ML20023C428
| ML20023C428 | |
| Person / Time | |
|---|---|
| Site: | 05000470 |
| Issue date: | 05/10/1983 |
| From: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| LD-83-045, LD-83-45, NUDOCS 8305170326 | |
| Download: ML20023C428 (52) | |
Text
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C-E P wsr Syztzmi Tel. 203/688-1911 Cornbustion Engineenng. Inc. Telex 99297 1000 Prospect Fhil Road Windsor. Connecticut 06095 POWER H SYSTEMS Docket No.: STN 50-470F May 10,1983 LD-83 045 Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Open Items 1 and 4, Revised Section 3.11 of CESSAR-F
Reference:
Letter LD-82-063, A. E. Scherer to D. G. Eisenhut, dated July 1, 1982
Dear Mr. Eisenhut:
i Section 3.11 of CESSAR-F, " Environmental Design of Mechanical and Electrical Equipment", describes the Combustion Engineering methodology for the environmental qualification of mechanical and electrical equipment required to mitigate the consequence of a design basis event or to attain a safe shutdown condition. Based on discussions with the NRC Staff reviewer and the reviewers of CENPD-255, " Class 1E Qualification", at EG&G Idaho, we have revised Section 3.11 to incorporate information necessary to resolve outstanding concerns. Our revised Section 3.11 is attached for Staff review.
The three areas of congern identified were (1) the treatment of radiation qualification below 10 rads, (2) the treatment of aging, and (3) distinction between sections that addressed electrical, mechanical or both types of equipment. The attached revision contains additional information to address, 4
in more detail, our methodology for radiation qualification below 10 rads and aging. We have also clarified the section to reflect its applicability to both electrical and mechanical equipment.
In addition to addressing the issues raised in the resolution of Staff concerns with equipment qualification in general, the revision addresses concerns raised in the review of the Inadequate Core Cooling Instrumentation (ICCI), Open Item 4. Specifically, the Staff requested more information on the qualification of the ICCI. To resolve this concern, we have added the ICCI to Table 3.118-2, " Class 1E Instrumentation Qualification Requirements". We believe that this change should resolve Open Item 4 of the CESSAR-F Safety Evaluation Report.
gc>o3 8305170326 830510 PDR ADOCK 05000470 A PDR
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Mr. Darrell G. Eisenhut LD-83-045 May 10,1983 Page 2 l
l The revised Section 3.11 will be incorporated into the text of CESSAR-F in an amendment. Revised sections have been highlighted by a vertical line and the ,
letter "A" in the right-hand margin next to the lines being changed. This '
submittal has been prepared to expedite the resolution of Open Items 1 and 4.
If you have any questions on the attached, please contact me or Mr. G. A. Davis of my staff at (203) 688-1911, extension 2803.
Very truly yours, COMBUSTION ENG EER G, INC.
n u -:
A. E r Director Nuclear Licensing F72063
- Attachment
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- Gary Meyer (Project Manager / USNRC) i 4
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3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT The design criteria with respect to environmental effects on the electrical and mechanical equipment of the Reactor Protective System and the Engineered Safety features System to ensure acceptable performance in all environments (normal and accident) depend upon equipment location and function. Such equipment is qualified to meet its performance requirements under the environmental and operating conditions in which it will be required to function and for the length of time for which its function is required. As
, far as practical, equipment for these systems is located outside the Containment Building or other areas where adverse environmental conditions could exist.
' Compatability of mechanical and electrical equipment with environmental l
conditions is provided within the following design criteria:
A. For operation under normal conditions the systems are designed and qualified to remain functional after exposures within the following ranges of environmental conditions:
- 1. Design temperatures maintained at the equipment location during normal operation by the ventilating and cooling system described in Section 9.4. Temperature ranges are given in Appendix 3.llA, Table 3.llA-1 thru 3.11A-14. l7
- 2. Relative humidity ranges are given in Appendix 3.11A, Table 3.ll A-1 thru 3.llA-14. l7
, 3. Pressure ranges are given in Appendix 3.11A, Table 3.11 A-1 thru
, 3.llA-14. l7 V 4. Maximum expected integrated radiation exposures for 40 years at the equipment location during normal operation are given in Appendix 3.11A, Table 3.llA-1 thru 3.11A-14. l7 4
B. In addition to the normal operation environmental reouirements given
- in listing A above, the mechanical and electrical components required to mitigate the consequences of a design basis event (DBE) or to attain a safe shutdown of the reactor are designed to remain functional l7 after exposure to the environmental conditions anticipated following the specific DBE which they are intended to mitigate. Anticipated environmental conditions and requirements are listed below.
- 1. The temperature, pressure, and humidity ranges following the l
design bases accidents such as the loss of coolant accident (LOCA), the main steam line break (MSLB), control element assembly ejection, or feedwater line break'(FWLB), " Worst Case" combined 7 (LOCA & MSLB) are indicated in Appendix 3.11A.
- 2. The time integrated post accident radiation doses are indicated in Appendix 3.llA. Equipment will be designed for the types and levels of radiation associated with normal operation plus the radiation associated with the limiting design basis accident (DBA). 7 If more than one type of radiation is significant each type may be j considered separately.
Amendment No. 7 March 31, 1982 I
3-11-1
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3.11.1 EQUlPMENT IDENT1FICAT10N AND ENVIRONMENTAL COND1TIONS Appendix 3.11B lists and categorizes systems required to mitigate a DBE or t
to attain a safe shutdown. Specific equipment and components for each
. system are discussed in the appropriate section of the safety analysis report as referenced in Appendix 3.118. The major component categories, i
such as motor-operated valves, pump motors, instrumentation and pressure boundary equipment in each system, and the -location of the components by area are also provided.
3.11.2 QUALIFICATION TESTS AND ANALYSES Qualification tests and analyses performed in accordance with the methodologies defined in CENPD 255 Rev. 03 on NSSS instrumentation and electrical equipment j (including pump and valve motors and electrical accessories) fulfill the 4 requirements of IEEE Standard 323-1974, and " Category 1" of NUREG 0588. For mechanical equipment, environmental qualification is based on engineering 7 evaluation, and material selection where sufficiently reliable data is available.
