Text

Requirements for Environ Qualification of Class IE Equipment
	ML20204B638
Person / Time
Site:	Clinch River
Issue date:	08/31/1978
From:	Clare G, Mclane F; ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To:	;
Shared Package
ML20204B444	List: ML20204B442; ML20204B638;
References
	WARD-D-0165, WARD-D-0165-R01, WARD-D-165, WARD-D-165-R1, NUDOCS 7810170259
	Download: ML20204B638 (69)
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Clinch River Breeder Reactor Plant REQUIREMENTS FOR ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT ENGINEERING RELEASE BY h LRM ERO L-00032 D ATE 8/31/78 Prepared for the United States Department of Energy under contracts EY 76 C 15-2395 and EY 76-C 15-0003.

Any Further Distribution by any Holder of this Document or of the Data Therein to Third Parties Representing Foreign Interest, Foreign Governments, Foreign Companies and Foreign Subsidiaries or Foreign Divisions of U.S. Companies Should be Coordinated with the Director, Division of Reactor Research and Development, U.S. Department of Energy.

W Westinglouse i ectric Cor] oration ADVANCED REACTORS DIVISION 8-78-PO1246-14 BOX OAK RIDGE TENNESSEE 37830

WARD -D-0165 t

REQUIREMENTS FOR ENVIRONMENTAL QUALIFICATION OF CRBRP CLASS 1E EQUIPMENT t

PREPARED BY:

$ 3 F. E. McLane, Systems E7tgineering' o

G. th-tTarti, Systaiffs Engineering APPROVED: .

W W. H. Hamilton,Jr., Manhgler, Systems Engineering l

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-,,,,c TITLE DOCUMENT NO.

Mi CHANGE CONTROL Requirements for j LMF, BR

_, RECORD Environmental Qualification WARD-D-0165

WESTINGHOUSE of CRBRP Class 1E Equipment ADVANCED REACTORS DIVISION .

CHANGE i REV NO./ RELEASE PAGES AFFECTED REMARKS DATE DOCUMENT Rev. 1/

8/31/78 L-00032 All Initial Release (Rev. O was never released) 1 4

4

=

'N 5-78-PO1471 1

L INFORMATION CONCERNING USE OF THIS REPORT PRELIMINARY DOCUMENT This report contains information of a preliminary nature prepared in the course of work for the U. S. Department of Energy. This information is subject to correction or modification upon the collection and evaluation of additional data.

NOTICE This report was prepared as an account of work sponsored by the United States Government. Neither the U. S. Department of Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, expressor implied, or assumes any legal liability or responsibility for the accuracy, completeness of usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights.

WESTINGHOUSE ELECTRIC CORPORATION ADVANCED REACTORS DIVISION P. O. B0X W 0AK RI DGE , TN . 37830

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4-TABLE OF' CONTENTS SECTION PAGE 1 INTRODUCTION 1-1 to' 1-2 2 , ENVIRONMENTS 2-1. to 2-14 ,

3 -QUALIFICATION BAS S AND IMPLEMENTATION 3-1 to 3-18' l 4 QUALIFICATION PROCEDURES 4-1 to 4-12

5 DOCUMENTATION OF QUALIFICATION 5-l' l ACRONYMS REFERENCES 1

APPENDICES A , EQUIPMENT QUALIFICATION DATA PACKAGE A-1 to A-12 l

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k LIST 0F TABLES-Table Title Page 2-1 Normal Envirorrnental Conditions 2-2 2-2 Design Basis Events Which may Produce Severe 2-3 to 2-5 .

Environments for Class 1E Equipment 3-1 ' Class 1E Equipment not Subjected to Severe 3-3 to 3-14 Envirorynents 3 Class 1E Equipment Subjected to Severe - 3-15 to 3-18 Environments ;

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!.IST OF FIGURES Figure Title Page 2 Temperature Transient (Pri Na Storage Tank Fire) 2-6 2-2' Pressure Transient (Pri Na Storage Tank Fire) 2-7 2-3 Radiation Dose Rates (Pri Na Tank) 2-8 2-4 Chemical Transient (Pri Na Storage Tank Fire) 2-9 2-5 . Temperature Transient (Pump Brg. Oil Fire) 2-10 2-6 Dose Rate (Reactor Cover Gas Release) 2-11 2-7 Temperature after Steam /Feedwater 2-12 2-8 Pressure after Steam /Feedwater 2-13 7

2-9 Dose Rate in RSB Cells 352A and 353A 2-14 4-1 Environmental Test for Equipment Not Subjected to 4-9 Severe Accident Environments 4-2 Qualification Envelope for Equipment Located in 4-10 Severe Accident Environments 4-3 AGE Acceleration vs. Temperature 4-12 ,

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1. INTRODUCTION This document establishes the qualification program which will be conducted to qualify Class IE equipment located in different areas of the Clinch River Breeder . Reactor Plant and sets forth the documentation to be completed for qualification. The entire program is designed to conform to IEEE Std. 323-1974 as clarified by the forward issued by NPEC on July 24, 1975 as IEEE - Std. 323A 1975. When IEEE Std. 323-1974 is mentioned in this document, it is to be understood to include the clarification issued as IEEE Std. 323A-1975. -

Class 1E equipment will be qualified to meet its performance requirements by analysis, type testing, operating experience or any appropriate combination thereof. The qualification will be based upon the most severe environment predicted to occur prior to and during those portions of the specific accident transients for which the component is required to perform its safety function.

Where it is practical to do so, CRBRP Class IE systems are designed with redundant channels located in separate cells. Consequently, redundant safety equipment located in separate cells is not required to be qualified for Design Basis Events and/or accident conditions if the effects of the DBE's are not propagated to the redundant cells. However, all of these equipment items shall, as a minimum, satisfy the seismic and aging qualification requirements of this document. Where the use of identical components in the same or more severe environments makes it possible to do so, component qualification data from licensed nuclear power plants will be utilized for qualification of CRBRP components.

The CRBRP qualification program described herein will meet the applicable re-quirements of Regulatory Guide 1.89. However, the CRBRP qualification program will use the radiological source term (site suitability source term) to define the radiation environment for qualification only for the Class IE equipment required to function during and following the SSST release to mit-igate the consequences of the release. For all other Class IE equipment, the radiation environment for qualification will be defined by the enveloping DBE (excluding the SSST) for which the specific Class IE equipment must perform a safety function. The DBE will include pressure, temperature, humidity, chemical, vibration, and seismic effects as well as those of radiation.

The nominal life of the CRBRP is 30 years and, consequently, the " aging" requirement of IEEE Std. 323-74 will be met by appropriate procedures based on exposure to normal environment for a maximum of 30 years. The specific procedures to be used are described in Section 4.

Electrical equipment that is part of the thermal margin beyond the design basis (TMBDB) is not included in this document. For treatment of the qualification of this equipment, see 500-27 and CRBRP - 3 Volume 2.

The scope of this document is limited to environment qualification of CRBRP Class IE equipment. Section 2 of this document describes normal and accident environments in the five buildings of the Nuclear Island.and for emergency cooling towers.

1-1

4 Section 3 states the basis for environmental qualification to all significant environmental parameters and lists (in table 3-2) curves of accident parameter transients from Section 2 that apply to each specific piece of Class IE equipment. The equipment that is not subjected to severe environments as a result of the applicable design basis events i_s ,

also listed (in table 3-1) with locations and maximum anticipated

~

temperatures . Tables 3-1 and 3-2 also define the length of time the equipment must operate during and/or after the DBE. The equipment information contained in these tables is subject to correction'or modification upon changes to the individual System Design Descriptions which establish the equipment requirements. All Class IE equipment will be qualified to the appropriate seismic' acceleration for its location within the plant. l Section 4 describes type test qualification procedures for Class IE equipment not subjected to severe accident environments and qualification procedures for Class IE equipment that is subjected to severe accident environments. This Section also describes qualification by operating experience and analysis.

Section 5 and Appendix A set forth the content and suggested fonnat for the preparation of Equipment Qualification Data Packages which will be prepared for each piece of equipment qualified by type test, operating experience or analysis.

The qualification program for active pumps and valves is presented in WARD-D-0174 (Active Pump and Valve Operability Verification Plan).

Class IE electro-mechanical equipment subject to the requirements of WARD-D-0174 must also be qualified according to the requirements of this document. .

A list of the references upon which this document is based is provided at the end of the text. A listing of acronyms is also provided.

1-2

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2. ENVIRONMENTS The environments to be considered in Class IE equipment qualification procedures are set forth in this section for normal operating conditions .

and for those design basis events in CRBRP that produce severe environments in cells that contain safety related equipment. Radiation doses resulting from release of the SSST are considered where appropriate. The numerical values of environment parameters specified in this section do not include the margins to be added per IEEE Std. 323-1974 for qualification. These margins have been added to produce the dotted curves in figures 2-1 to 2-11. Equipment specifications are to include the appropriate margins, the time interval during which the equipment must be capable of performing its safety function,. and the applicable parameter transients from Section 2.

