ML20077G732
| ML20077G732 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 07/22/1983 |
| From: | Artigas R GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20077G719 | List: |
| References | |
| 22A7007, G07186, G7186, NUDOCS 8308040417 | |
| Download: ML20077G732 (54) | |
Text
-. _
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev.19 O
INSTRUCTIONS FOR FILING AMENDMENT NO.19 Remove and insert the pages listed below.
Dashes (----) in the remove or insert column indicate no action required.
Remove Insert Chapter 3 3.11-iii,3.11-iv,3.11-v, 3.11-iii,3.11-iv.3.11-v, 3.11-vii/3.11-viii,3.11-ix, 3.11-vii/3.11-viii,3.11-ix/
3.11-x,3.11-12,3.11-14,3.11-25, 3.11-x,3.11-12,3.11-14, 3.11-26,3.11-30,3.11-43,3.11-44, 3.11-25,3.11-26,3.11-30, 3.11-48,3.11-49 through 3.11-81, 3.11-43,3.11-44,3.11-48, 3.11-82,3.11-83/3.11-84,3.11-91/
3.11-49 through 3.11-81, 3.11-92,3.11-93/3.11-94,3.11-95/
3.11-82,3.11-83,3.11-84, 3.11-96,3.11-97/3.11-98,3.11-103/
3.11-91,3.11-92,3.11-92a 3.11.-104, and 3.11-153 through through 3.11-92f,3.11-93, 3.11-162a/3.11-162b 3.11-94,3.11-94a through 3.11-94e,3.11-95,3.11-96, 3.11-96a through 3.11-96c, 3.11-97,3.11-98,3.11-98a, O.
3.11-103,3.11-104,3.11-104a through 3.11-104h,3.11-153 through 3.11-160, and 3.11-165 through 3.11-174 Appendix 3I 31-t i,31-i i i,31-i v,3I. 2-3,3I. 3-1 3I-ti,3I-iii,31-iv,31-iva, through 31.3-6,3I.4-1 through 3I.2-3,31.3-1 through 3I.3-6, 31.4-6,3I.5-1,3I.6-5,3I.6-6, 3I.4-1 through 31.4-7/3I.4-8, 31.7-3,3I.7-4,31.8-1,31.8-2, 31.5-1,3I.6-5/31.6-6,31.7-3/
31.8-7,31.8-8,3I.8-14,31.8-15, 3I.7-4,3I.8-1/31.8-2,3I.8-7, 31.8-17,31.8-19,3I.8-27, and 31.8-8,3I.8-14,31.8-15,31.8-17, 31.8-28 3I.8-19,3I.8-27, and 31.8-28 l
l l
$$$7
!!7 Amendment 19 July 22,1983 0
D PDR
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 CONTENTS (Continued)
Section Title Page 3.11.2.2.4.2.5.2 Product and Assembly Testing 3.11-59 3.11.2.2.4.2.5.3 Multiple-Frequency Tests 3.11-61 3.11.2.2.4.2.5.4 Single and Multiaxis Tests 3.11-61 I
3.11.2.2.4.2.5.5 Time Duration 3.11-62 3.11.2.2.4.2.5.6 Single Frequency Tests 3.11-62 3.11.2.2.4.2.5.7 Fragility Test 3.11-63 3.11.2.2.4.2.5.8 Damping 3.11-63 3.11.2.2.4.2.6 Design Basis Event Exposure 3.11-63 3.11.2.2.4.2.7 Post-Test In,spection 3.11-64
]
3.11.2.2.4.2.8 Modification 3.11-64 3.11.2.2.4.2.9
' Repairs 3.11-65 3.11.2.2.4.3 Operating Experience 3.11-65 3.11.2.2.4.3.1 dperating Environment 3.11-65
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(' }
3.11.2.2.4.3.2 Product Performance 3.11-66 3.11.2.2.4.3.3 Qualification Determination 3.11-66 3.11.2.2.4.4 Analysis 3.11-67 3.11.2.2.4.4.1.