3.11.2.1 fECHANICAL AND ELECTRICAL Conoonent Environnental' Desion and qualifi^ cation A for Normal Coeration -
s t
Equipment listed in Appendix 3.llB is designed for 40 years of continuous operation in the temperature, pressure, humidity, and radiation environment that exists at the equipment location during normal operation, assuming proper routine preventive maintenance is performed, such as periodic replace-ment of seals and packing. s Appendix 3.ll A provides the ranges of the design temperatures, pressure, ./
and humidities, as well as the exposures to chemica1 spray and radiation for each area in which safety-related equipment listed in Appendix 3.llB is located.
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3.11.2.2 "ECHA1! CAL ann ELECTRICAL Corconent Envirar.nental nesian and cuali fica tion A for Operation After a Pesian Pasis Event Equipment listed in Appendix 3.llB is designed to remain functional in the temperature, pressure, humidity, and chemical spray environment conditions that exist at the equipment location after the design basis LOCA. This equipment is also designed for the maximum calculated integrated radiation Amendment No. 7
- March 31, 1982 3.11-2
exposure after the design basis LOCA, as discussed in Section 3.11.5. The temperature, pressure, and humidity environment inside the containment after a LOCA is discussed in detail in Section 6.2.1.3. The containment spray cnaracteristics are given in Section 6.2.2.1. The integrated post-accident radiation dose for those aieas at which equipment is located is given in Appendix 3.llA. The temperature, pressure, and humidity environment inside the containment after a MSLB is discussed in detail in Section
. 6.2.1.4.
The requirements of the General Design Criteria, Appendix A to 10CFR50, are met as follows:
- Criterion 1 - Quality Standards and Records, refer to Section 3.1.1.
- Criterion 4 - Environmental and Missile Design Basis, refer to Subsection 3.1.4.
- Criterion 23 - Protection System Failure Modes, refer to Section 3.1.19.
- Criterion 50 - Containment Design Basis, refer to Sections 3.1.43 and 6.2.1.
The requirements of the Quality Assurance Criterion III, Appendix B to 10CFR50 are met as discussed in the Design and Procurement Q.A. Program
.- (See Chapter 17).
The recommendations contained in the documents discussed below, listings A through 0, and other applicable Regulatory Guides and Standards have also been utilized.
A. Regulatory Guide 1.30, Quality Assurance Requirements for the Installa-tion, Inspection, and Testing of Instrumentation and Electric Equipment.
B. Regulatory Guide 1.73, Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants. A descripiton of the tests and analysis by which active NSSS valves are qualified is provided in Section 3.9.2.2.
C. The qualification methods and documentation requirements of IEEE Standard 323-1974, IEEE Standard for Qualifying Class lE Equipaent for Nuclear Power Generating Stations and " Category 1" of NUREG 0588, are discussed in CENPD-255 Rev. 3 (Reference 1). l7 D. Pressure boundary components inside the containment are designed for the appropriate temperature and pressure environment in accordance with j7 the applicable code to which the component is constructed.
Environnental qualification testinc is not considered necessary . for such A components.
Amendment No. 7 March 31, 1982 3.11-3 i
AGlNG FOR-HARSH- AND-NON-HARSH-EMVfRONMENT E0V! PENT
- As stated in CENPD 255 Rev. 03 the aging portion of the qualification program is l defined based upon whether or not equipment is located in a harsh or non-harsh envi ronment. Equipment located in a harsh environment will undergo an aging analysis and an accelerated age conditioni.ng program. Equipment located in a 4
non-harsh environment will undergo an. aging analysis that focuses on the ideritification of known aging mechanisms that significantly increase the equipments susceptibility to its design basis event (seismic event only for non- A harsh environments). If no known significant aging eechanisms are found, a
. surveillance / preventive maintenance (S/PM) program will be developed to monitor for degradation trends that suggest increasing seismic
- suscepti bili ty. If an aging mechanism is found that is known to significantly increase the equipments seismic susceptibility with time, that mechanism will be analyzed to determine whether an accelerated aging program or a periodic part replacement program is appropriate. j RADI ATION FOR-HARSH-AND-NON-HARSH-ENV IRONMENT EOUIPENT Ecuipment will be designed for the types and levels of radiation associated with normal operation plus the. radiation associated with the limiting Design Basis Accioent (DBA). These levels are defined in Appendix 3.11 A.
I Ecuipment which is exposed to radition above 10 Rads will be irradiated to its anticipated Total Integrated Dose (TID) prior to type testing unless determined by analysis that radiation does not effect its ability to perform its required fuheti on. Where the application of the accident dnse is planned during DBA testing, it need not be included during the aging process. A Equipment whien will be' exposed to radiation levels of 10' Rads or below will
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be analyzed to determine whether low level adiation could impact its ability to perform its required function. Where analysis supported by partial type test data cannot demonstrate proper operation at the required radiation levels, type testing will be performed. Additionally, Electronic Ecuipment exposed to lcw level radiation will be addressed 'by an Aging Analysis which focuses on the identification of semi-conductor (organic material) components that are considered to be age-sensitive in 40 years. For electronic components that are ace-sensitive a surveillance / preventive maintenance program will be developed.
CENPD 255 Rev. 03 outlines this methodology.
Mechanical / Electrical Ecuipent will be qualified to the typical radiation environments define ~d in Appendix 3.11A. If more than one type of radiation is significant, each type may be applied separately.
Gama -
Cobalt-60 is considered an acceptable gama radiation source. Other sources l-may be found acceptable, and will be justified. Electrical Equipment will be i tested to typical gama radiation levels defined in Appendix 3.11 A. ,
3.11-4
- 1 Beta Equipment exposed to beta radiation will be identif.ied and an analysis will be performed to determine if the operabili,ty of the equipment is affected by beta radiation ionization andheating effects. Qualification will be performed by test unless analysis demonstrates that the safety function will not be degraded
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by Beta exposure. Equipment will be tested and/or analyzed to the beta 'l radiation l'evels , defined in Appendix 3.11 A. Where testing is recommended, garma equivalent radiation source will be used. .
Heutron Ecuipment exposed to neutron ra,4{ation will be identified and neutron radiation levels defined. When actual neturan dose qualification testing is not performed, an equivalent gamma Fadiation dose will be useo for qualification testing to simulate neutron exposure. The basis for establishing an equivalent gamma radiation dose will be provided. ,
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paints / Radiation Effects _ ,
An analysis will be performed addressing paint exposure to beta and ganma radiation. Qualification of painted equipment will be by test if analysis indi cate's that the safety function of the equipment could be imoaired by failure due to radiation.