Seismic event parameters are considered in accordance with IEEE Std. 344-1975 (Reg. Guide 1.100) and WARD-D-0037. The seisnic and vibration environments for ea~ch e c iten specification and,quipment thereforeitem are presented are not defined'in in ea'this h equipment section. end-2.1 Nominal Environments Nominal environments in the buildings of the Nuclear Island are shown in Table 2-1.

2.2 Accident Environments For the purpose of qualification of Class IE equipment throughout CRBRP, the design basis events listed in the PSAR were reviewed and those which might produce significant environmental effects in each building were tabulated in Table 2-2. Study of the environmental parameter transients resulting from these events has shown which events produce the most severe transients and, therefore, which set of transients will serve as the basis for environmental qualification. The resultant transients are shown in Figures 2-1 through 2-13 in this section.

A DBE which produces changes in environmental parameters that are so small or otherwise of such a nature that they do not change mechanical, electrical, physical or chemical properties of any Class IE equipment is considered to produce a non-severe environment. The alternative concept is also ,

used. A DBE which produces changes in environmental parameters which may significantly change the properties of Class IE equipment is considered to produce a severe environment.

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4 Table 2-1 NOMINAL ENVIRONMENTAL CONDITIONS 30 Year Equipment -

Temp. % RH Pressure Radiation op Dose RADS Reactor Containment Building Head Access Area 85 30% -k" W.G.

I&C Cubicles 75 30% -k" W.G. < 50 Operating Floor 100 30% -k" W.G. < 50 Inerted & RAPS Cells 120 N/A -k" W.G.

95 " W.G. *

' All Other Areas 30% -

Reactor Service Building Operating Floor 100 30% -k" W.G. < 50 Refueling Connunication Center 80 30% -k" W.G. < 50 Fuel Handling Cell Op. Gallery 80 30% -k" W.G. < 50 Inerted Cells 120 N/A 3/4!'W.G .

All Other Areas 110 30% -k" W.G.

Steam Generator Building ,

Intermediate Bay Na Cells 100 30% ATM Intermediate Bay All Other Areas 100 30% ATM Loop Cell Bays 100 30% ATM < 50 Auxiliary Bay AFWP Cells 100 30% ATM Auxiliary Bay-All Other Areas 100 30% ATM ,

Diesel Generator Building Diesel Generator Room 105 30% ATM

'< 50 All Other Areas 105 30% ATM Control Room Building ,

Control Room 76 50% + " W.G.

Control Room HVAC/ Filter Cells 100- 30% + " W.G. ' < 50 Battery Rooms 95 30% ATM All Other Areas 105 30% ARM /

N/A = Not Applicable o For normal radiation dose in 30 years for equipment in specific cells, refer to normal i radiation by area given on pages 7-190 to 7-201 of OPDD-10 and multiply area dose rate in MREM /HR by 250 to get equipment dose in RADS.

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Table 2-2 DESIGN BASIS EVENTS WHICH MAY PRODUCE SEVERE ENVIRONMENTS FOR CLASS 1E EQUIPMENT -

I. Reactor Containment Building

1. Loss of off-site electrical power and failure of 1 diesel

2. Primary heat transport system pipe leak

3. Intermediate heat transport system pipe leak

4. Single fuel assembly cladding failure and subse'quent fission gas release during refueling

5. Off-normal cover gas pressure in the reactor primary coolant boundary

6. Leakage from sodium cold traps

7. Maximum possible conventional fire

8. Primary sodium In-Containment storage tank failure during maintenance 9 Failure of ex-containment primary sodium storage tank

10. Safe Shutdown Earthquake 11 Maximum possible internal flood or water spray

12. RAPS surge tank failure (or high pressure pipe from surge vessel)

NOTE: The SSST release will produce a severe radiation environment for .

some of the electrical equipment which must function to mitigate the consequences of the SSST release.

II. Control Building

1. Intermediate heat transport system pipe letk

2. Maximum possible conventional fire

3. Safe Shutdown Earthquake t

4. Maximum possible internal flood or water spray

5. RAPS surge tank failure (or high pressure pipe from surge vessel) 2-3

r TABLE 2-2 DESIGN BASIS EVENTS WHICH MAY PRODUCE SEVERE ENVIRONMENTS FOR CLASS lE EQUIPMENT !

III. Turbine Building None ( no safety related equipment )

IV. Steam Generator Building

1. Loss of off-site electrical power and failure of one diesel

2. Steam or feed-line pipebreak

3. Intermediate heat transport system pipe leak

4. Maximum possible conventional fires

5. Safe shutdown earthquake f

6. Maximum possible internal flodd and w'atdf Ypray

7. RAPS surge tank failure (or high pressure pipe from surge vessel)

V. Diesel Generator Building

1. Intermediate Heat Transport system pipe leak

2. Failure of RAPS / CAPS Cold Box (or high pressure pipe from surgevessel)

3. Maximum possible conventional fire

4. Safe shutdown earthquake

5. Maximum possible internal flood and water spray VI. Reactor Service Building

1. Loss of off-site electrical power and failure of 1 diesel

2. Intermediate heat transport system pipe leak

3. Single fuel assembly cladding failure and subsequent fission gas release during refueling

4. Cover gas release during refueling

5. Cover gas release during operation

6. Failed fuel element in FHC

7. Primary sodium in containment, storage tank failure during maintenance 2-4

TABLE 2-2 DESIGN BASIS EVENTS WHICH MAY PRODUCE SEVERE ENVIRONMENTS FOR CLASS 1E EQUIPMENT

8. Failure of ex-vessel sodium cooling system during operation

9. Maximum possible conventional fire

10. Maximum possible internal flood and water spray

11. Safe shutdown earthquake l'2. RAPS surge tank failure (or high pressure pipe from surge vessel) 9 l

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3. QUALIFXCATION BASIS AND IMPLEMENTATION The qualification requirements presented herein are based on applicable General Design Criteria (GDC), Regulatory Guides 1.73,1.89 (as applicable),

IEEE 323-1974, and IEEE 344-1975.

Equipment not subjected to severe accident environments is listed in table 3-1 and qualification procedures for it are discussed in paragraph 4.2.1.

Class 1E equipment subjected to severe environments is listed in table 3-2 and qualification procedures are discussed in paragraph 4.2.2.

Ciass 1E equipment located in ventilated cells in CRBRP' buildings and in the emergency cooling tou.rs may be subjected to a suspended sodium aerosol less than TBD gm/sc) as a result of sodium spills. In addition to sodium aerosol, sodium hydroxide will be considered since it can be fonned from HOLD # sodium oxide in the presence of water. A series of generic tests will be 10002004 performed to verify that equipment will function in sodium aerosol concentra-tions less than TBD gm/cc. This assumption applies to cells such as the control room and to other areas where a sodium spill will not directly result in high aerosol concentrations. ,

No individual qualification testing will be performed for specific Class 1E equipment exposed to sodium aerosol concentrations less than TBD gm/cc.

3.1 Temperature, Pressure, Humidity, Chemical Class 1E equipment will be qualified to the enveloping transient with added margins per IEEE 323 for environmental parameters of temperature, pressure, humidity, and chemical. The margin for the chemical parameter shall be 10%.

Figure numbers for the enveloping transients of each parameter, as it applies to specific equipment, are listed in Table 3-2 and the figures are in Section 2. These parameters will be used in the development of the qualification envelope in accordance with the procedures set forth in Section 4.

3.2 Radia tion The Class 1E equipment will be qualified to the worst case envelope (with IEEE Std. 323 margins) based upon normal service exposure plus the most severe radiation environment predicted to occur prior to and during those portions of the specific accident transients for which the component is required to perform its safety function. Worst case accident parameters ,

are shown in Table 3-2. These parameters will be used in the development of the qualification envelope as described in the procedures of Section 4.

3.3 Vibration The vibration parameter will apply to a few sensors and transmitters which are located on mechanical devices which vibrate due to slight un-balances in rotating systems or on fluid lines which are subjected to vibration will be qualified to that environment per IEEE Std. 323-1974.

Worst case parameters are not shown on Table 3-1, but will be developed on 3-1

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l 3.3 Vibration (Continued) an individual component basis dependent upon the component location. In those instances where vibration is significant, the amplitude and frequency of the vibration will be provided in the equipment specification and the

equipment will be qualified to acceleration 10% greater than that calculated or measured at the mounting point of the equipment. Those equipment items being qualified to the vibration environment will'tue identified in Tables 3-1 and 3-2. I i

3.4 Seismic Qualification to the seismic environment is to be carried out in accordance with IEEE Std. 344-1975, 32?-1974 and WARD-D-0037. Worst case parameters are not shown on Table 3-1 or Table 3-2, but will be developed on an individual component basis dependent upon the component location. Acceleration ,

shall be increased by 10% for qualification per paragraph 6.3.1.5 of IEEE Std. 323-1974. Guidelines for seismic qualification of active valves and pumps are provided in WARD-D-0174. The horizontal and vertical acceleration for the safe shutdown earthquake (SSE) is specified in WARD-D-0037. These ground motions are translated to the component location as described in WARD-D-0037.