Analytical Techniques 3.11-67 3.11.2.2.4.4.1.1 Similarity 3.11-67 3.11.2.2.4.4.1.2 Extrapolation 3.11-67 3.11.2.2.4.4.1.3 Mathematical Modeling 3.11-68 3.11.2.2.4.4.1.4 Dynamic Qualification by Analysis 3.11-68 3.11.2.2.4.4.1.4.1 General Requirements 3.11-69 3.11.2.2.4.4.1.4.2 Mathematical Model 3.11-70 3.11.2.2.4.4.1.4.3 Analysis and Design 3.11-71 3.11.2.2.4.4.1.4.4 Three Components of Motion 3.11-72 3.11.2.2.4.4.1.4.5 Static Analysis Method 3.11-73 3.11.2.2.4.4.1.4.6 Dynamic Analysis Method-3.11-74 3.11. 2. 2. 4. 4.1. 4.16 J Modal Responses 3.11-74 3.11.2.2.4.4.1.4.6 2 Required Response Spectra 3.11-74 3.11.2.2.4.4.1.4.163 Time History Analysis 3.11-75
()
3.11.2.2.4.4.1.4.6.4 Generation of In-Product Spectra 3.11-75 3.11.2.2.4.4.2-Qualification Determination 3.11-76 3.11-111
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19
(
SECTION 3.11 Tables Table Title Page 3.11-1 Environmental Zones 3.11-85
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3.ll-2a Environmental Conditions for Containment (Outside Drywell) Equipment 3.11-91 f
3.ll-2b Environmental Conditions for Drywell Equipment 3.ll-92c 4
3.11-3 Environmental Conditions and Limits for Auxiliary Building Equipment 3.11-93 3.11-4 Environmental Conditions and Limits for Fuel Building Equipment 3.11-95 3.11-5 Environmental Conditions and Limits for Control Building Equipment 3.11-97 3.11-6 Environmental Conditions and Limits for' Diesel Generator Building Equipment 3.11-99 l
3.11-7 Environmental Conditions and Limits for Turbine Building Equipment 3.11-101 s
3.11-8 Notes for Tables 3.11-2 Through 3.11-7 3.11-103 3.11-9 Safety-Related Equipment Identifica-l tion and Environmental Qualification Summary 3.11-105 3.11-9 (B21)
Safety-Related Equipment and Environ-mental Qualifications Summary - Main Steam System 3.11-108 3.ll-9(B33)
Safety-Related Equipment Identifica-tion and Environmental Qualification i
I Summary - Reactor Recirculation System 3.11-113
- 3. ll-9 (Cll)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Rod Control System 3.11-114
- 3. ll-9 (C41)
Safety-Related Equipment Identifica-l tion and Environmental Qualification l
Summary - Standby Liquid Control l
System 3.11.115
- 3.11-9 (C51)
Safety-Related Equipment Identifica-l tion and Environmental Qualification Summary - Neutron Monitoring System 3.11-116
(~T 3.ll-9(C61)
Safety-Related Equipment Identifica-(_,).
Summary - Remote Shutdown System 3.11-117 tion and Environmental-Qualification 3.ll-v
GESSAR II 22A7007 238 NUCLEAR ISLAND R:v. 5 TABLES (Continued)
Table Title Page
- 3. ll-9 (C71)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Reactor Trip System 3.11-118 3.ll-9(D17)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Process Radiation Monitor-ing System 3.11-119 3.ll-9(D23)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Containment Atmosphere Monitoring System 3.11-120 3.ll-9(E12)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Residual Heat Removal System 3.11-121 3.ll-9(E21)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Low Pressure Core Spray System 3.11-123 3.ll-9(E22)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - High Pressure Core Spray System 3.11-124 3.ll-9(E31)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Leak Detection System 3.11-126 3.ll-9(E32)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - MS Positive Leakage Control Systems 3.11-131 3.ll-9(E51)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Reactor Core Isolation Cooling System 3.11-134 3.ll-9(Fll/
Safety-Related Equipment Identifica-13/15/16/42) tion and Environmental Qualification Summary - Fuel Handling Equipment and Accessories 3.11-136 3.11-9 (G41)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Fuel Pool Cooling and Cleanup System 3.11-137 3.11-vi
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 TABLES (Continued)
Table Title Page
- 3. ll-9 (H13)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Control Room Panels 3.11-140
- 3. ll-9 (H22)
Safety-Related Equipment Identifica-tion and Environmental Qualification Summary - Control Room Panels 3.11-143
- 3. ll-9 (P38)
Standby Gas Treatment System 3.11-144
- 3. ll-9 (P4 5)
Control Building Chilled Water System 3.11-144 3.11-9 (P5 3)
Pneumatic Supply System 3.11-145
- 3. ll-9 (P60)
Water Positive Seal Isolation Leakage control System 3.11-145
- 3. ] l-9 (P61)
Air Positive Seal Isolation Leakage control System 3.11-145
- 3. ll-9 (R4 3)
Diesel Emergency Power 3.11-146
- 3. ll-9 (T41)
Reactor Building HVAC 3.11-147
(~'
- 3. ll-9 (T49)
Safety-Related Equipment Identifica-( s)/
tion and Environmental Qualification Summary - Flammability Control System 3.11-147 3.11-9 (XA3)
Diesel Generator Building HVAC 3.11-148
- 3. ll-9 (X6 3)
Fuel Building HVAC 3.11-150
- 3. ll-9 (X73)
Auxiliary Building HVAC 3.11-151
- 3. ll-9 (X9 3)
Control Building HVAC 3.11-152 3.11-10 Selected GE Positions on NUREG-0588 3.11-153
)
3.11-11 Example of a Test Sequence for Type Testing 3.11-161 3.11-12 Recommended Margins 3.11-162 tv 3.ll-vii/3.ll-viii
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 i
)
SECTION 3.11 ILLUSTRATIONS f
Figure Title Page 3.11-1 Drywell and Containment Environmental Zones 3.11-163 3.11-2 Post-LOCA Containment Semi-Infinite Beta 3.11-165 Dose Rate 3.11-3 Post-LOCA Containment Gamma Dose Rates 3.11-166 and Doses 3.11-4 Post-LOCA Drywell Doses 3.11-167 3.11-5 Post-LOCA Doses for Remaining Areas of Auxiliary Building 3.11-168 3.11-6 Post-LOCA Steam Tunnel Beta Dose 3.11-169 3.11-7 Post-LOCA Steam Tunnel Gamma Dose 3.11-170 3.11-8 Post-LOCA Suppression Pool Fluid Contact Doses 3.11-171 3.11-9 Post-LOCA Beta Dose 3.11-172 3.11-10 Post-LOCA Gamma Dose 3.11-173
()
3.11-11 Post-LOCA SGTS Filter Cubicle Dose Rates and Doses 3.11-174 4
'Q b
3.ll-ix/3.ll-x
GESSAR II 22A7007 238 NUCLEAR ISLAND Rav. 5 O
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3.11.2.1.2.2 Section XI - Test Control (Continued) test procedures include provisions for assuring that prerequisites for the given test have been met for mandatory hold points (where applicable), for acceptance and rejection criteria, and for appro-
~
priate methods of documenting test results.