3.11-4a
Chemical Soray After a postulated accident, such as the LOCA or MSLB, components located in the Containment Building may be exposed to a chemical spray from a solution used to remove iodine from the containment building atmosphere. Equipment will be environmentally tested to these conditions and performance requirements demonstrated during and after the test. The most severe spray composition will be determined by single failure analysis of the spray system. Corrosion effects due to long term exposure will be addressed, as appropriate.
Where qualification for chemical spray environment is required, the simulated spray will be initiated at the time shown in Appendix 3.llA.
Typical values of chemical spray composition, concentration and pH are defined in Appendix 3.llA, Tables 3.llA-1, 3.11A-2 and 3.11A-13.
3.11.3 QUALIFICATION TEST RESULTS 3.11.3.1 NSSS Instrumentation and Electrical Eouipment Qualification testing and analyses of NSSS Instrumentation and Electrical Equipment are discussed in Reference 1.
3.11.3.2 NSSS Mechanical Eouipment Qualification tests results and analyses of NSSS Mechanical Equipment are provided in Section 3.9.2.2 .
3.11.4 CLASS lE INSTRUMENTATION LOSS OF VENTILATION EFFECTS
- Loss of ventilation is discussed in the Applicant's SAR. Interface criteria 7
are presented in Chapter 7.
Class lE equipment which is located in the control room or similar areas includes the following:
Plant Protection System Cabinet (PPS)
Auxiliary Relay Cabinet (ARC)
Auxiliary Protective Cabinet (APC)
Main Control Panels Process Ir.strument Cabinet Other instrumentation, such as process transmitters and signal converters and the reactor trip switchgear system circuit breakers, are located in the Auxiliary Building or Containment Building. Equipment in these areas is qualified for the maximum expected temperature, radiation, humidity, and pressure under which the ecuipment is expected to operate.
The following are the normal and abnormal envirormental conditions for which C-E Class IE safety-related equipment is qualified to operate according to the service location cf the equipment and the expected environmental condition.
Amendment No. 7 3.11 40 March 31, 1982
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typical environmental n Appendix 3.ll A, Tables 3. ll A-1 thru 3.11 A-14 which A conditions and$ssociated environmental test profiles are iuoted in Figures 3.11A-6A thru 3.llA-10. -
3.11.5 -
CHEMICAL SPRAY, RADIATION, HUMIDITY, DUST, SUBMERGENCE, AND POWERSUPPLY VOLTAGE AND FREQUENCY VARIATION 3.11.5.1 Chemical Environment Engineered Safety Feature Systems are designed to perform their safety-related functions in the temperature, pressure, and humidity conditions described in Section 3.11.1 and Sections 6.2 and 6.3. In addition, components of ESF systems inside the containment are designed to perform their safety-related functions in the presence of the existing chemical environment, resulting from the boric acid and hydrazine solutions recirculated through the Safety Injection System (SIS) and Containment Spray Systems (CSS). The SIS is designed for both the maximum and long-term boven concentration and pH. These chemical environment conditions are given in Appendix 3.llA.
3.11.5.2 Radiation Environment The components in the Engineered Safety Feature and Reactor Protection Systems are designed to meet their performance requirements under the environmental and operating conditions in which they will be required to function and for the length of time for which their function is required. The components are designed to ensure acceptable performance under normal operational radiation exposure in addition to the single most adverse post accident environment. The normal operational exposures are based on the design source terms provided in 7
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Section 11.1 and Section 12.2. Radiation environments for those components for which the most adverse accident conditions are post LOCA are based on the )
source term assumptions consistent with Regulatory Guides 1.4 and 1.7.
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Radiation environments for those components for which the most adverse accident condition is other than the LOCA (such as the main steam line break, feedwater line break or CEA ejection) are based on conservative estimates of the fuel assembly gas gap activities and maximum Reactor Coolant specific activities as discussed in Section 11.1.
HUMIDITY j Equipment not subjected to steam environments during DBE testing will be I environmentally tested to shor.t term high humidity levels prior to operation andperformancerequirementQemonstratedduringandafterthetest. Equipment that is subjected to steam environments will be subjected to the appropriate l test profiles in Appendix 3.llA.
DUST Dust environments will be considered when establishing service conditions and qualification requirements. The potential effects of dust exposure will be evaluated relative to effects upon equipment safety function performance.
Amendment No. 7 March 31,1982 3.11-5
Where dust could have a degrading effect on equipment safety function performance, it will be addressed in the qualification program through the development of a maintenance program and/or an upgrading of equipment interface requirements.
SUBMERGENCE Equipment locations and operability requirements will be reviewed to establish whether or not specific equipment could be subject to submergence during its required operating time. Flood levels both inside and outside containment will be reviewed and potential impacts on equipment qualification appropriately addressed. Where operability during submergence is required, qualification will be demonstrated by type test and/or analysis supported by partial type 7 test data.
Power Supply Voltace and Frequency Variation Power supply voltage and frequency variation is addressed in several areas throughout the equipment design and verification process. During the design process interface requirements dictate the acceptable range of power supply variation. Equipment specifications incorporate these interface requirements into the design to ensure acceptable operation within the defined range of power supply voltage and frequency variation. Upon equipment fabrication and completion, design verification tests are performed to demonstrate design I
adequacy.
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l Amendment No. 7 March 31, 1982 3.11-6
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REFERENCES ?
" Qualification of Combustion Engineering Class lE Instrumentation", . !
- 1. !
CENPD-255 Rev.03, Combustion Engineering, Inc., Windsor, Connecticut. l7
- 2. Griess, J. C. and Ba'carella, A. L., " Design Considerations of Reactor Containment Spray Solutions", CRNL-TM-2412, Part III, Oak Ridge National ,
Laboratory, Oak Ridge, Tennessee, December,1969. {
1,
- 3. Kircher, J. F. , and Bowman, R. E. , " Effects of Radiation on Materials and Components", Van Nostrand Reinhold, New York, 1964.
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Amendment No. 7 March 31, 1982 3.11-7
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i APPENDIX 3.11 A TYPICAL ENVIRONMENTAL CONDITIONS AND TEST PROFILES l7 F0R ,
STRUCTURES AND COMPNENTS3 Amendment No. 7 March 31, 1982
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APPENDIX 3.11A TYPICAL ENVIRONMENTAL CONDITIONS AND TEST PROFILES l7 FOR STRUCTURES AND COMPONENTS This appendix defines the generic environmental cualification requirements for CESSAR scope structures and comaonents. The requirements are given in categories which combine various locations and conditions of design for
{' environmental qualification purposes.