4 These ground motions are translated to the canponent location as described in WARD-D-0037. These ground motions are translated to the component location as described in WARD-D-0037 and will be provided in the equipment specification for each item of Class 1E equipment.

3.5 Periodic Pressure Test The reactor containment will be tested with an internal pressure of 11.5 psig one time during containment acceptance tests. During its 30 year lifetime, it will be subjected to nine additional tests at 10 psig per

10CFR50, Appendix J. It is required that 1E equipment in contaimnent remain i

functional after the leak rate tests, otherwise the equipment must be removed during the tests. Analysis, previous operating experience and type testing are acceptable methods for demonstrating that the equipment will remain functional after the leak rate tests. If equipment testing is required, then the tests shall be performed after the equipment is aged. .

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Class 1E: Equipment Not Subjected to Severe Environments TABLE 3-1 (Sheet 1 of 12) ** ,

EQUIPi:ENT LOCATION (RCB Cell Numbers)* MAXIMUM ACCIDENT TEMPERATURE Reactor inlet Pressure Transmitter 1500F .

Reactor Vessel Ha Level Transmitter 105T and HAA Pressure sensor Signal Cond. ,165, 165, 167 120 F Na Flow Senser Signal Cond.

Pump Tachometer Signal Cond.

Reactor Level Sensor Signal Cond.

101 C, 101D, 101E 150up Ha Flow Sensor PRI IHX Outlet Na Temp. Sensor 1 21, 122, 123 150 F Aux. Liq. Metal Valve Operators and 1078, 157D, 157E 150 F .s

, Position Indication g P#i Thermocouples 1078 150"F Cold Trap Thennoccupies . 157A,1578 1500F Primary Makeup Pump Field Cor.t. Panels 105A , 105F 120 F Primary Makeup Pumps 103, 104 o System 81 Local Control Panel 105V 120 F Flux Monitoring CiC, Fission Chamber Preamps HAA _ 1200F .

Compensated Ion Chambers Fission Chamber In Sealed Graphite Housing Located in 0 Detectors Reactor Cavity 120 F Sys. 25 Unit Cooler 25 ARA 021 165 .

120 F

' Sys. 25 Unit Cooler s

25 ARA 022 166 120 F Sys. 25 Unit Cooler 25 /RA 023 167 120 F System 28 Fan Cooler I&C (2) 105L 1500F rnnnectnes A Terminations Various 1500F or 120u F as appropriate

Location of cell numbers within each building may be readily determined from the General Arrangement Drawings. ;

- Identification responsible for of designing IE equipnent that and, equi {ent equipmen . location Shall be under the change control of the systen

TABLE 3-1 (Sheet 2 of 12)

EQ'JIPMENT LOCATICN (SGB Cell Numbers)* f4AXIfiUti ACCIDENT TEMPERATURE PWST Level Instrumentation 215 120 F e -

Emerg. Chiller A 23 ECH 001 216 120 F Emerg. Chilled Water Pump 23 ECP 001 A EI&C Rack A l

Emerg. Chiller B23 ECH 001B Emerg. Chilled Water Pump 23 ECP 0018 217 -

120 F

. El&C Rack 5 MrE 12 NIE 044A ; 273 1200F MCC 12 NIE 050A 271 1200F MCC 12 NIE 0508 247 120 F e

y IHTS Pony Motors 120up

= ARD Brg. Blower / Motor j244,245,246 s.

6 Tachometer 1200F Reaction Products Dump Line Press Switches 241, 242, 243 120 F -

IHTS Floymeter Chan. PM Flow Sensor 227, 228, 230 120 F e _s

Location of cell numbers within each building may be readily determined from the General Arrangement Drawings.

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TABLE 3-1 (Sheet 4 of 12)

EQtJIPMENT LOCATION (SGB Cell Numbers)* MAXIMUM ACCIDENT TEMPERATURE Superheater & Steam Drum Vent Control Valve Operator -

AFW Drive Turbine Steam Supply Isolation Valve Operator ? 241, 242, 243 . 120 F ,

PACC Return Tenp. Inst.

PACC Return Flow Instrumentation AFW Pump Motor & Accessories 204 1200F AFW Pump Recirc. Valve Solenoid Steam Flowneter Instrumentation - 241, 242, 243 1200F

. Steam Drum Level Inst. Rack. 241, 242, 243 120"F .

Feedwater Rack 241, 242, 243 1200F Steam Drum Press. Inst. Rack 241, 242, 243 1200F Sys. 23 I&C Equipment (A) 21 6 120UF y Sys. 23 I&C Equipnent (B) 217 120ur m

^

Sys. 23 I&C Equipment (A) 202A 1200F Sys. 23 I&C Equipment (B) 202B 1200F Sys. 75A I&C Equipnent (A) 216 120 F Sys. 75A I&C Equipment (B) 217 1200F -

Sys. 75A Panel (s) (A) 216 120uF

< 1 Sys. 75B Panel (s) (B) 217 1200F

Location of cell numbers within each building may te readily determined from the General Arrangement Drawings.

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TABLE 3-1 (Sheet 5 of 12) ,

EQud.1ENT LOCATION (SGB Cell Numbers)* NAXIMUM ACCIDENT TEMPERATURE Intermed. Bay Air Handling Unit 25 AGA 204 262 120 F .

Intemed. Bay Air Handting Unit 25 AGA 206 271 120 F .

Emerg.' Chillers Unit Cooler 25 AGA 223A 216 1200F Emerg. Chillers Unit Cooler 25 AGA 223B 217 120 F Intermediate Bay Supply Fans .

25 AGA 244A and 25 AGA 244B 262 120 F .

SGB Unit Cooler '

2$ AGA 237A 272A 120'F ,

SGB Unit Cooler 25 AGA 237B 2728 1200F SGB Unit Cooler 0 25 AGA 237C 272C 120 F Intermediate Bay Supply Fans 25 AGA 249A and 25 AGA 249B 271 120 F-w Intermediate Bay Exhaust Fans 25 AGA 264A and 25 AGA 264B 262 1200F L

k. Intermediate Bay Exhuast Fans 25 AGA 267A and 25 AGA 2678 271 120"F SGB Air Ibndling Unit #1 0 I 25 AGA 201 244 120 F SGB Air Handling Unit #2 i 25 AGA 202 245 120 F 4 _

SGB Air llandling Unit #3

.' 25 AGA 203 246 120 F Auxiliary Feed Pump Unit Cooler s .

25 AGA 221A 204A .120 F 1 Auxiliary feed Pump Unit Cooler i

25 AGA 2218 204B 1200F

!

Location of cell numbers within each building may be readily 'detemined from the General Arrangenent Drawings.

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TABLE 3-1 (Sheet 6 of 12)

EQUIPMENT LOCATI0fi (SGB Cell Numbers)* MAXIMUM ACCIDENT TEMPERATURE Aux. Fr ed Pump Unit Coolers 25 /JA 222A 202A 120 F .

Aux. Feed Pump Unit Coolers 2s AGA 222B 202B 120 F SG8 Cell Supply Fans #1 25 AGA 241 A&B 244 1200F SGB Cell Supply Fans #2 25 AGA 242 AaB 245 1200F SGB Cell Supply Fans #3 0 25 AGA 243 A&B 246 120 F SGB Cell Exhaust Fan

I' 25 AGA 261 A&B 244 120 F _

SGB Cell Exhaust Fans #2 25 AGA 262 A&B 245 120 F SGB Cell Exhaust Fans #3 25 AGA 263 A&B 246 120 F AFW Pump Turbine Controller and Accessories 202 120ur w AFW Drive Turbine Pressure Control Valve

/n Operator 202 _

120 F RCB (Atmos.) Pressure Transmitter 263 120 F RCB (Atmos.) Temperature Transmitter 263 120 F Containnent Isolation System Breaker Pa nels 271, 262 120 F Connectors and Terminations Various 120 F AFW Supply Isolation Valve Solenoid '

' AFW Centrol Valve Motor Operator 202, 206 120 F AFW and AAFW Purrp Inlet Valve Operator ~215 120 F AFW Flow Instrumentation 202, 206 1200F

Location of cell numbers within each' building may be readily determined from the General Arrangement Drawings. _

I .

4.

TABLE 3-1 (Sheet 7 of 12)

EQUIPMENT LOCATION (RSB Cell Numbers)* MAXIMUM ACCIDENT TEMPERATURE 120 F NA Pomo Control Panels 352A. 353A System 81 Local Control Panel 311 1200F 1

EVST Sodium Pumps 357A, 360 150W Loop B EVST Sodium Pump 357A 1500F Loop B EVST Na Valve Field Inst.