Prerequisites include such items as appropriate and calibrated test equipment,. trained test personnel, completion status of the specimen to be tested, suitable environmental conditions, and provisions for data acqui-sition and storage.
Test procedures for procured products are based on engineering design and ASME code requirements and, when prepared by the sup-plier, are approved by assigned GE engineering or QA personnel.
S Product test results are documented, reviewed, and evaluated by designated QA engineering personnel prior to release for shipment to assure that test requirements have been satisfied.
3.11.2.1.3 Conformance to NUPEG-0588
~
L The following discussion provides an itemized account of the GE interpretation of the NRC staff positions on environmental qual-g ification as published in the 1979 "For Comment" version of NUREG-0588.
The format and sequence are consistent.witn that of NUREG-0588.
Each position statement is reprinted as it appears in the i
staff document, followed by the GE position.
Where the GE position differs from that of~the staff, justification is,provided.
m
- 3. -
v 3
t a-3.11-11 n;
i GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
3.11.2.1.3.1 Establishment of Qualification Parameters for
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Design Basis Accidents 3.11.2.1.3.1.1 Temperature and Pressure Conditions Inside Containment Loss-of-Coolant Accident (LOCA) a.(1)
NRC Staf f Position 1.1. (1) :
The time-dependent temperature and pressure, established for the design of the containment structure and found acceptable by the staff, may be used for environmental qualification of equipment.
a.(2)
GE Position:
The time-dependent temperature and pressure, established for the design of the containment structure and found acceptable by the staff, may be used for environmental qualification of equipment.
Alternate methods may be used by the applicant subject to NRC m
approval.
b.(1)
NRC Staff Position 1.1.(2):
Acceptable methods for calculating and establishing the con-tainment pressure and temperature envelopes to which equipment should be qualified are summarized below.
Acceptable methods for calculating mass and energy release rates are summarized in Appendix A.
e Boiling Water Reactors (BWRs) e Mark I, II, and III Containment Calculate LOCA environment using methods of GESSAR Appendix 3B or equivalent industry codes.
Additional guidance is provided in SRP Section 6.2.1.1.C, NUREG-75/087.
3.11-12
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 5
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3.11.2.1.2.1.1 Temperature and Pressure Conditions Inside Contain-ment Loas-of-Coolant Accident (LOCA) (Continued) l b.(2)
GE Position:
Guidance for establishing methods for calculating mass and energy release rates for GESSAR II are provided by the following:
e Mark III Containment Design NEDO-20533, The General Electric Mark III Pressure Suppression Containment System Analytical Model e
other methods found acceptable by the NRC.
c.(l)
NRC Staff Position 1.1.(3):
-s V
In lieu of using the plant-specific containment temperature and pressure design profiles for BWR and ice condenser types of plants, the generic envelope shown in Appendix C may be used for qualification testing.
c.(2)
GE Position:
The generic envelope shown in Appendix C of NUREG-0588 may be used for qualification testing of the product in the drywell in lieu of using plant specific containment temperature and pressure design profiles for BWRs.
d.(1)
NRC Staf f Position 1.1. (4) :
The test profiles included in Appendix A to IEEE Std. 323-1974 should not-be considered an acceptable alternative in lieu of (h
(,j.
using plant-specific containment temperature and pressure 3.11-13
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 9
3.31.2.1.2.1.1 Temperature and Pressure Conditions Inside Contain-
~
ment Loss-of-Coolant Accident (LOCA) (Continued) design profiles unless plant-specific analysis is provided to verify the adequacy of those profiles.
d.(2)
GE Position:
The test profiles in Appendix A of IEEE 323-1974 shall not be considered acceptable unless plant-specifi, analysis is provided to justify such profiles.
3.11.2.1.3.1.2 Temperature and Pressure Conditions Inside Containment - Main Steamline Break (MSLB) a.(1)
NRC Staf f Position 1. 2. l(1) :
The environmental parameters used for equipment qualification m
should be calculated with a plant-specific model reviewed and approved by the staff.
a.(2)
GE Position:
The environmental parameters used for equipment qualification should be calculated with a plant-specific model reviewed and approved by the staff.
b.(1)
NRC Staff Position 1.2.(2):
Models that are acceptable for calculating containment parameters are listed in Subsection 1.1. (2).
b.(2)
GE Position:
See GE Position 3.ll.2.1.3.1.1.b(2).
g 3.11-14
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
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3.11.2.1.3.1.5 Environmental Conditions for Outside Primary Containment a, (1)
NRC Staf f Position 1. 5. (1) :
Equipment located outside containment that could be subjected to high energy pipe breaks should be qualified to the conditions resulting from the accident for the duration required.
The techniques for calculating the environmental parameters described in Subsections 1.1 through 1.4 above should be applied.
a.(2)
GE Position:
Products important to safety located outside primary contain-O' ment that could be subjected to high energy pipe breaks shall be qualified to the conditions resulting from the accident l
for the duration required.
The techniques for calculating l
the resulting environmental parameters described in GE Position Statements 3.11.2.1.3.1.1 through 3.11.2.1.3.1.4 shall be applied.
b.(1)
NRC Staf f Position 1.5. (2) :
Equipment located in general plant areas outside containment where equipment is not subjected to a design basis accident environment should be qualified to the normal and abnormal range of environmental conditions postulated to occur at the equipment location.
b.(2)
GE Position:
(~
For the purpose of this harsh environment program this staff
\\-
position is not applicable.