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EFFECTIVE PAGE LISTING ,
i CHAPTER 3
,, APPENDIX 3.llA Table of Contents Page Amendment i
Scope Statement 7 i 7 ii 7 iii 7 I
Text Page Amendment ;
3.llA-1 7 3.llA-2 7 Table Amendment
/ 3.ll A-1 through 3.ll . A-14 7
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Figures Amendment 3.llA-1A 7 I
3.llA-1B 7 3.llA-2 7
. 3.11A-3 7
- 3.llA-4 7 3.llA-5 7
l 3.llA-6A 7 1 3.11A-6B 7
- 3.llA-7 7 3.11 A-8 7 3.llA-9 7 3.llA-10 7 Amendment No. 7 March 31,1982
TABLE OF CONTENTS CH APTER 3 APPENDIX 3.11 A Section Sub.iect Pace No.
3.11A.1 DEFINITION OF ENVIRONMENTAL CONDITIONS AND PROFILES 3.11A.1 7
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Amendment No. 7 March 31, 1982 i
LIST OF TABLES -
CHAPTER 3 APPENDIX 3.11A Table Subj ect 3.11A-1 Category "A-1" Environmental Conditions (LOCA: In-Containment) 3.11A-2 Category "A-2" Environmental Conditions (MSLB: In-Containment) 3.11A-3 Category "B" Environmental Conditions (Normal In-Containment) 3.11A-4 Category "C" Environmental Conditions 3.11A-5 Category "D" Environmental Conditions 3.11A-6 Cateoory "E" Environmental Conditions 3.11A-7 Category "F" Environmental Conditions i
3 .11 A-8 Category "G" Environmental Conditions 7 3.11A 4 Category "H" Environmental Conditions 3.11A-10 Category "I" Environmental Conditions (Outside Plant Buildings) ,
3.11A-11 Category "J" Environmental Conditions 3.11A-12 Category "K" Environmental Conditions (nutside Plant Buildings) 3.11A-13 Category "V-1" Environmental Conditions (Vorst Case: In Containment) i 3.11A-14 Category "V-2" Environmental Conditions (Worst Case: Outside Containment) i .
Amendment No. 7 March 31,1982 ii
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LIST OF FIGURES CH APTER 3 APPENDIX 3.11A Figure Subject 3.11A-1A Tyoical Containment Atmosphere Temperature Condition following (LOCA) 3.11A-1B Typical Containment Atmosphere Pressure Condition follcwing (LOCA) 3.11A-2 Typical Annulus Atmosphere Temperature Condition following (LOCA/MSLB) 3.11A-3 Typical Containment Atmosohere Temoerature Condition following (MSLB)
Typical Integrated Dose in Scherical Containment Following (LOCA) A 1A4A q.{lA4B
-. Typical Integrated Dose in Cylindrical Containment Following (LOCA) 3.11A-5 Typical Containment Gamma Dose Rate following (LOCA) 3.11A-6A Typical Containment Building Environmental Test Profile for Category "A-1" " A-2" and "V-1" Environmental Conditions l' 7 A Q.
3.11A-7 Typical Environmental Test Profile for Category "C" Environmental Conditions 3.11A-8 Typical Inside Cabinet Environmental Test Profile for Category "C" Environmental Conditions A
3.11A-9 Typical Environmental Test o rofile for Categories "H" and "J" Environmental Conditions 3.11A-10 Typical Inside Cabinet Environmental Test Profile for Categories "H" and "J" Environmental Conditions l
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c 3.llA-1 DEFINITION OF ENVIRONMENTAL CONDITIONS AND PROFILES The purpose of this appendix is to define typical environmental conditions and associated environmental test profiles.
SUMMARY
Figures 3.11 A-1 A through 3.11 A-5 provide typical post accident environmental conditions. These figures are not " test" profiles and therefore do not include margin.
Tables 3.llA-1 through 3.11A-14 provide a series of tables titled " Category "XX"" Environmental Conditions". These tables were developed for the purpose of defining a limited set of clearly established environmental conditions that could be associated with specific equipment and/or locations. Appendix 3.11A utilizes and illustrates this approach by correlating a generic piece of equipment with its corresponding environmental category designator.
These tables also do not define actual test conditions or parameters and therefore do not include margin.
Figure 3.11A-6 is an in-containment test profile that corresponds to the post accident environmental conditions defined in Figures A 3.ll A-1 A through 3.ll A-5 and Tables 3.11 A-1, 3.11 A-2 and 3.11 A-13.
Figure 3.llA-6A incorporates a nd illustrates required margin.
For an explanation of the use of this orofile see Section 3.4.1 of CENPD ,,
(~ 255, Rev. 03. /
Figures 3.11A-7 through 3.llA-10 are test profiles for equipment located outside containment. These test profiles incorporate and illustrate marcin. lA The test profiles included herein represent " typical" examples of qualifica-tion test profiles and are not intended to represent the complete set of all test profiles utilized.
ENVIRONMENTAL CONDITIONS A. Tables 3.11A-1 and 3.11 A-2 list typical carameters for design basis lA accident conditions inside containment (Environmental Categories "A-1" and "A-2").
B. Table 3.llA-3 lists typical parameters for normal environmental conditions inside containment (Environment Category "B").
C. Tables 3.llA-4, 3.ll A-ll and 3.ll A-12 list typical parameters for normal environment conditions outside containment (Environment Categories "C",
"J" and "K").
D. Tables 3.11A-5 through 3.llA-10 list typical parameters for abnormal environment conditons outside containment (Environment Cateqories "D",
"E", "F", "G", "H" and "I").
Amendment Nc.7 March 31,1982 3.llA-1
I E. Table 3.11 A-13 lists typical " Worst Case" parameters for valves inside ,
containment (Environment Category V-1).
F. Table 3.11A-14 lists typical " Worst Case" parameters for valves outside containment (Environment Category V-2).
G. Figures 3.11A-1A through 3.ll A-5 provide profiles for typical post
- accident environment conditions.
H. Figures 3.ll A-6A represents a simulated environmental profile A for equipment located inside containment, as appropriate (Environment Categories "A-1", "A-2" and "V-1").
I. Figures 3.llA-7 and 3.llA-8 represent simulated environmental conditions for equipment located outside containment, as aopropriate (Environment Category "C") .
