..

l 1

Texas Utilities Electric Company M3 6

Comanche Peak Steam Electric Station Mechanical Design Review Criteria; Job No. 84056; DC-4; Rev.1 WN1111NilNill1NNN1111

e Redundant components shall be protected from simultaneous failure resulting from natural phenomena, missiles, fires, floods and harsh environments.

. e Relief valves shall be provided to prevent overpressurization of piping and components.

e The surge tank shall be connected to the suction piping of the pumps and located above the pump to provide adequate NPSH.

4.2 System flow and pressure drop calculations shall have been performed in accordance with accepted industry practice and meet Westinghouse, equipment vendor, and NRC requirements for all modes of operation.

4.3 The component cooling water (CCW) system shall provide adequate cooling water to the required components during normal, abnormal, accident and post-accident conditions in accordance with Criterion 44 of 10 CFR bU Appendix A, and Westinghouse document Number BOP FR-1, e.g.:

e The system shall be sized to reduce the temperature of the reactor coolant after a plant shutdown from 350*F to 140'F in 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> initiating cooldown operations approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after plant l shutdown. .

e The system shall supply cooling water to the residual heat removal heat exchangers at a maximum temperature of 120'F gradually reducing the temperature to 105'F following a plant shutdown.

e The system shall supply cooling water which is < 105'F for all otner operating modes.

Texas utilities Electric Company 7 Ma IMIN11111M1111111111111 Comanche Peak Steam Electric Station Mechanical Design Review Criteria; Job No. 84056; DC-4; Rev.1

., , _ , , , , 7, - . _ - - - - _ _ _ .-

e The system shall supply the design flow rates specified in 80P-FN-1 to the components specified in 80P-FR-1.

e CCW system pressure shall be maintained above service water system pressure to prevent in-leakage of service water.

4.4 The CCW system's essential portions shall be designed to witnstand severe natural phenomena, and shall have redundancy so that safety functions can be performed after a single active or passive component failure in accor-dance with Criteria 2 and 44 of 10 CFR 50 Appendix A, and Westinghouse j document 80P FR-1, e.g.:

e Redundant safeguards loops to ensure one safeguard loop is available following any single failure.

e Redundant isolation valves provided to ensure isolation in the event of a valve failure coincident with loss of offsite power.

e Redundant heat exchangers to ensure dissipation of plant heat loads in the event of a heat exchanger failure.

e Redundant pumps provided to ensure pumping capacity in the event of a pump trip.

9 4.5 The CCW system's non-essential portions shall be isolable from the essential portions of the system by redundant automatically operated isolation valves in accordance with Regulatory Guide 1.141, and Criterion 44 of 10 CFR 50 Appendix A.

4.6 The system design shall provide for functional test and inspection requirements of the NRC, as stated in Criteria 4b and 46 of 10 CFR 50 Appendix A, e.g.-

! Texas Utilities Electric Company 8 Comanche Peak Steam Electric Station  !

l Mechanical Design Neview Criteria; Job No. 84056; DC-4; Rev. I  ;

l 1

_.' ' -~

l e Operability and performance of the active system components.

.e System operability during normal plant operation and shutdown.

e Inspectability of piping ar.d components on a periodic basis.

4.7 The surge tank shall be designed in accordance with Westinghouse document 80P FR-1, e.g.:

  • The tank shall have sufficient capacity to acconnodate expected leakage from the system for seven days.

e Makeup water can be supplied to either header in a split header system.

e The loss of the entire contents of the entire surge tank shall not occur in the event of a header rupture.

e The tank shall be the high point in the system to ensure an adequate net positive suction head to the CCW pump and provide for system venting.

4 Texas Utilities Electric Company 9 M Comanche Peak Mechanical Design ReviewSteam Criteria; JobElectric Station No. 84056; DC-4; Hev.1

. _ _ . .__

Retrieved from "https://kanterella.com/w/index.php?title=ML20127P612&oldid=2918290"