3.11-25
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
3.11.2.1.3.1.5 Environmental Conditions for Outside Primary Containment (Continued) c.(1)
NRC Staff Position 1.5.(3):
Equipment not served by Class lE environmental support systems or served by Class lE support systems that may be secured during plant operation or shutdown should be qualified to the limiting environmental conditions that are postulated for that location, assuming a loss of the environmental support system.
- c. (2)
GE Position:
E See Table 3.11-10.
3.11.2.1.3.2 Qualification Methods 3.11.2.1.3.2.1 Selection of Methods
- a. (1)
NRC Staf f Position 2.1. (1) :
Qualification methods should conform to the requirements of IEEE 323-1974, a.(2)
GE Position:
Qualification methods shall conform to the criteria defined in Subsection 3.11.2.2.4.
O 3.11-26
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
3.11.2.1.3.2.2 Qualification by Test (Continued)
- a. (2)
GE Position:
See Table 3.11-10.
- b. (1)
NRC Staff Position 2.2.(2):
Test results should demonstrate that the equipment can per-form its required function for all service conditions postu-lated (with margin) during its installed life.
- b. (2)
GE Position:
Test results shall demonstrate that the product can perform its design function for all service conditions postulated (with margin) during its installed life.
O 9
- c. (1)
NRC Staf f Poaition 2.2. (3) m The items described in Subsection 6.3 of IEEE Std. 323-1974, supplemented by Items (4) through (12) (NRC Staff Positions 2.2(4) through 2.2(12)) below, constitute acceptable guidelines for establishing test procedures.
- c. (2)
GE Position:
Subsection 3.11.2.2.4 defines the acceptable guidelines for establishing test procedures.
These procedures are consistent with Subsection 6.3 of IEEE Std. 323-1974.
- d. (1)
NRC Staf f Position 2.2. (4) :
When establishing the simulated environmental profile for
()
qualifying equipment located inside containment, it is pre-ferred that a single profile be used that envelops the 3.11-30
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
3.11.2.2.1 Scope (Continued)
The manufacturers and users of Class lE products are required to provide assurance that each product will meet or exceed its performance requirements throughout its installed life.
This is accomplished through a disciplined program of quality assurance that includes but is not limited to design, qualification, production quality control, installation, maintenance, and periodic testing.
It is the primary role of qualification to assure that, for each type of Class lE product, the design and the manufacturing pro-cesses are such that there is a high degree of confidence that the product will perform as required in the specified environment.
Other steps in the quality assurance program invoke strict design and manufacturing control to assure that all products of the same type match that which was qualified and are suitabley applied, n
installed, maintained, j
and periodically tested.
s The methods described in this subsection apply to work accomplished by the General Electric Nuclear Energy Business Operation (NEBO) as well as all its vendors and contractors.
3.11.2.2.2 Applicable Documents If a conflict exists between the requirements contained in this subsection and those in a listed document, those in this sub-section shall govern.
3.11.2.2.2.1 General Electric Documents The following document forms a part of these requirements:
(1)
EMI Susceptibility Test Specification
]
)
J 3.11-43
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 3.11.2.2.2.2 Codes, Standards, and Regulations The following codes, standards, and regulations, as interpreted by NEBO, form a part of theso requirements to the limits specified in this subsection:
(1)
NRC Regulatory Guides *'
No.
Title (a) 1.40 Qualification Tests of Continuous Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants (generally accepts IEEE 334-1971) h (b) 1.63 Electric Penetration Assemblies in Con-tainment Structures for Water-cooled Nuclear Power Plants (generally accepts IEEE 317-1976)
(c) 1.73 Qualification Tests of Electric Valve Operators Installed Inside the Contain-ment of Nuclear Power Plants (generally accepts IEEE 382-1972)
QSee Section 1.8 for revision and date.
O 3.11-44
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 5 O
3.11.2.2.2.2 Codes, Standards, and Regulations (Continued)
(j)
IEEE 650-1979 - IEEE Standard for Qualification of Class lE Static Battery Chargers and Inverters for Nuclear Power Generating Stations (k)
IEEE 634-1978 - IEEE Standard Cable Penetration Fire Stop Qualification Test (1)
IEEE 501-1978 (ANSI C37.98) - IEEE Standard Seismic Testing of Relays (m)
IEEE 535-1979 - IEEE Standard for Qualification of Class lE Lead Storage Batteries for Nuclear Power Generating Stations (4)
American Society of Mechanical Engineers (ASME)
(a)
ASME Boiler and Pressure Vessel Code Sections II, III,-
IV, V, VIII, and XI 3.11.2.2.3 Reference Documents (1)
IEEE 101, IEEE Guide for the Statisitcal Analysis of Thermal Life Test Data, The Institute of Electrical and Electronics Engineers, Inc. - 1972.
1 (2)
EPRI NP-1558, A Review of Equipment Aging Theory and Technology, Electric Power Research Institute, September 1980.
(3)
NUREG/CR-0275 (SAND 78-0067), An Experimental Investi-gation of Synergisms in Class 1 Components Subjected to LOCA Type Tests, Sandia Laboratories, August 1978.