- System 28 I&C 360 1350F

- System 28 ISC 357 135"F System 28 Fan Cooler I&C 28 ECA 005B 383 1200F System 28 Fan Cooler I&C 28 ECA 005A 324 120 F System 28 Fan Cooler I&C

'/R FRA nos 325 1200F Y*

System 28 Fan Cooler I&C 120 F 28 EAA 005 306A 0 ABHX Air Conditioning Unit o

'- 25 ASA 104A 327 120 F ABHX Air Conditioning Unit o 25 ASA 104B 326 120 F Connectors and Terminations Vari us 150 F or 120 F as appropriate Aux. Liquid ~ Metal ' Valve Operators and Indicators 357A, 360, 352A, 353A 150 F s

Location of cell numbers within each building may be readily determined from the General Arrangement Drawings.

E' 4

l 1 . .

i

.. + -

TAELE 3-1 (Sheet 8 of 12)

EQUIPMENT LOCATION (RSB Cell Numbers)* MAXIMUM ACCIDENT TEMPERATURE Motor Control Center U 12 NIE 041A 306A . 120 F .

Motor Control Center

-12 NIE C41B 305B 120"F ,

Motor Control Center l 12 NIE 058A 305F 120 F Motor Control Center n 12 NIE 058B 305E 120 F i Unit Sub-Station i

12 NIE 032A 305F 120 F .

, . Unit Sub-Station 12 NIE 0328 305E 120 F '

Annulus Pressure Main Fan

, and I&C 25 ARA 172A 398 120F) 0 I&C 25 ARA 173A 398 120 F

- i I&C 395 .120 F y HOLD # 10002005 w- f 25 ARA 172B I&C

, g 25 ARA 173B 395 120 F I 4

tl Annulus Filter Cell Coolers **

o 25 ASA 132A 398 120 F

- l

. Annulus Filter Cell Coolers 25 ASA 132B 395 120 Ff

. k I

i < 7

Location of cell numbers within each building may be'readily determined from the General Arrangement,7tayings. '

. **This equipment functions to mitigate the SSST release. (See OPDD-10, Seccion 7.8.2.4 for source magnitude.) .

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TABLE 3-1 (Sheet 9 of 12) ,

EQUIPMaiT LOCATION (CB Cell Numbers)* MAXIMUM ACCIDENT TEMPERATURE l i 125 VDC Distribution Panel 4 i 120 V Vital A-C Buses -

480 V A-C Battery Chargers 454, 459, 460 120 F 120 V A-C Inverters 480 V-120V Vital Reg. Transfonner ,

f '

125 V D-C Batteries 451, 453, 458 120 F 250 V D-C Batteries 452 120 F -

i

! - 480 V Motor Control Center i 12 NIE 042A 413 1200F ,

I 480 V Motor Control Center

. 12 NIE 0428 412 1200F Control Room INAC Monitors 431 120 F i

I' System.23 EC Main Control Room Panels 431 1200F Y System 75 EP Main Control Room Panels 431 1200F

-f

k. Control Room A/C Unit '

j 25 ACA 410A 410A 1200F

Control Room A/C Unit

! 25 ACA 411A 411 A 1200F

! SER A/C Unit A

! 25 ACA 411 413 120 F i I' SER A/C Unit B 25 ACA 412 412 120 F l System 99 Main Control Room Cabinets 431 1200F 1 < ,

PAM and Safety System Control Room Panels 431 1200F

!

Location of cell numbers within each building may be readily determined from the General Arrangement Drawings.

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. . . , . . . - , . . - . . ~ - . . . .- . . - . - , , -

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TABLE 3-1 (Sleet 10 of 12)

HAXIMUM ACCIDENT TEMPERATURE EQUIFMErlT LOCATION (CB Cell Numbers)*

1 Control Room Return Fan 110 F _

25 ACA 451A 410A Control Room Return Fan 110 F 25 ACA 451B 411A _

j SWGR Rt. turn Fan A 120 F 25 ACA 452 413 o

' SWGR Return Fan B 120 F 25 ACA 453 412 l

~

j Battery #1 Room Exhaust Fan 120 F ,

s 25 ACA 461 412 Battery #2 Room Exhaust Fan 120 F ,

j 25 ACA 462 413 _

y Battery #3 Room Exhaust Fan 0 120 F 25 ACA 463 413 Battery Room Exhaust Fan 1200F 25 ACA 464 412

- 110 F l / Control Room Filter Fan 4108 f 25 ACA 441A 4

" I ** 110 F L Control Room Filter Fan 411B .

, g ru / 25 ACA 441B

- o k MOLO f 10002005 Control Room Filter Unit 4108 110 F

' 25 ACA 471A

- o Control Room Filter Unit I 110 F j I 411B

( 25 ACA 471B #

Various 120 F or 110 F as appropriate Connectors and Terminations 455, 457 120 F Pri. Pump Under Voltage Sensors l

, 7 i

Location of cell numbers within each building may te readily determined from the General Arrangement Drawings.

- This equipment functions to mitigate the SSST release. (See OPDD-10, Section 7.8.2.4 for sourte magnitude.) .

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i TABLE 3-1 (Sheet 11 of 12)

MAXIMUM ACCIDENT TEMPERATURE EQUIPHENT LOCATION (DGB Cell Numbers)*

Diesel Generators (12NIE022A, B)

Diesel Gen. XFMR & Resistors (12NIE002A, B) 511, 512 '120 F 480 V Unit Sub-Stations 521 120 F 12 NIE 027A & 12 NIE 028A 480 V Unit Sub-Stations 120 F 12 NIE 0278 & 12 NIE 0288 522 I 4.16 KV SUGR 521 120 F-12 NIE 003A

" 4.16 KV SWGR 120 F 12 NIE 003B 522 I Motor Control Center 120 F .

12 NIE 040A 521 ,

l Motor Control Center 120 F 12 NIE 040B 522 511 1200F I 12 NIA001A, C k

512 ' 120 F

,4 ! 12 NIA001B, D -

I .L Fuel Oil Transfer Pumps W 526 120 F g 12 NIP 001A and 12 NIP 001C -

' Fuel 011 Transfer Pumps s'

527 1200F 12 NIP 001B and 12 NIP 001D System 75A 0 120 F I&C Equipment (A) 511

+

System 75A 120 F I&C Equipment (B) 512 j #

Various 120 F Connectors and Terminations

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Location of cell numbers within each building may b'e readily determined from the General Arrangement Drawings.

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i-f *$ Class lE: Equipment Subject *

! to Severe Envircratants TABLE 3-2 (Sheet 1 of 4) (4)

RCB FIGURE NUMBERS OF ENVELOPING ENVIRONMENTAL TRANSIENTS OR MAX VALUES b}

CLASS lE EQUIPMENT CELL

NUMBER (2) TEMPFRATURE PRESSURF HUMIDITY RADIATION CHEMICAL Primary RSS Cable HAA and Above Oper- '

s ating Floor 2-1 2-2 _ 2-3 _4 c- -

Secondary RSS Cable HAA and Above Oper-ating Floor 2-1 2-2 _

2-3 2-4 CIS Valve Actuators (1) 2-1 2-2 2-3 2-4 Radiation Monitors and Cable Various _

PHTS Pony Motors ARD Brg. Blwr./Mtr. and Cable 161C,1610,161E 2-1 2-2 - 2-3 2-4 Primary Pump Tachmieter 161C,161D,161 E -

2-5 -

2-6 -

i 2

. RCB Pressure Sensor Above Operating Floor ~

2-1 2-2 2-3 2-4 _

RCB Temperature Sensor Above Operating Floor 2-1 2 -

2-3 2-4 i -

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.g Connectors and Terminations Various t3

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. -(1)rhis equipment functions to mitigate the SSST release.

(2 location of cell numbers within each building may be readily detemined from the General Arrangement Drawings.

i (3) Consistent with enviromental transients for equipment utilizing connectors / terminations. ~~

(4) Identificaticn of Class IE equipment and, equipment location shall be under the change control of the i system responsible for designing that puipment. .

(5) Components which wijl be qualified to vibration environments will be indicated on this table at a ,

! later date. .

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TAB.LE 3-2 (Sheet 2 of 4) f t

1 SGB LIGURE NUMBERS OF ENVELOPING Eff>IRONMENTAL TRANSIENTS OR MAX. VALUES ,

7 CLASS lE EQUIPMENT CELL

, FRNBER** TEMPFRATIfRF pRFSSilR F HtNIDITY RADIATION CHEMICAL i

t 4 l Steam Flowneter 241,242,243,244,245, 2-7 2-8 100% - -

, 246 Superheated Steam 241,242,243 2-7 '2-8 100% - -

l .

Temnerature Sensor j -

Superheated Steam 241,242,243 2-7 2-8 '100%, - -

1 Pressure Sensor Steam Drum 241,242,243,244,245 2-7 2-8 100% - -

] 246 f

Level Sensor Feedwater Flowneter 241,242,243,244,245, 2-7 '2-8 100% - -

246 .l Feedwater Temperature Sensor 241,242,243 100% - -

{ 2-7 24

! w a Steam Drum Pressure 241,242,243 100% - ;

2-7 2-8 ,

$ Sensor and Instrumentation d

^ '

RSS/SGAHRS Cable Various 2-7 2-8 100% - -

i j Evap. Outlet Sodium 244,245,246 100% - -

Temperature Sensors 2-7 2-8 '

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! **Locatien of cell numbers within each building may be readily determinedfrom the General Arrangement Drawings.