J. Figures 3.11 A-9 and 3.11 A-10 will be used to simulate environment conditions for equipment located outside containment, as appropriate (Environment Categories "H" and "J").
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I Amendment No. 7 3.llA-2 March 31, 1982
3.llA.2 QUALIFICATION REQUIREMENTS (by Category)
Structures and components in each of the environmental qualification cate-gories are designed and qualified in accordance with the following*: (The ,
environmental conditions referred to are given in Table 3.llA-1). .
A-1 One time service during the condition specified for Category A-1, up to the point in time at which they are required to function, unless plant environmental control systems, physical separation, barriers, or other teatures make such design and qualification unnecessary. ,
Continuous service during the conditions specified for Category B'.
A-2 One time service during the conditions specified for Category A-2, up to the point in time at which they are required to function, unless plant environmental control systems, physical separation, barriers or other features make such design and qualifications unnecessary.
Continuous service during conditions specified for Category B.
B. Continuous service during the conditions specified for Category B.
C. Continuous service during the conditions specified for Category C.
D. One time service during the conditions specified for Category 0, up to
- tne point in time at which they are required to function, unless plant environmental control systems, physical separation, barriers or other
'- features make such design and qualification unnecessary.
Continuous service during the conditions specified for Category C.
E. One time service during the conditions specified for' Category E, uo to the point in time at which they are required to function, unless plant environmental control systems, physical separatio7, barriers or other features make such design and qualification unnecessary Continuous service during the conditions specified for Category C.
t F. One time service during the conditions specified for Category F, up to the point in time at which they are required to function, unless plant environmental control systemc, physical separation, barriers or other features make such design an'd qualification unnecessary.
Continuous service during conditions specified for Category C.
G. One time service during the conditions specified for Category G, up to the point in time at which they are required to function, unless plant environmental control systems, physical separation, barri'ers or other features make such design and qualification unnecessary.
Continuous service during ccnditions specified for Category C.
- $;ecific exemptions to these ge'eral requirenents may be taken when justifica-tion is provided.
3.11A-2
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H. Short-term service (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> maximum darAtion for each event, total time not to exceed 1% of operating life) under conditions specified for Category H. Continuous service during conditions specified for Category J.
X. Continuous service under conditions specified for Category I.
J. Continuous serv' ice under conditions specified for Category J.
K. Continuous service under conditions specified for Category K.
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3.11A-4
4 TABLE 3.11A-1 CATEGORY "A-1" ENVIRONMENTAL CONDITIONS (LOCA: IN-CONTAINMENT)
ENVIRONMENTAL PARAMETERS RANGE AND DURATION TEMPERATURE, *F FIGURE 3.11A-1A PRESSURE, PSIG FIGURE 3.11A-18 HUMIDITY SUPERHEATED STEAM /
AIR MIXTURE 7
RADIATION, RADS FIGURES 3.11 A-4 AND 3.ll A-5 l.,,
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CHEMICALS NOTE 'l' l
NOTE 1 - 4400 PPM BORON AS H 80 , 200 A 3 3 PPM HYDRAZINE AS24 N H AND pH =t TO 10.
Amendment No. 7 March 31, 1982
I TABLE 3.llA-2 I
CATEGORY "A-2" ENVIRONMENTAL CONDITIONS ,
(MSLB: IN-CONTAINMENT) .
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r 1
ENVIRONMENTAL RANGE DURATION PARAMETERS FIGURE 3.11A-3 0-12 MIN.
TEMPERATURE, F _
A FIGURE 3.11A-1A (AFTER 12 MIN. )
i SAME AS LOCA PROFILE PRESSURE, PSIG : FIGURE 3.11A-18 l l
. ! I SH STEAM / AIR 0-12 MIN. , !
l MIXTURE ! )
i HUMIDITY SAT. STEAM / AIR MIXTURE (AFTER 12 MIN.)
i RADIATION, RADS 4.5 X 10# y (TID) l NOTE 'l' l CHEMICALS I l !
I I
t A
NOTE 1 4400 PPM BORON AS H 80 , 2co PPM HYDRAZINE AS N H AND 24 3 3 4
T0 10. i l
o 5.H. 3 ?" "'"
Amendment No. 7 March 31, 1982 l
1
TABLE 3.11A-3 CATEGORY "B" ENVIRONMENTAL CONDITIONS (NORMAL: IN-CONTAINMENT) 9 ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE, *F 55 TO 122 CONTINUOUS PRESSURE, PSIG 0-5 - CONTINUOUS HUMIDITY, % 20-90 CONTINUOUS 7
/' !
(
NOT*r 'l' !
i CHEMICALS NOT APPLICABLE NOTE 1 - DOSE VARIES WITH COMPONENT (SEE CESSAR-F, TABLE 3.11B-2)
Amendment No. 7 March 31, 1982
, . - , _ . - _ - -6 . , . - . , - , ,--...,m-.-- . - , , , - - - - . , _ - , --- _W
_ ~ _ . .- -- .-. _ - - - . - .. = _ .
i b
TABLE 3.11A-4 i
CATEGORY "C" ENVIRONMENTAL CONDITIONS l
ENVIRONMENTAL RANGE DURATION PARAMETERS TEMPERATURE, 'F 55 TO 104 CONTINUOUS i
PRESSURE, PSIG 0 i CONTINUOUS i
HUMIDITY, % 20-90 CONTINUOUS NOTE 'l' i
RADIATION, RADS l (TID) NOTE '2' l l
CHEMICALS 1 NOT APPLICABLE -
7 NOTE 1 - AT OR AB0VE 80 F, THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90%
RELATIVE HUMIDITY AT 80 F (DEWPOINT OF 77 F).
NOTE 2 - DOSE VARIE3 WITH COMPONENT (SEE CESSAR-F, TABLE 3.118-2).
i Amendment No. 7 March 31, 1982 l
1
l 1
i
] TABLE 3.11A-5 CATEGORY "D" ENVIRONMENTAL CONDITIONS ENVIRONMENTAL RANGE OR PARAMETERS MAXIMUM DURATION t
104-120 4 HR.