D(_)
3.11-47
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
3.11.2.2.3 Reference Documents (Continued)
(4)
NUREG/CR-0401 (SAND 78-1452) and NUREG/CR-0276 (SAND 78-0799), Qualification Testing Evaluation Quarterly Reports, Sandia Laboratories, 1978.
(5)
NUREG-0588, Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, December 1979.
(6)
NUREG/CR-2156 (SAND 80-2149), Radiation Thermal Degrada-tion of PE and PVC:
Mechanism of Synergism and Dose Rate Effects, R.
Clough and K. Gillen, Sandia Laboratories, June 1981.
~
(7)
NUREG-0484, Rev.
l., Methodology for Combining Dynamic Responses, R.
K.
Mattu, April 1980 O
3.11-48
GESSAR II 22/57007 238 NUCLEAR ISLAND Rev. 19*
O 3.11.2.2.4 Program Description PROPRIETARY INFORMATION - provided under separate cover.
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- All pages are Revision 5 except for the following:
Revision 6 - Pages 3.11-54, 3.11-55, 3.11-63, 3.11-69, 3.11-70, 3.11-71, 3.11-72, 3.11-73, 3.11-74, 3.11-75, 3.11-76, 3.11-70 Revision 19 - Pages 3.11-51, 3.11-53, 3.11-56, 3.11-57, 3.11-58, 3.11-59, 3.11-59a, 3.11-59b, 3.11-60, 3.11-61, 3.11-62, 3.11-64, 3.11-67, 3.11-68, 3.11-77, 3.11-77a O
3.11-49 through 3.11-81
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19
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3.11.3 Qualification Results Applicant to supply.
t 3.11.4 Loss of Ventilation 4
Environmental conditions resulting from loss of ventilation (HVAC)
~
are presented in Tables 3.11-2 through 3.11-6, where applicable, for Nuclear Island areas except for the Radwaste Building.
The Radwaste Building does not contain any safety-related or safe shutdown equipment.
As noted in the tables, areas containing major equipment of safety-related systems are provided with safety j
grade cooling systems and as such are not affected by loss of ventilation.
The loss-of-ventilation environmental conditions shown in the tables are included in Nuclear Island design and equipment
(
g
)
specifications and are to be considered for environmental qualifi-cation of equipment.
The loss of ventilation calculations were based on maximum heat loads and considered operation of all operable equipment regard-less of safety classification.
l t
n O
V 3.11-82
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 o
3 m
3.11.5 Estimated Chemical and Radiation Environment 3.11.5.1 Chemical Environment Equipment located in the containment (outside of the drywell) is potentially subject to water spray from the containment spray mode of the RHR System.
In addition, equipment in the lower portions of the containment is potentially subject to submergence and wetting by pool swell and weir annulus backflow.
3.11.5.1.1 Containment Spray The containment spray is to be considered activated for a period of time between 10 minutes and 100 days
- post-LOCA.
Spray charac-teristics are 400 micron particle size (nominal minimum); 1.1 gpm
- This should not be necessarily construed as establishing a con-tinuous 100-day operating time for the Containment spray System.
O Actual operating time guidance is established in NEDO-24934 (BWR Emergency Procedure Guidelines).
3.11-83
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 3.11.5.1.1 Containment Spray (Continued)
~
h per square foot and 125 P temperature.
Water quality is given in Subsection 3.11.5.1.3.
3.11.5.1.2 Suppression Pool Wetting and Submergence The characteristics and extent and post-LOCA pool swell, and weir annulus backflow are given in Appendix 3B.
Water quality is given in Subsection 3.11.5.1.3.
3.11.5.1.3 Post-LOCA Water Quality The following water quality is based on fission product release of Regulatory Guide 1.7:
(1) pH = 4.5 to 7.0 O
(2) conductivity 1 21 p S/cm (3) 1 8 ppm 02' 5 1 ppm CO2
-5 (4) 1 2.0 x 10 g mole /1 dissolved salts available to deposit as dry salts upon evaporation from hot surfaces.
(5) 5 9.0 ppm undissolved solids (6) 1 60 ppb dissolved H arising from < 4% volume of H 2
2 in containment atmosphere.
3.11.5.2 Radiation Environments The radiation environments are given in Tables 3.11-2 through 3.11-6 for the various Nuclear Island buildings except for the Radwaste Building.