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TABLE 3-2 (Sheet 3 of 4)

SGB FIGURE NLNBERS OF ENVELOPING ENVIR0tHENTRL TRANSIENTS OR MAX. VALUES CLASS lE EQUIPMENT

~

CELL HUMBER** TD4PFRATURE PRESSURF H!NIDITY RADIATION CHDtICAL Feedwater Inlet Isolation Valve Operator 241,242,243 2-7 2-8 100% - -

Superheater Outlet Isolation 2-7 28 Valve Operator 241,242,243 100% - -

Steam Drum Drain Isolation .

Valve Operator 241,242,243 2-7 2-8 100% - -

207,208,209,221, Cell Humidity Sensor 222,223,224,225,22 6 2-7 2-8 100% - -

Cell Temp. sensor 241, 242, 243 2-7 2-8 100% - -

244. 245. 246 l .-

Connectors and Terminations 241,242, 243 244,245, 246 2-7 2-8 100% - -

Y -

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. ** Location of cell numbers within each building may be readily determined from the General Arrangement Drawings.

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TABLE 3-2 (Sheet 4 of 4)

RSB FIGURE NUMBERS OF ErlVELOPING ENVIR0fNENTAL TRANSIEtiTS OR MAX. VALUES -

CLASS lE EQUIPMENT CELL MUMBER ** TPJPFR ATUR E PREssitPE HUMIDITY RADIATION CHEMICAL Loop A EYST ABHX Fan Motor, i flak Pump Field Control Panels, f352A

- - - 2-9 -

ABHX touver Solenoids 'i fia&NaK Valve Solenoids Inst. .

EVST Na Lyl. & Temp. Transmittery Loop B EVST ABHX Fan Motor, flak Pump ,

Field Control Panels '(353A - - -

2-9 ABHX Louver Solenoids l Na& flak Valve Solenoids ,-

EVST fia Lvl. & Temp. Transmittersi Cable Various - - - -

2-9 -

Connectors and Terminations 2-9 t .

y, _

.L -

oo i.

- Location of cell numbers within each building may be readily determined from the General Arrangement Drawings.

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4. QUALIFICATION PROCEDURES 4.1 CRBRP Class 1E Equipment The design basis accident environment is significantly different from the normal environment in selected cells affected strongly by accidents.

Consequently, Class 1E equipment located in these cells must be aged and qualified to the severe accident environments per paragraph 4.2.2. Other Class 1E equipment which is not subjected to severe accident environments i may be qualified by any one or an appropriate combination of the several ways of meeting the requirements of IEEE 323, such as type testing, (Sections 4.2.1,4.2.2) operating experience (Section 4.2.4) or analysis (Section 4.2.5). The results of the qualification procedure are to be recorded per IEEE 323-1974 (see Appendix A for an illustration of format).

The cognizant engineer preparing an Equipment Specification for any piece of Class 1E: equipment will determine whether it is to be qualified according to paragraph 4.2.1, 4.2.2, 4.2.3 or 4.2.4. Each piece of Class 1E equipment must be qualified for operation during that portion of the applicable transients during which it must perform its safety function. The cognizant engineer must specify the choices, if any, which are being passed to the vendor. In each instance the cognizant engineer must specify the require-ments for qualification. He must determine the time interval during which the particular Class 1E equipment must perform its safety function. IEEE 323 requires that 10% be added to this time interval for margin. If(for example), the equipment appears in Table 3-1 and will be qualified by type test, the cognizant engineer rust roecify this type test in accordance with the procedures of paragraph 4.2.2. He must also specify that the records of these tests be prepared in such form as to meet the auditable documenta-tion requirements of IEEE 323-1974. An illustration of acceptable documentation is given in Appendix A.

4.2 Specific Procedures 4.2.1 -

QUALIFICATION PROCEDURES FOR CLASS 1E EQUIPMENT NOT SUBJECTED TO SEVERE ACCIDENT ENVIRONMENTS

Class 1E equipment in this category is not subject to severe accident environment qualification. This equipment will be qualified to the l temperature, humidity, voltage and frequency conditions defined in Figure l

4-1 by operating experience (4.2.3) analysis (4.2.4) or the type test described in this paragraph. When size or other practical requirements t

limit type tests, this part of the qualification may be completed by a combination of partial type tests with extrapolation or analysis.

Equipment subjected to this type test shall have first passed all other E-Spec acceptance tests. The type tests shall be performed in numerical order to meet the requirements ofIEEE 323 paragraph 6.3.2. Also, any item being type tested shall undergo the complete set of tests described below.

4-1 l

1. Pre-Operational Tests: Visual examination, dieletric and insulation resistance tests followed by interconnection to function as a complete working system. Dummy input signals and loads shall be provided as required to perform simulated system operation. Electrical inter-ference tests shall be performed as defined in equipment specification. ,,

2. Functional Tests: Verify that the equipment performs its safety function; e.g.: Inject test signals and determine that logic computation is correct; relay operates; bistable operates and set-points are correct.

3. Aging: The methods to be used to satisfy the requirements to age equipment in non-severe environnents will be determined when sufficient information is available from the LWR industry. It will be the policy of the CRBRP environment qualification program to utilize the aging methodology of the LWR industry, as applicable to the CRBRP, once the aging requirements are better defined by NRC and the LWR procedures

developed. Acceptable methods for aging by analysis, previous experiene: e testing or a combination of these will be developed.

4. Burn-In Test (Determination and evaluation of infant mortality):

After completion of the initial system tests, the system shall be energized for a minimum of 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at nominal voltage under room temperature conditions to assist in the detection and elimination of components subject to early failure. The operation of the system shall be checked during the burn-in test as outlined below, and by complete operational test perfonned at the completion of the test.

Periodically, during the burn-in tests, functional performance of the equipment shall be verified. The time between periodic tests shall not exceed 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months . Any malfunction observed during this test shall be cause to interrupt the test, evaluate the cause of failure, and repair the malfunction. If the malfunction is repairable, the repair may be performed and the test continued. Any repaired component should be reinserted into the system at the next periodic check. The

- test time shall be extended beyond 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months as required to insure,

at the completion of the test, that all components initially installed I have been energized for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , and all components replaced as a result of malfunction have been energized for at least 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months . ,

No requirement for design modification is cnticipated in this phase

! of the qualification. However, if the need should occur, the modifica-tion will be in accordance with IEEE-Std. 323-74, Section 6.8. *

5. Operational Tests: Verify that the equipment meets the electrical requirements of its performance specifications, including static and dynamic calibration.

l 6. If required, a pressure test will be performed in accordance with Section 3.5.

4-2

7. Environmental Tests: Environmental testing shall be performed according to Figure 4-1. Equipment shall be mounted in a manner and a position that simulates its expected installation when in actual use unless an analysis can be performed and justified to show that the equipment's performance would not be altered by other means of .

mounting. The equipment, with all electrical loads and inputs properly simulated, shall be placed in an environmental test ;

chamber capable of providing concurrently the conditions defined by the curves. Complete instrumentation shall be used to permit continuous monitoring of the environmental conditions. The equipment shall be energized throughout each test cycle as indicated by the figure. Input / output simulation shall be t. sed to provide the capability to test the equipment for proper operation during and af ter the test cycles. The test chamber conditions shall be stabilized for a minimum of two. hours prior to the start of any test cycle. The tolerances on the steady state test chamber conditions are to be added to the temperature and relative humidity '

ranges with appropriate sign to be sure that the specified ranges are accomplished by the test.

Functional tests (Test 2) shall be performed at the beginning 'of the -

test and at the end of each cycle. Eight hours (maximum) between cycles is recommended for testing, repair and to establish the new test chamber conditions for cycles 1 through 4. The test chamber conditions shall be established in 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months maximum except for the last cycle as defined below. After cycle 4 is completed, including the functional test, the equipment is to cool slowly to room temperature and humidity.

g, Seismic Tests: After completion of the applicable portion cf the above tests, the Class 1E equipment shall be seismically qualified in accordance with IEEE Standard 344-75 and WARD-D-0037. performance shall be monitored during the seismic qualification and the functional tests performed to demonstrate that the equipment can perform its safety function.

1

9. At the conclusion of each test series, any malfunctioning components l shall be examined to determine the cause of malfunction by a complete failure analysis. Replacement of the component with one having suitable characteristics or redesign of the assembly shall be pursued if shown to be necessary by the failure analysis. ,

10*

The test report shall contain the technical information required to satisfy IEEE Std. 323-1974.

4-3 l

L - ._

11. In the evaluation of the qualification test results, any sample equipment is considered to have failed when the equipment does not perform the Class 1E functions required by the equipment specifications. .