! TEMPERATURE, 'F I 1
- 104 TO 55
AFTER 4 HR.
i
- l
(..- PRESSURE, PSIG '
- O ALL r \s. - i DURATION 1 HUMIDITY, % !20-90 i NOTE 'l' NOTE '2' 6
RADIATION, RADS 4 X 10 Y (IID) t CHEMICALS l NOT APPLICABLE i
NOTE 1 - AT OR ABOVE 20'F, THE M0ISTURE CONTENT IS THAT WHICH PRODUCES 90%
RELATIVE HUMIDITY AT 80*F (DEWP0"1T OF 77 F). AT OR ABOVE 120 F, THE M0ISTURE CONTENT IS THAT WHICH PRODUCES 99% RELATIVE HUMIDITY AT 120 F (DEWPOINT OF ll6*F).
} NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "C" UNLESS j OTHERWISE SPECIFIED.
i Amendment No. 7 March 31, 1982 i
l i
TABLE 3.11A-6 CATEGORY "E" ENVIRONMENTAL CONDITIONS ,
i n
ENVIRONMENTAL RANGE OR l MAXIMUM DURATION PARAMETERS 7
e j 55 TO 330 ,
0 - 3 MIN. .
ITEMPERATURE, *F ,
I i 104-55 AFTER 3 MIN.
l i
I '
3 0-3 MIN.
j l PRESSURE,PSIG i
\
' AFTER 3 MIN. j 0 ;
i ;
c '
7 100 0-3 MIN. .!
l IHUMIDITY, % i i NOTE '2' '
AFTER 3 MIN. h i (NOTE 'l') l l
! RADIATION, RADS <103 (TID) !
i
', 1
. i i
- CHEMICALS NOT APPLICABLE i "C" UNLESS ,
NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY '
OTHERWISE SPECIFIED. .
i NOTE 2 - AT OR AB0VE 80*F, THE M0ISTURE CONTENT IS THAT WHICH PRODUCES 90% l RELATIVE HUMIDITY AT 80 F (DEWPOINT OF 77 F). l Amendment No. 7 March 31, 1982
l TABLE 3.11A-7 CATEGORY "F" ENVIRONMENTAL CONDITIONS i
t ENVIRONMENTAL -
PARAMETERS RANGE DURATION TEMPERATURE, 'F FIGURE 3.11A-2 (NOTE '2')
PRESSURE, PSIG 0 ALL DURATION HUMIDITY SAT. STEAM / AIR NOTE '2' MIXTURE _ .
RADIATION, RADS NOTE 'l' f"' , . CHEMICALS NOT APPLICABLE
\s.!
4 NOTE 1 - FOR UNCONTROLLED ACgESS AREAS 1 X 10 y (TID) AND FOR CONTROLLED ACCESS AREAS 4 X 10 y (TID).
I NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "C" UNLESS OTHERWISE SPECIFIED. !
t l
Amendment No. 7 March 31, 1982
, . . .- . . . - _ - .= _ .- -
TABLE 3,llA-8 CATEGORY "G" ENVIRONMENTAL CONDITIONS ENVIRONMENTAL
- PARAMETERS RANGE DURATION i
1.
TEMPERATURE, F FIGURE 3.llA-2 (NOTE 'l')
l 0 ALL DURATION .
l PRESSURE,PSIG ,
I l HUMIDITY SAT. STEAM / AIR NOTE 'l' MIXTURE _ _ _ , _ , . . . . _ _ _ _ _
[
RADIATION, RADS 3.1 X 104 y (TID)
CHEMICALS NOT APPLICABLE I
(
NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "C" UNLESS OTHERWISE SPECIFIED.
4 1
Amendment No. 7 March 31, 1982
- .. . =_. _ _ _ _ .
TABLE 3.11A-9 CATEGORY "H" ENVIRONMENTAL CONDITIONS ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE, *F 55 T0 104 NOTE '2' PRESSURE, PSIG 0 ALL DURATION f l l
HUMIDITY, % f 20-90 i NOTE '2' NOTE '1' 1 l
RADIATION, RADS <103 (TID) i NOT APPLICABLE 7 CHEMICALS 1
I NOTE 1 - AT OR AB0VE 80 F, THE MOISTURE CONTENT IS THAT WHICH FRODUCES 90%
RELATIVE HUMIDITY AT 80 F (DEWPOINT OF 77 F),
l l NOTE 2 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "J" UNLESS
[
OTHERWISE SPECIFIED.
i Amendment No. 7 March 31, 1982 i
2 TABLE 3.11A-10 -
CATEGORY "I" ENVIRONMENTAL CONDITIONS (0UTSIDE PLANT BUILDINGS) i ENVIRONMENTAL
- PARAMETERS RANGE DURATION i i TEMPERATURE, *F -30 TO 122 NOTE 'l' f I I
l
< PRESSURE, PSIG ! O ALL DURATION i ! __
- i
. HUMIDITY, % . l' 100 NOTE 'l' i
. i 1
- RADIATION, RADS l <103 (TID) t j7
, CHEMICALS NOT APPLICABLE e
i l
NOTE 1 - LIMITED TO 8 HOURS OUTSIDE THE NORMAL RANGE OF CATEGORY "K" UNLESS OTHERWISE SPECIFIED.
Amendment No. 7 March 31, 1982 i
1
,- ,,c- . . - - - . . - - - , ...,-.n~- . - - _ - - , , - - - - - - , - - - - - , - - . - . . , , , - . - - - - - . -- - - - - _ _ . . , , . - - . - - . -
TABLE 3.11 A-11 CATEGORY "J" ENVIRONMENTAL CONDITIONS ENVIRONMENTAL PARAMETERS RANGE DURATION TEMPERATURE, *F 65 TO 85 CONTINUOUS 7
PRESSURE, PSIG 0 CONTINUOUS I
HUMIDITY, % ! 40-60 CONTINUOUS I
- March 31, 1982
. l' TABLE 3.11A-12 CATEGORY "K" ENVIRONMENTAL CONDITIONS (OUTSIDE PLANT BUILDINGS)
ENVIRUNMENTAL PARAMETERS RANGE DURATION TEMPERATURE, 'F -30 T0 120 CONTINUOUS PRESSURE, PSIG 0 CONTINUOUS HUMIDITY, % 20-90 CONTINUOUS NOTE 'l' RADIATION, RADS <103 (TID)
CHEMICALS NOT APPLICABLE i
NOTE 1 - AT OR AB0VE 80 F, THE M0ISTURE CONTENT IS THAT WHICH PRODUCES 90%
RELATIVE HUMIDITY AT 80 F (DEWPOINT OF 77 F). AT OR ABOVE 120 F, THE MOISTURE CONTENT IS THAT WHICH PRODUCES 90% RELATIVE HUMIDITY AT 120 F (DEWPOINT OF ll6'F).