3.11-84
i
'r T
e
]
Table 3.11-2a ENVIRONMENTAL CONDITIONS FOR CONTAINMENT (OUTSIDE DRYWELL) EQUIPMENT
{
RH a Int Deta Int Gamma l'luence Condition Freq/
Tempe ra ture Tfinal Radiation Radiat{on (Ntn/
Li_mitigj, Condition
- Duration 40 Yrs
(*F)
(1)
Pressure (rads)1*2 (rads) 3 cm2)
Supp Data j
Eone CT-1 Containment - Above Ref ueling Floor, 84 '-7" E l t
I Normal !!VAC Summer / Winter 20 to 90
(-10.1 to 1.8 x 10 O
90/70
(-)).O inch H O 2
Abno rmal e Loss of HVAC 0 to 45 min avg 3
90 to 121 avg 20 to 90
(-10.1 to 0
I
(+11.0 inch H 0 y
45 min to 20 hr 3
121 50 to 100
(-)0.1 inch to l
(+)1.0 inch H O 2
20 hr to 27.5 hr 3 121 to 90 50 to 100
(-}0.1 to bJ
(+)1.0 inch H 0 f
y e Loss of oftsite Same as loss of HVAC power (HVAC powered by Non-Div *N" Bus - Interrupt offsite powert gg i
C3 Cl I
LJ e Isolation events
- (1 DG
't4 03 h'
4 2
M U3 (1,2,3,4,5,6,7,B, O to 30 min Note 1 90 to 120 100 0 to 1.75 osig 1.2 x 10 4.4 x 10 0
i f
3p 12.16) 30 min to 10 hr 120 100 1.75 psig (Note 2)
(Note 25 pg y) 40 tv 24 hr 120 to 90 20 to 90 1.75 to O psig i
g HH i
est (18)
O to 20 hr 12 90 20 to 90 8 psig 0
03 F4 Accider.t e Large HE pape O to 6 see 1
90 to 120 100 0 tc 6 psig Figure Figure CI break in drywell 6 to 45 see 120 to 150 100 6 to 9 nsig 3.11-2 3.11-3 45 see to 10 min 150 to 185 100 9 to 15 psig (Note 3)
(Note 31 10 min to 1 day 185 100 15 psig 1 to 100 days 185 to 90 100 15 to o psig j
Zone CT-2 Centainment - Above Suppression Pool, (-111 *-2" E l 1
l Normal HVAC Normal /Startup 20 to 90
(-)O.1 inch to (Note 4) 0 100/40
(-)1.0 inch H O l
2 e Hot standby 100 to 120 20 to 90
(-10.1 to 0
j
(-11.0 inch H O l
2 Abnormal e Loss of HVAC 0 to 45 min avg 3
100 to 121 avg 103 0 to 1.24 psig 0
I 45 min to 20 hr 121 100 1.24 osia sg h3 20 hr to 27.5. hr 121 to 100 100 1.24 to o psig m h3
'[
< DW I
e Loss of offsite Sare as loss of HVAC a
'e
=J power (HVAC powered by Non-Div *N* Bus - Interrupt offsite power)
C3 i
Fd C3 1
WD =J -
t
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 i
f t
i
+
..,,~ -
Table 3. l l-- 2 a ENVIRONMENTAL CONDITIONS FOR CONTAINMENT (OUTSIDE DRYWELL) EQUIPMENT (Continued)
RH 9 Int Beta Int Gamma Fluence Condition Freq/
Tempe ra t ure Tfinal Radiation Radiation (Ntn/
Limi t ing _C.mli t i on
- Curation 40 Yrs
(*F)
(t)
Pressure (rads)l,2 (rads)2,3 cm2)
Supp Data Zone CT-2 (Continued) e Isolation events 4
2 (1,2,3,4,5,6,7,8, O to 30 min Note 1 100 to 150 avg 100 0 to 1.75 psig 1.2 x 10 4.4 x 10 0
Note 5 12,16) 30 min to 10 hr 150 100 1.75 psig (Note 2)
(Note 2) 10 to 24 hr 150 to 100 100 1.75 to O psig Test (IS)
O to 20 hr 12 100 20 to 90 8 psig 0
Acc i d er. t PJ e snail HE pipe o to 45 see 1
100 to 150 0 to 9 psig La break in drywell 45 see to 10 min 150 to 185 9 to 15 psig 00 10 min to 1 day 185 15 psig 1 to 100 days 185 to 100 15 to O psig 25 C C1 o Large HE pipe O to 1.5 sec 1
100 to 125 0 to 15 psig Figure Figure 0
I) EU h, ),
ps break in drywell 1.5 to 4 see 125 15 psig 3.11-2 3.11-3 Fd 4 to 6 sec 125 to 120 15 to 6 psig (Note 3)
(Note 3)
)
I 6 to 45 see 120 to 150 6 to 9 psig 7g pg AD 45 to 10 min 150 to 185 9 to 15 psig bJ 10..In to 1 day 185 15 psig pq pa 1 to 100 days 185 to 100 15 to O psig 03 pq Zone CT-1 Containment - HCU F l cwo r,
11'-0* El No rma l hVAC Normal /Startup 20 to 70
(-10.1 to 7.0 x 10 0
C7 90/40
(-)1.0 inch H o y
Abnorral e Los s of KVAC 3 to 45 P.in avg 3
90 to 121 20 to 90
(-10.1 to O
(+ ) 1. 0 inch H O 2
45 min to 20 hr 3
121 50 to 100
(-)0.1 to
(+)1.0 inch H O 2
20 hr to 27.5 hr 3 121 to 90 50 to 100
(-)O.1 to
(+)l.0 inch H o y
e Loss of offsite Same as less of HVAC power (RVAC pcwered by Non-Div "N*
Bus - Interrupt offsite power) e Isolation events (1,2,3,4.5,6,7,8.
O to 30 min Note 1 90 to 120 100 0 to 1.75 psig 1.2 x 10*
4.4 x 10 0
00 bJ 12.16) 30 min to 10 hr 120 100 1.75 psig (Note 2)
(Note 2)
Q hJ 10 to 24 hr 120 to 90 20 to 90 1.75 to O psig 4 g,
%J
)
- (
) In this colann refers to event nar.ber of Note 1 of Table 3.11-8 pa c)
WD -J l
1 O
O O
i Table 3.ll-2a l
ENVIRONMENTAL CONDITIONS FOR CONTAINMENT (OUTSIDE DRYWELL) EQUIPMENT (Continued) j i
l f
RH 9 Int Beta Int Carnma Fluence Condition Freq/
Temperature Tfinal Radiat{on Radiation (Ntn/
trads) 2 (radsl2.3 cm2)
Supp Data Limitinj Condition
- Duration 40 Yrs
(*F)
(*)
Pressure Zone CT-3 (Continued) r Test (18)
O to 20 hr 12 50 20 to 90 8 psig
[
Accident I
e 1.arge HE pape O'to 6 see 1
90 to 120 100 0 to 6 psig Figure Figure 0
break in drywell 6 to 45 see 120 to 150 100 6 to 9 psig 3.11-2 3.11-3 J
45 see to 10 min 150 to 185 100 9 to 15 psia INote 3)
(Note 1)
(
10 min to 1 day 185 100 15 psig i
I to 100 days 185 to 90 100 15 to o psig
?