I e

i 4-4 l

)

4.2.2 CLASS 1E EQUIPMENT SUBJECTED TO SEVERE ACCIDENT ENVIRONMENTS -

Class 1E equipment which is subjected to severe accident environments during the time interval in which it must perform its safety function, will be qualified per paragraph 4,2.3, 4.2.4 or by type test as described in the following paragraphs, or a combination of those methods to the environments defined in Table 3-2. When size or other practical requirements limit type tests, this part of the qualification may be completed by a combination of partial type tests with extrapolation or analysis.

If the equipment is a large rotating machine, it may be qualified by a l combination of analysis, motorette testing and type testing. The procedure will meet the requirements of. IEEE 117-1974 for random wound coils or IEEE i 275-1966 for form wound coils, and will conform to the requirements of IEEE 323-1974 and IEEE 334-1974, and will meet the applicable requirements of '

Regulatory Guide 1.40. The motorettes will be thermally aged, irradiated and subjected to the appropriate accident ervironments as shown in Figure 4- 2.

Qualification requirements for valve operators, in addition to those defined in this docunent, are defined in Regulatory Guide 1.73 and IEEE 383-1972.

Equipment subjected to this type test shall have first passed Equipment Specification acceptance tests. The type tests shall be performed in numerical order t' meet the requirements of IEEE 323-1974, paragraph 6.3.2.

Also, any item being type tested shall undergo the canplete set of tests described below:

Type Test Procedures are as follows:

1. Pre-operational Tests: Visual examination, dielectric and insulation resistance tests followed by interconnection to function as a complete working system. Dummy input signals and loads shall be provided as required to perform simulated system operation. Electrical interference tests shall be performed, where applicable, according to the equipment specification. .

2. Functional Tests: Verify that the equipment performs its safety function; e.g.: Inject test signals and determine that logic canputation is correct; relay operates, bistable operates and set-points are correct.

3. Thermal A Operate the equipment (or motorette representing motor windings)ging:at elevated temperature for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months as shown in Figures 4-2 and 4-3 and explained in paragraph 4.2.2.1.

4. If required, a pressure test will be performed in accordance with Section 3.5.

4-5

5. Operational Tests: Verify that the equipment still meets the electrical requirements sp(ecifiedisinmost Figure 4-1 or thoseincluding specified in itsand performance specification whichever conservative), static dynamic calibration (if applicable).

6. Seismic and Radiation Tests: Class 1E equipment shall be seismically qualified in accordance with IEEE Standard 344-1975 and WARD-D-0037. ,

The Equipment Specification shall specify the seismic frequencies and accelerations plus the IEEE 323-1974 margins for acceleration.

If the specific equipment is subjected to vibration due to fluid turbulence or machine unbalance, this information is to be provided and a vibration test included with the seismic and radiation tests providing the equipment cannot be shown by analysis or operating experience to be un-affected by the vibration.

Performance shall be monitored during these tests and the functional tests performed to demonstrate that the equfpment can perform its safety function. The radiation dose shall be applied at this point in the test sequence unless it can be shown that a more severe test results from a different sequence.

The dose shall be the sum of normal exposure for 30 years (from Table 2-1) plus the dose resulting from the DBE (from Table 3-2) plus 10% of the DBE dose (per the dotted curve). The details of seismic and radiation tests shall be included in the Eauipment Specification for the specific Class 1E equipment.

7. Margin Transient: The Class IE equipment will be mounted in a temperature controlled test chamber and subjected to a transient to the peak accident temperature plus the IEEE 323-1974 temperature margin of 15 F. The accident temperature will be the maximum temperature to which the equipment is exposed (according to Table 3-2) during the time interval in which it must perform its safety function. This information shall be supplied in the Equpment Specification for specific Class 1E equipment.

8. DBE Transient: Maximum temperature, pressure, humidity, and chemical values as applicable (Table 3-2) will be taken from the appropriate portion of the (dotted curve) parameter transients (Figures 2-1 to 2-11).

The Class 1E equipment shall be exposed to that portion of the accident transient (from Table 3-2) during which the equipment must perform its safety function for a time of 110% of this interval (the IEEE 323-1974 time margin). .

9. At the conclusion of each test series, any malfunctioning components shall be examined to detennine the cause of malfunction by a complete failure analysis. Replacement of the component with one having suitable characteristics or redesign of the assembly shall be pursued if shown necessary by the failure analysis.

10. The test report shall contain the technical information required to satisfy IEEE Std. 323-1974.

4-6

l l

l

11. Post Accident Aging: Some Class 1E equipment will be required to operate for a significant time interval following the termination of the accident.

Figure 4-2 shows that the Class 1E equipment will next be exposed to this aging condition for a minimum of 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months at a temperature to be determined from Figure 4-3. The temperature and time for post accident aging are to be specified in the Equipment Specification if this function '

is required. I

12. In the evaluation of the qualification test results, any sample equipment j is considered to have failed when the equipment does not perform the i Class 1E functions required by the Equipment Specifications. l 4.2.2.1 Simulated Aging This sub-section applies to Class 1E equipment subjected to severe accident environments.

The CRBRP Project aging method assumes that the assemblies of components which make up each piece of equipment will be, in effect, many different insulation systems. Each of these systems will have sane aging characteristics (dependent upon its insulation material) which will range from the "non-aging" characteristics of some ceramics to the characteristics of electrolytes in 0

capacitors which double their aging rate for 6.9 F increase in temperature.

When testing an assembly, the increase in temperature to double the aging rate will be taken from the insulator in the assembly which requires the largest temperature increase to double its aging rate. If insulators are involved in one assembly that have very different aging characteristics, it may be necessary to remove some components, " age" them separately, and then reassemble.

The aging simulation for mechanical stress, electrical stress and cyclic operations will be conducted and evaluated as follows. An arbitrary normal life for the module or assembly will first be assumed. (typically 30 years or as otherwise specified in the equipment specification. The module or assembly will be aged to this assumed normal life. If an assembly contains one or more items that are clearly in the category of replaceable elements (such as some electrolytic capacitors), the projected qualified life of these items is to be determined and they are to be listed as replaceable elements and their replacement schedule is to be specified in the EQDP. If the module or sub-assembly successfully completes the aging procedure and the following environmental tests without failure, the projected qualified life will be the assumed nonnal life. If the module or sub-assembly fails the simulated aging or the following environmental tests, attempts may be made to achieve

a redesign which can pass the tests. If it is impractical to change the 1

cesign, new " aging" tests may be run for a shorter " aging" interval and, if the following environmental tests are canpleted satisfactorily, the projected qualified life of the sub-assembly will be determined by the maximum " aging" interval achieved. Equipment modification, if required, will be in accordance with IEEE Std. 323-1974, Section 6.8. If this procedure proves to be impractical, the equipment may be aged by a combination of analysis, test, and available data concerning aging rates for specific types of insulating material.

4-7

9 4.2.3 Operating Experience A very large amount of equipment qualified to earlier criteria is presently

- operating successfully in nuclear plants.

Another experience source is that of equipment features such as insulation systems, lubricants, bearings and so forth, previously qualified for applica-tion in PWR designs and BWR designs, but now designed into CRBRP equipment.

The CRBRP Project plans to use this experience where available and applicable.

Operating experience will apply to Class IE equipment located throughout CRBRP buildings. Qualification by operating experience shall meet the requirements of IEEE 323-1974, paragraph 6.4.

4.2.4 Analysis Analysis can also be employed as the primary method or to supplement other methods as appropriate. In particular seismic analyses of large rotating apparatus will be employed. Analysis can apply to Class IE equipment located throughout CRBRP buildings. Qualification by analysis shall consist of a mathematical or logical demonstration that Class 1E equipment can meet or exceed its safety requirements under worst case conditions. An analytical approach to qualification may be used when extensive operational experience and/or manufacturer test data, which is applicable to CRBRP DBE's or accident environment, exists for the same or similar equipment. Analysis may also be used to establish the aging characteristics of some types of Class 1E i equipment whose components can be classified into groups such as ceramics, copper, pvc insulation, varnish or rubber (for example) whose aging characteristics are known from large quantities of research and development data. Qualification by analysis shall meet the requirements of IEEE 323-1974, paragraph 6.5.

4.3 Qualified Life ,

l The CRBRP Project will determine a projected qualified life based on the i results of the qualification procedures described throughout this report The maintenance and refurbishing procedures employed, as well as many other factors, affect the useful life of the equipment under consideration. The projected qualified life validity will, therefore, also depend on these -

procedures. To enhance this validity, the CRBRP Project will also assure that its manuals, and operating and maintenance instructions are current, definitive and accurate. j i .

l- 4-8 L

l

HOLD OMAX- ' - - - - - -

NOTES:

O = AVERAGE NORMAL VALUE 6 -- T EMPE R ATURE FROM TABLE 2-1 1

@ = MAX VALUES FROM TABLE 3-1 I

HOLD 55 F + 0%

I i i I i i i i I l I I l I l TYPE TEST PER PAR. 4.2.1 ,

85% (OPERATION IN FOUR DIFFERENT I

STATES OF 48 HOUR TOTAL DURATION) 1 WILL BE PERFORMED AS SliOWN.

g Tile VERTICAL LINES BETWEEN THE HUMIDITY FOUR DIFFERENT STATES MAY REPRESENT g AS MUCil AS 8 HOURS FOR ANY NECESSARY i

10%

,-- g REPAIR AND FOR TIME TO CHANGE l l 1 l TEST CHAMBER CONDITIONS.