Amendment No. 7 March 31, 1982
TABLE 3.11A-14 CATEGORY "V-2" ENVIRONMENTAL CONDITIONS (WORST CASE: OUTSIDE CONTAINMENT): NOTE 2 ENVIRONMENTAL PARAMETERS RANGE DURATION NORMAL 60-104 CONTINUOUS LOCA FIGURE 3.llA-2 TEMPERATURE, F 60-330 0-3 MIN.
MSLB FIGURE 3.llA-2 AFTER 3 MIN.
NORMAL 0 CONTINUOUS PRESSURE, PSIG LOCA 0 ALL DURATION 3 0-3 MIN. 7 MSLB 0 AFTER 3 MIN.
NORMAL NOTE '1' ;
HUMIDITY, ", l SAT. STEAM / AIR LOCA MIXTURE ALL DURATION l
l SAT. STEAM / AIR l !
lMSLB
! j MIXTURE l ALL DURATION l RADIATION, RADS ,
5 X 107 (TID)
CHEMICALS NOT APPLICABLE NOTE 1 - 95% RELATIVE HUMIDITY (RH) AT 60 TO 80 F. FOR 80 F TO MAXIMUM l
TEMPERATURE FIXED M0ISTURE CONTENT IS EQUIVALENT TO 95% RH AT 80 F.
NOTE 2 - COMBINED '" WORST CASE" CONDITION FOR NORMAL /LOCA/MSLB ENVIRONMENTS.
Amendment No. 7 March 31, 1982
TABLE 3.11 A-13 CATEGORY "V-1" ENVIRONMENTAL CONDITIONS (WORST CASE: IN-CONTAINMENT): NOTE 3 RANGE DURATION ENVIRONMENTAL PARAMETERS NORMAL 60 - 122 CONTINUOUS LOCA FIGURE 3.11A-1A TEMPERATURE, 'F I
FIGURE 3.llA-3j 0-12 MIN.
I MSLB I
FIGURE 3.llA-1A AFTER 12 MIN.
NORMAL 0-5 , CONTINUOUS l
PRESSURE, PSIG LOCA FIGURE 3.11A-18 MSLB FIGURE 3.11A-18 1
NOTE 7
[' NORMAL 'l'
, MIXTURE HUMIDITY, % ; SHISTEAM/ AIR l MSLB ; MIXTURE 0-12 MIN.
l f SAT. STEAM / AIR AFTER 12 MIN.
l MIXTURE l
RADIATION, RADS 1 X 108 (TID) i f
CHEMICALS NOTE '2' NOTE 1 - 95% RELATIVE HUMIDITY (RH) AT 60 TO 80 F. FOR 80 F TO MAXIMUM TEMPERATURE FIXED M0ISTURE CONTENT IS EQUIVALENT TO 95% RH AT 80 F.
H NOTE 2 - 4400 PPM BORON AS H B0 ,100 PPM HYDRAZINE AS N 23H AND P 3 3 4 T0 10.
t l
NOTE 3 - COMBINED " WORST CASE" CONDITION FOR NCRMAL/LOCA/MSLB E!.VIRONMENTS.
l
- 5 .11 2 suecA+30TED Amendment No. 7 March 31. 1982 t
_l
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ATandment No 7 l d o '3 B n1VB3dW31 March 31,1952 C-E / Figure
/ TYPICAL ANNULUS ATMOSPHERE TEMPERATURE ggg / / CONDITION FOLLOWING LOCA/MSLB 3.11 A-2
400 i i i i i 350 - -
,1 300 - -
?
N 2 .
Q 250 c:
y RAMP TEMPERATURE FROM INITIAL AMBIENT f,_ 2 .
(, $ CONDITION (120 F) TO PEAK TEMPERATURE (370* F) OVER 10 SECONDS 200 - -
150 - -
l I
I ' ' ' '
100 0 2 4 6 8 10 12 TIME, MINUTES l
l l
i Amendment No. 7 i March 31,1982 l
l l
/ 9"
/ TYPICAL CONTAINMENT ATMOSPHERE TEMPERATURE j [ g f_./f g / / CONDITION FOLLOWING MSLB 3.11 A-3 l
9 1X10 ,
.....i . . . . . . . . . . . . . .-
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DECAY tit'.I, HOUR S 3
A..end.ent No. 7 Mar:n 31, 15E2 C-E TYPICAL INTEGRATED DCSE IN SPHERICAL CCNTAIN!iENs ngure
/
_,gg,.yggjf g-FOLLOWING LOCA 2.'11 A4 A Aw.A4.
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^
DECAY TIiE, HOURS Amendment No. 7 Maren n, iss2 C-E / TYPICAL INTEGRATED DOSE IN CYLINCRICAL CONTAINMEN- Figure f ,~$57{,j/ FOLLCWING LOCA 3 llM3 o
usu fsG.
l l
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-i l x 10 4 i i i i iiiil i i i i i n iil i i i iiiii I 1 10 100 1000 l -[ > TIME, HOURS TN Os
EFi
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3 I I I
' 4~ > 4 DESIGN BASIS EVENT TRANSIENT TRANSIENT TEST TIME LIMITED BY SAFETY-RELATED >
4 TEST TIME LIMITED BY-> <
700 gg g, gig + S AF ETY-R EL ATED GG PSIG FUNCTION r3 I \ flEQUlilEMENT r---------------------~N I
PRESSURE s
\ 160 PSIG 60 l N -
000 \ SUPERilEATED Q
[ PSIG 60 g STEAM / AIR \\
\
ab \ -
50 y o gr . 500 \ SLOPE \ $
\ UNSPECIFIED SUPERilEATED po g d STE AM/ AIR SATURATED c m -i $ \
385 F STEAM / AIR
\ .
40 3 2oE
<mz t-
<t 400 385"F r- w
\
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\
. TEMP.d 20 200 n2 33 TEMP.