M Zone CT-4 Containment - SLCS At e%.
37*-1* El W
Normal HVAC Summer / Winter 20 to 90
(-10.1 to 1.8 x 10 90/70
(-11.0 inch H O 2
Abnormal MM H
e Loss of HVAC 0 to 45 min avq 3
90 to 123 20 to 90
(-10.1 to O
I
(+11.0 inch H O
[
2 l
45 min to 20 hr 3
121 50 to 100
(-10.1 to M
(+)1.0 inch H 0 U
y
.H H
]
20 hr to 27.5 hr 3 121 to 100 50 to 100
(-10.1 to mH
(+11.0 inch H O 2
I e loss of offsite Same as loss of HVAC power (HVAC powered by Die "N" Bus - Interrupt offsite power)
U
.[
t e isolation events f
4 I
2 t
(1,2,3,4,5.6.7,8 O to 30 min Note 1 90 to 120 100 0 to 1.75 psig 1.2 x 10 4.4 x 10 0
12.16) 30 min to 10 hr 120 100 1.75 psig (Note 2)
(Note 2) l 10 to 24 hr 120 to 90 20 to 90 1.75 to O psig Test (18)
O to 20 hr 12 90 20 to 90 8 psig Accident 4
t i
e Large HE pipe O to 6 sec 1
90 to 120 100 0 to 6 psig Figure Fioure i
break in drywelt 6 to 45 see 120 to 150 100 6 to 9 psig 3.11-2 3.11-3 45 see to 10 min 150 to 185 100 9 to 15 psig (Note 31 (Note.3)'
i l
10 min to 1 day 185 100 15 psig
-t i
1 to 100 days 135 to 90 100 15 to O psig Af M (D N
- (
) In this column refers to event number of Note 1 of Table 3.11-8
%J I
o wo t
W4 I
J
, _,..- _~ - -
_.. _ ~ _, _ _. _ _ _ _. _ _ _
Table 3.ll-2a ENVIRONMENTAL CONDITIONS FOR CONTAINMENT (OUTSIDE DRYWELL) EQUIPMENT (Continued)
Rif 4 Int Ise t a Int Gar.r.a I l' er.i c Condit on Freq/
TemDerature Tfinal Radiation Radia t f or; IN t;;
Limitin L Con.lition*
Juration 40 Yrs
(*F)
(t)
Pressure tradsi l**
cr - '
baFP Data
< r acts '*-
pne Q } Contai_ggent_ _ RWCU p g (Holding Py Lan,d Filter _Deminerg ire,r. 9 92 7," El Normal HVAC
- Pump Room 90 2C to 70
(-10.1 to
!L te 66 0
- F/D Rooms 105
(-11.0 inch HO 2
Abnormal e Loss of tiV AC 0 to 45 man 3
100 to 109 avq 20 to 90
(-10.1 to O
(PWCL pump and
(+t1.0 inch H O 2
g F'D) 45 man to 20 hr 3
109 20 to 90
(-10.1 to
(+11.0 inch H o g
y w
20 hr to 27.5 hr 3 109 to 100 20 to 90
(-10.1 to cQ
(+ )1.0 inch H O OM 2
H MW 4
2 H
e Less of oftsite O to I hr 100 to 127 20 to 90
(-10.1 to 1.2 x 10 4.4 x 10 0
M t/)
I power isalaticn 0 inch H2O (E te 2)
(Note 2) event WW N
(All HVAC equip (RWCU HVAC powered by Div N1 and N2 Buses - normal power. DG backed, shed on LOC?. only; containment HVAC HH H
exc1 RWCU rooms) powered by Non-Div "N" Buses - Interrupt offsite power) z Test 0 te 20 hr 12 100 20 to 90 8 psia y
- ccident e Large HE pipe O to 6 see 1
100 to 120 100 0 to 6 psig Figure Fiqare 0
breik in drywell 6 te, 45 see 120 to 150 100 6 to 9 psig 3.11-2 3.11-3 45 see to 10 mie 150 to 185 100 9 to 15 psig (Note 33 (Note 3) 10 man to 1 day 185 100 15 psag 1 to 100 days 185 to 100 100 15 to O psia
- (
) In this colurn refers to event number of Note 1 of Table 3.11-8 WM mN
. 4 O
HO (D 4 O
O O
(d
('~
f 3
N Table 3.ll-2b i
ENVIRONMENTAL CONDITIONS FOR DRYWELL EQUIPMENT fci e Int Beta Int Gamma Fluence Condition Freq/
Temperature Tfinal Radiation Radiation (Ntn/
Limiting Condition
- Duration 40 Yrs
(*F)
(O Pressure (rads)ie2 (rads)2,3 cm2)
Supp Data Zone DW-1 Drywell - Outside RPV Shield Wall - Not at Core Midplane Normal HVAC 135 20 to 90 12 psig (Note 7)
(Note 7) e Refuelin9 70 20 to 90 12 psig Abnormal e loss of HVAC 0 to 16 min 3
135 to 242 1 to 90 0 to 3 psig 16 to 58 min 242 to 251 1 to 90 3 to 2 psig 58 min to 5 hr 251 to i'5 1 to 90 2 to 0 psig g