[

-+- 12+ -*- 12+l + 12+1 +12+l p ]

HOURS

- 1 I l I i

110% ,

VOLTAGF- i NOMIN AL 100%

. I 90%

l l l l l l 1 1 I l

l 1 I i l G3 Hz g FIGURE 4-1 g

ENVIRONMENTAL TEST I I FOR EQUIPMENT NOT SUBJECTED FREQUENCY TO SEVERE ACCIDENT ENVIRONMENTS 60 IlZ 57 Hz ------

4-78 P01321-14-1 a

- O

I FIGURE 4-2 CUALIFICATION ENVELOPE FOR EQUIPMENT LOCATED IN SEVEllE ACCIDENT ENVIRONMENTS i

- RADIATION (1) AND/0R SEISMIC

+ : AEROSOL TG SIMULATE Na FIRE -

, VillERE APPROFRfATE

+ + M- ; ; P C E

< AIR STE M ST EN I Pjf EP '

HOT G AS IIOT G AS PER TABLE 3-2 PER TABLE 3-2 i .-

m 7

~

. I I i

I E-m '! l l ti i I l 5 I I l

4 % i i

! Ei lTRANS. l H I SIMULATED l '

! SIMULATED FOR i NORMAL EXTRA l ACCIDENT I I SIMULATED POST ACCIDENT i AGlHG MARGIN g COND!TIONS AGING i

g l (2)

I i I j - ! I I I

^

I I I

, { 1 1 1

,e i I g F

i I i a -e e i e I I l I I I l 0 100llRS MINIMUM TIME i . -

i,o QUALIFICATION NOTES (See Figure 4-2)

The following notes supplement the test sequence information shown in , ,

Figure 4-2.

1. The simulated normal aging time-temperature profile may optionally be .

modified according to the curve by Figure 4-3 which is a plot of the equation.'

1/P =2 X P = simulated aging period (hours) ,

X' = number of Y F steps that the aging temperature is above normal ambient for the test item Y = Change in temperature required to double the aging rate for the materials in the assembly which requires the largest temperature , change to halve its life. (See Table - pg. 4-13)

L = required test item life (hours)

Simulated. normal aging time shall not be less than 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months . Equipment shall be continually energized during the aging test unless it can be -

shown that aging in the deenergized state is more severe. Simulated post accident aging may also be optionally modified according to Figure 4-3. >

2. Required by IEEE Std. 323-1974, page 16. The peak temperature dwell time shall be one minute minimum.

4-11

fV . -

104 == FIGURE 4 3

~

AGE ACCELERATION VS TEMPERATURE 103

{ .

E ~

t

?-

E u.

z S 102. :

5 -

5 Z d -

1 y -

~

NOTES:

1. EACH SENTS Y FfEMPERATURE STEPNOR-ABOVE THE AVERAGE REPRE-f 101. -

MAL AMBIENT (EOR THE EHulPMENTBEING A

~

2. EQUIPMENT SHALL BE ENERGlZED .

~

l DURING AGE SIMULATION.

3.THE MINIMUM AGING TIME SHALL

~

i BE 100 HOURS FOR ANY TEMPERATURE.

1 2 3 4 5 6 7 8 9 10 11 12 13 TEMPERATI.lRE STEPS ( X )

! i 1

[

l 4-12

l I

Table of "Y" Valves for Typical Materials of Class 1E Assemblies , .

TEMPERATURE' INCREASE TO HALVEg0MPONENT SOURCE DESCRIPTION LIFE ( F)

MILHDBK 217A Vinyl-Nylon Wire 11.1 Type 1 Silicone Wire 28.4 FEP Wire Type K 13.7 McGrath, T. J. Resistors 12.8 ,

Aging of Class 1E Modules, Paper IEEE Capacitors 6.9 4 Nuclear Power System. Symposium Transistors 25.0 Dec.12, 1974 T. W. Dakin, E.H. Henry, Polyester Amide Wire 28.0 and G. A. Mullen " Life Enamel, Kraft Paper Testing of Electronic. Layer Insulation Power Transformers, Part Power Transformers II, IEEE Transactions on Electrical Insulation, Vol . El-3, No.1, Feb.1963 AIEE Std.1 (now IEEE-273)

Standard Handbook for

- Electrical Engineers, ninth Edition, McGraw Hill Book Co.

Section 4-382,385(6) Transformers 12.6 to 18 Class A Insulation 21 .6 4-13

, n - - . , , . <.,n. ., . , . , - . . , - . . ~ . . . , , . , , , , , . . , , , . . ,,n. .,w. .

I -

1 e

l l

5. DOCUMENTATION OF QUALIFICATION I The overall documentation plan will consist of this generic interpretation l parent docunent and a series of supplements, or " Equipment Qualification ,

Data Packages." One date package supplement will be submitted for each l piece of Class IE equipment or system as applicable upon successful qualifi- !

cation of the candidate equipment. This package provides the "Auditable I Link" required by IEEE Std. 323-1974. i l

The preferred Equipment Qualification Data Package format is illustrated in j Appendix A. i Any format which meets the requirements of IEEE 323-1974 is acceptable.

4 5-1

r 2 i

1 e.

ACRONYMS ,

ABHX. Air Blast Heat Exchanger- ,

A/C Air Conditioning .

AFW Auxiliary Feedwater-AFWS- Auxiliary Feedwater System CAPS . Cell Atmosphere Processing System CB Control Building CIC Compensated Ion Chamber ;

CIS Containment Isolation System CRBRP Clinch River Breeder Reactor' Plant DBE Design Basis. Event'

'DGB Diesel Generator Building EVST Ex-Vessel Storage Tank

- FHC Fuel Handling' Cell

' HAA Head Access Area HVAC- Heating Ventilating and Air Conditioning IEEE The Institute of Electrical and Electronics Engineers, Inc.

IHTS Interediate Heat Transport System 'k PACC Proteicted Air Cooled Condenser PAM Post Accident Monitoring , ,

PPS Plant Protection System PHTS Primary Heat Transport System PWST Protected Water Storage Tank ,

. RAPS Radioactive Argon Processing System RCB Reactor Containment Building RSB- Reactor Service Buildi,ng -

RSS Reactor Shutdown System

ACRONYMS SGB Steam Generator Building .

SGAHRS Steam Generator Auxiliary Heat Removal System SSE Safe Shutdown Earthquake SSST Site Suitability Source Term l

l l

l

/

~

LIST OF REFERENCES (1) IEEE Std. 117-1974, " Systems of Insulation Materials for Random-Wound A/C Electric Machinery, Std. Test Procedure for Evaluation Of". '

(2) IEEE Std. 275-1966 (R-1972), " Systems of Insulation Materials for A/C Electric Machinery Employing Form Wound Pre-Insulated Stator Coils, Test Procedure for Evaluation Of".

(3) IEEE Std. 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations", February 28, 1974.

(4) IEEE Std. 323A-1975, " Supplement to the Foreward of IEEE Std. 323-1974".

(5) IEEE Std. 334-1974, " Standard for Type Tests of Continuous Duty Class 1E Motors for Nuclear Power Generating Stations".

(6) IEEE Std. 344-1975, "IEEE Recorrmended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations".

(7) IEEE Std. 382-1972, " Trial Use Guide for the Type Test of Class 1 Electric Valve Operators for Nuclear Power Generating Stations",

April 10, 1973.

(8) IEEE Std. 383-1974, " Standard for Type Test of Class IE Electric Cables, Field Splices and Connections for Nuclear Power Generating Stations".

(9) Regulatory Guide 1.89, " Qualification of Class 1E Equipment for Nuclear Power Plants", November,1974.

(10) Regulatory Guide 1.73, " Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants", (1/74).

(11) Regulatory Guide 1.40, " Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants",

(3/16/73).

(12) Best, Brotts, McLean, and Lampart, " Determination and Application of Aging Mechanisms Data in Accelerated Testing of Selected Semi-Conductors,

, Capacitors, and Resistors, ' Nations! Symposium on Reliability and Quality -

Control 1965'", p. 293-302.

! (13) Reynolds, Fredrick H., " Thermally Accelerated Aging of Semi-Conductor Components", IEEE Proc. Vol. 62 No. 2, Feb. 1974 (14) Wakefield Engineering Inc., " Guideline on Component Burn-In Technology".

(15) Rabinowica, E., "McEntire R. , and Sireklar B. , " Technique for Accelerated Life Testing", ASME Transactions, August,1970.'

(16) Steck and Zimmer, Sandia Labs and New Mexico University, " Estimation of Acceleration and Aging Functior.s",1972.