OL O \ TEMP. STABILIZE AT NORMAL 2 m 120, ENVillONMENT U. :a 100 STAlllLIZE AT NORMAL
\ 4
. 10 db- ENVillONMENT
\
INITIATE CllEMICAL SPRAY o9y \
$"U L PRESSURE l I I l '
O UE O '
100 1000 10000
/ -4 10 2 10 24 10 SEC .
hM SEC TIME, MINUTES
'1-
$ ?N QUAllFICATION LEVEL
-4 gg ,
- > g u, n i g ,, 7,3 - -
- TEST LEVEL e f!!
e ~
- N
,e %
i E5ti hn f5!:
e
% 170 Ril < 90% ~
~
l (NO IlUMIDITY CONTROL)
NOTE 4 NOTES:
150 -
Rii = 90% l 1. T3 = TIME TO STABILIZE TEST TEMPERATURE -
lT 3 EXTERNAL TO TEST ITEM
~ ~
l 135 F l 2. NO CONDENSATION SilALL FORM ON Tile QH l l TEST ITEM DURING ANY PilASE OF Tile q$ 130 -
Tg 8 liOURS TESTING m-OO 120"F 3. TEST TEMPERATURE EXTREME INCLUDES m r 15"F MARGIN
-<,z m 8 ilOURS
. 4. Rif CORRESPONDS TO A DEWPOINT OF 116*F q$ ~m g 110 - -
mO 3 zz Q .- _
s 2:
m e
un m$
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5E F
$ r," F AMBIENT 75 F AMBIENT hH 70 - -
03 o
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23, 8 IlOURS oh 30 3Q w <o DURATION W 71
- f*
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% 170 1 I RH <90%
l NOTE 4 TS g agg-gog l ! (NO HUMIDITY CONTROL) -
g i 153 F _
i 150 I NOTES:
g g
I 8 HOURS _
< g 1. T 3a TIME TO STABILIZE TEST n2 ~ l l TEMPERATURE EXTERNAL TO '
@S l l TEST ITEM
- 2. NO CONDENSATION SHALL FORM a$'
130 -
Tl3 l ON Tile TEST ITEM DURING ANY 120"F
$5 PHASE OF Tile TESTING ~
O 8 HOURS 3. TEST TEMPERATURE EXTREME
-< g ,u- 110 _
INCLUDES 15 F MARGIN _
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OF 11G"F _
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05 g2 Zo 75"F AMBIENT bh Zm
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~
~
(NO HUMIDITY CONTROL) 150 NOTES: -
- 1. T3 = TIME TO STABILIZE TEST 1 I NOTE 4 TEMPERATURE EXTERNAL TO _
l I l TEST ITEM T3 I 2. NO CONDENSATION SHALL FORM P
h1
-4 3 130 -
1 1
RH = 90% l 1 ON Tile TEST ITEM DURING ANY 119,' F l PHASE OF THE TESTING
]Q _
l 1
8 IlOURS
! $0[ o' i l 3. TEST TEMPERATURE EXTREME 5F 2 ui 110 - I l INCLUDES 15"F MARGIN __.
o *6 $ ' l 4. RH CORRESPONDS TO A DEWPOINT 2o*
- l OF 77"F _
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l l NOTE 4 (NO llUMIDITY CONTROL) 150 1 I NOTES: -
l l TS l 1. Tg = TIME TO STABILIZE TEST
- I 137"F l TEMPERATURE EXTERNAL TO -
y
! TEST ITEM
$N 8 IlOURS
-4 3 130 _
1 2. NO CONDENSATION SilALL FORM -
39 ; His = 90% l ON THE TEST ITEM DURING ANY yO{ ,
l PH ASE OF THE TESTING -
5F$ a ui l 3. TEST TEMPERATURE EXTREME
$5 5 110 -
l INCLUDES 15 F MARGIN -
( $ $
l l 4. RH CORRESPONDS TO A DEWPOINT OF 77"F -
l l
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8* $?
~
IABIE 3.118-2 (Cont'd. ) (5heet 10 of 12)
ClA55 1[ IN51RIHtHIAI10N QUALIfICA110N REQUIREHfMIS ENVIRONHf MI (1) (2) NADIAIION DOSE RADS OPf8AllNG COMPONENI PARAHLItR H00Ul f OfSIGNAll0N 10 Call 0N NORMAt ACCIDENI 40 YRS ACCIOfMI Ilif, NIN HI Sately Power isuitcator Ji-001 CR/MCB 14 H 8kgrd Negligible N/A (5)
Cleannel A, B, C, D NI Safety Power Recorder JR-00lA CR/HC8 H !! Skgrd Negligible N/A (5)
Cliasinel Cliargisig iIow Indicator II-212 CR/MCB 11 11 Skgrd Negligible N/A (5)
Clearging Pressure ludicator PI-212 CR/HC8 H H 8kgrd Negligible N/A (5) 0 Iteactor Pressure Iransmitter PI-268 C8/55 8 Al, A2 2.0 x 10 Negligible N/A (5)
Drain lasik Steam tevel Indicator II-Ill3, 1123 CR/RSP H 11 Skgrd Negligible N/A (5)
Generator A-1, B-l Steam Pressure Indicator PI-Ill3, 1923 CR/R$P H H Bkgrd Negligible N/A (5)
Generator A-1, B-l
$P$ togic Assembly CilNL A, 8, AB C C 8kgrd Negligible N/A (5)
C, D inadespia t e Display Plasseia IbisplaY N/A fit ll 11 bkgrd (one 6 soling linit & Power i epe lleient Supply N/A Page Control N/A fR 11 11 Skgrd Hei.l. I e N/A ilcaler N/A (R ll 11 Bb9rd A fnnt oller flia ssI $
lamiperature Core Exit N/A CB B Note (7) (5.1x106 (8)(9))
Ilie:wucouple Al, A2 louperatuse llea ted Jiatiction N/A CB B Note (7) (8.5x106 (8) (10))
liienocouple Al. A2
}
TABLE 3.118-2 (Cont'd.) (Sheet 12 of 12)
CLASS lE INSTRUMENTATION QUALIFICATION REQUIREMENTS Notes (1) See Table 3.llA-1 for definition of environmental categories.
(2) Equipment located within a cabinet will be qualified allowing for temperature increase inside cabinet.
(3) 55 - 250*F.
(4) Only required to improve reliability of reactor trip.
(5) N/A - Not applicable. Environment not affected by accident.
(6) Process Protective Cabinet contains all other Class lE devices in process instrumentation systems between transmitters and indicators such as signal processors, power supplies, isolators and interlocks.
(7) Post Accident Conditions; equipment is designed to survive the accident condition and to perform its intended function through the post accident period, (8) Ex-Vessel Portion of the instrument. A (9) Instrument Design life of 6 years.
(10) Instrument Design life of 10 years.
-C
.