(17) Wiksten, D. et.al . , Jet Propulsion Lab. " Accelerated Life Testing of Spacecraft Subsystems", November, 1972.

e l

I l

m APPENDIX A SAMPLE i

EQUIPMENT QUALIFICATION DATA PACKfiiE i

l A-1 .

i 9

,-- r_ ,-n- - -- e >---

h.

. . CRBRP PROJECT Oak Ridge, Tennessee.

EQUIPMENT QUALIFICATION DATA PACKAGE COVER SHEET

(

L This cover sheet shows the revision status of the other sheets of the qualification data package. It is revised when any other sheet of the package is revised.

PAGE REVISION . APPROVALS Y

l e

EQUIPMENT ISSUED LAST REVISION t

PAGE OF PAGES i

A- 2 [

..._.,.,..,__.,m..__. _ . . . . . _ . , . . . _ _ . _ . . , , , _ , . _ . , _

~

'y'4 EQUIPMENT QUALIFICATION DATA PACKAGE ,

FORMAT r

The " Equipment Qualification Data Package (EQDP's) is intended as an outline for the documentation of methods utilized to qualify safety related electrical equipment in a systematic and auditable form. The package is organized in five parts: (1) Equipment Identification; (2) Performance Specifications; (3) Qualification by Test; (4) Qual- ,

ification by Experience; and (5) Qualification by Analysis. Parts 1 and 2 are required for each qualified safety class component (or camponent with attached safety class auxiliary devices). In addi-tion, Parts 3, 4 and 5 should be completed as applicable.

I I

l I

1 A-3

4 EQUIPMENT QUALIFICATION DATA PACKAGE (PART 1 - IDENTIFICATION)

EQUIPMENT BEING QUALIFIED

'Name:

Manufacturer's Identification Number:

(

-Design Specification Number:

c Rev.

r Unusual Design Features of the Equipment (if any):

f If this equipment was qualified by type test and failures during the type test resulted in design changes, describe the failure analysis ,.

and the changes and provide the new manufacturer's Identification Num-ber below:

5 I

i i

F A-4

. . . - , . . _ , . . . . ~ - _ . . . _ , _ _ . . . . . . ..._. . . . . . . . , . . . _ _ _ . . _ . . _ . . . _ . . _ _ _ . _ , . , . . . . , _ . . , . , . . _ _ _ _ . . .

EQUIPMENT QUALIFICATION DATA PACLsuE (PART 2 - SPECIFICATIONS) l

.l 1.0 PERFORMANCE' SPECIFICATIONS l 1

1.1 Electrical Requirements 1.1.1 Voltage i

1.1.2 Frequency 1.1.3 Load 1.1.4 Electromagnetic Interference 1.1.5 Other 1.2 Installation Requirements ,

1.3 Auxiliary Devices (l)

L 1.4 Preventative Maintenance' Schedule 1.5 DesignLife(2) 1.6 Operating Cycles (3) 1.7 Performance Requirements (4)

! 1.7.1 Normal ,

1.7.2 Abnormal 1

-r 1.7.3 Containment Test ;

1.7.4 DBE j t

1.7.5 Post DBE I

PAGE OF __

i A-5

.. . . . . ~ . . - - . - - , , . . . . , , - - . . . , . - . . . - , . , - . . , . - , , , . . . , - - . . . . . . . . , - . - . . . _ , , _ , . . . . , - , , - ~ . . . - . . . - , . - .

.4

P 1.8 Environmental Conditions (5) .

1.8.1 Temperature 1.8.2 Pressure- .

1.8.3 Humidity 1.8.4 Radiation ,

r i

1.8.5 Chemical -4 1.8.6 Seismic ,

1.9 Projection Qualified Life (6) f 1.10 Remarks 1.11 Part 1 Notes i

-i (1). List auxiliary devices required for proper. operation of. the

- qualified equipment and reference Qualification data sheet for auxiliary devices if qualified separately. l (2) Main equipment; if required auxiliary devices design life is different,so state.

(3) Expected number of operational cycles including testing during design life.

(4) Accuracy, duration of requirement, .etc. , DBE is the Design Basis Event. l (5) Conditions and duration of each. Reference to standard curve may be used. Do not include margins. .

(6) May be determined after qualification by test or analyses. '

s

, -l PAGE OF L

8 A-6 ,

r 5

, , , . . . , . , , , . . - _ . . , _ . . . , , - . . . . . . . . . ~ , , , , , - . - . _ . . . - - , , , . . . . . - . . - -

EQUIPMENT QUALIFICATION DATA PACKAGE (PART3-QUALIFICATIONBYTESTS) .

2.0 TEST PLAN

-2.1 Equipment Description

2. 2 Number Tested 2.3 Mounting

. 2.4 Connections 2.5 Aging Simulation Procedure 2.6 Simulated Environmental Conditions (1) 2.6.1 Temperature 2.6.2 Pressure.

2.6.3 Humidity 2.6.4 Radiation 2.6.5 Chemical 2.6.6 Seismic ,

PAGE OF A-7. i

,. .,a ., - . , .,, , a. ,,, , , , - , , . , , ,,..,.v,,.m

w l

i 2.7 Measured' Variables Not 1

- 2.7.1 Category I - Environment Required Required 'l 1 2.7.1.1 Temperature 2.7.1.2 Pressure-2.7.1.3 Moisture Content' ;l 2.7.1.4 Gas Composition -

2.7.1.5 Vibration 2.7.1.6 Time 2.7.2 Category II - Input Electrical Characteristics 2.7.2.1 Voltage 2.7.2.2 Current 2.7.2.3 Frequency 2 7.2.4 Power 2.7.2.5 Other 2.7.3 Category III - Fluid Characteristics 2.7.3.1 Chemical Camposition 2.7.3.2 Flow Rate 2.7.3.3 Spray 2.7.3.4 Temperature 2.7.4 Category IV - Radiological Features 2.7.4.1 Energy Type 2.7.4.2 Energy Level 2.7.4.3 Dose Rate 2.7.4.4 Integrated Dose PAGE OF A-8

t 2.7.5 Category V - Electrical Characteristics 2.7.5.1 Insulation Resistance .

2.7.5.2 Output Voltage 2.7.5.3 Output Current 2.7.5.4 Output Power 2.7.5.5 Response Time 2.7.5.6 Frequency Characteristics ,

2.7.5.7 Simulated Load 2.7.6 Category VI - Mechanical Characteristics 2.7.6.1 Thrust 2.7.6.2 Torque 2.7.6.3 Time 2.7.6.4 Load Profile 2.7.7 Category VII - Auxiliary Equipnent (List Function and Required Measurements) 2.7.7.1 2.7.7.2 l

2.7.7.3 2.7.7.4 ,

i PAGE OF A-9

s 2.8 Test Sequence Preferred (2) 2.8.1 Inspection of Test Item .

2.8.2 Operation (Normal Condition) 2.8.3 Operation (Perfonnance Specifications Extremes, Section 1) 2.8.4 Simulated Aging (3) 2.8.5 Vibration (4) 2.8.6 Operation (Simulated DBE Conditions)(3) 2.8.7 Operation (Simulated Post DBE Conditions)(3) 2.8.8 Disassembly and Inspection 2.9 Test Sequence Actual (l)

Step Justification 2.9.1 2.9.2 2.9.3 2.9.4 2.9.5 2.9.6 2.9.7 2.9.8 2.10 Type Test Data 2.10.1 Objective 2.10.2 Equipment Tested 2.10.3 Features Demonstrated by the Test i

2.10.4 Description of the Test Facility l

l 2.10.5 Test Procedures PAGE OF l

A-10 ;

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

i 4

e 2.10.6 ' Test' Data and Accuracy .

2.10.7 Summary, Conclusions and Recommendations i

i 2.10.8 Supporting Data }

i i

1 (APPROVAL) (DATE).. !

i 1

2.11 Part 2 Notes (1) ' Reference to Standard Curve may be used. Margins per'IEEE-323-1974 have been'added.

4 C (9) Paragraph 2.8 shows the preferred test sequence. Show'.

actual sequence and justify in Section .2.9 >

(3) Aging and radiation may be combined. If combined, DBE and ,

post DBE conditions need not include radiation.

s t

(4) -Simulated Seismic and other Nomal vibration seen in service e k

?

iV PAGE 0F ,

t A-11

-i

- . . . . , . . . . ._2.,. ~ . _ - . - - . . . ~ . . . . . ~ . .. . . - . . . ~ . . . _ _ . . . . . . _ _ _ . _ . . _ . .,__.__.;_,,...~...

u a:

w EQUIPMENT QUALIFICATION DATA PACKAGE (PART 4 - QUALIFICATION BY EXPERIENCE) 3.0 OPERATING EXPERIENCE DATA 3.1 Interface or Boundary Conditions 3.2 Qualification Features Demonstrated 4

3.3 Comparison of Experience and Specifications 1

'3.4 Summary and Source of Experience a

I 3.5 Qualification Basis

( APPROV AL) (DATE)

PAGE _ _ 0F A-12

ML20204B638

Text

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