e Loss of offsite No impact - Same as normal power (HVAC powered by Div N1 and N2 Buses - normal power, DG backed, shed on LOCA only) ha e Isolation events 0 to 75 sec 50 135 to 150 15 to 60 0 to 2 psig 1.2 x 10 4.4 x 10 Note 8 2
. W 75 see to 30 min 150 to 135 20 to 90 2 to O psi 9 C3 tr3 t" CA P
Test (17)
O to 20 hr 12 100 20 to 90 3 psig t:3 (n
- H
- I Accident MM W
M
.e Large HE pipe O to 1.5 see 1
135 to 330 Steam 0 to 30 psig Figure Figure HH O
break in drywell 1.5 to 40 sec 330 Steam 30 psig 3.11-4 3.11-4 UH 40 to 45 sec 330 to 250 Steam 30 to 15 psig (Note 9)
(Note 9) 45 see to I hr 250 Steam 15 psig 1 hr to 1 day 250 100 15 to 5 psig g
1 to 100 days 250 to 135 100 5 to o psig Zwa DW-2 Drywell - Outside RPV Shield Wall - At Core Nidplane Normal HVAC 135 20 to 90 12 psig (Note 7)
(Note 7)
. e Refueling 70 20 to 90 12 psig Abnormal e loss of HVAC 0 to 16 min 3
135 to 242 1 to 90 0 to 3 psig 16 to 58 min 242 to 251 1 to 90 3 to 2 psig 58 min to 5 hr 251 to 135 1 to 90 2 to 0 psig e loss of offsite No impact - Same as normal
-power (HVAC powered by Div N1 and N2 Buses - Normal power, DG backed, shed on LOCA only) e Isolation events 0 to 75 sec 50 135 to 150 15 to 60 0 to 2 psig 1.2 x 10 4.4 x 10 Note 8 AS M 75 see to 30 min 150 to 135 20 to 90 2 to o psig 2N
. w
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 g.~
l
Table 3.ll-2b ENVIRONMENTAL CONDITIONS FOR DRYWELL EQUIPMENT (Continued) mi
.m
- 25.
Condition Freg '
Terperature Tgina; t >
Pres 5Jre
!r3dS ***
- 5 **
N1_[O Limiting Condition
- Duration 40 Yrs
(*F)
Zone DW-2 : Con *. in aed )
Test (17)
C to 20 hr 12 100 20 to 93 3 psig Accident e Large HC pipe O to 1 5 see 1
135 to 330 Stean 0 to 30 pst:
r i.: s break in drywell
- 1. 5 to 4 0 sec 330 Steam 30 psig 3.1;-4
.;-4 40 to 45 sec 330 to 250 Steam 30 to 15 psi ;
Nete 3
+ 9 45 sec to 1 hr 250 Steam 15 osia 1 hr to 1 day 250 100 15 to 5 psta M
I to 100 days 250 to 135 100 5 ts O psia a
Zo_ne_DW,3_Drywell - Under FPV Inside Pejestal
~
4
,o'*
yg Normal ItVAC 135 20 to 90
-2 ps1a s
g OM p y3 Abnormal g
M U2 e Loss of HVAC 0 to 3 min 3
135 to 276 1 to 90 0 to 3 psia H
i;)
with scram 3 to 58 min 276 to 251 1 to 90 3 to 2 psig yy g
58 min to 5 hr 251 to 135 1 to 90 2 to O psia H H N
Q.
CO H e Ix>ss of offsite No impact - Same as normal power (HVAC powered by Div Ng and N2 Buses - Normal power, DC backed, shed on LOC; c ;y -
e Scram with 0 to 1 min 50 135 to 185 6 to 30 U
isolation 1 to 30 min 185 6 to 30 30 min to I hr 185 to 150 15 to 60 1 to 2 hr 150 to 135 90 4
e Scram without 0 to 1 min 150 135 to 185 6 to 30 1x 10 4.4 x 10' isolation 1 to 30 min 185 6 to 30 30 min to I hr 185 to 135 90 Test 0 to 20 hr 12 100 20 to 90 3 psig Accident e Large HE pipe O to 1.5 see 1
135 to 330 Steam o to 30 psig ricare ria;re o
break in drywell
- 1. 5 t o 4 0 sec 330 Steam 30 osig 3.11-4 3.11-4 40 to 45 sec 330 to 250 Steam 30 to 15 psig (Note 9:
(Note 91 45 see to I hr 250 Steam 15 psig i hr to 1 day 250 100 15 to 5 osig 1 to 100 days 250 to 135 100 5 to O psig MN O N 4
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 O
HO W4 O
O O
1--
e O
O Table 3.11-2b ENVIRONMENTAL CONDITIONS FOR DRYWELL EQUIPMENT (Continued)
RH @
Int Beta Int Gam: ta Fluence Condition Freq/
Temperature Tfinal Radic tio n Radiation (Ntnf Limiting Condition
- Duration 40 Yrs
(*F)
(t)
Pressure trads)1 2 frads)2*3 cm2)
SJPP Data Zone DW-4 Drywell - Chee, Within Drywell Head Normal HVAC 151 10 to 90 t2 psig 2.7 x 10 6.0 x Note 10 1014 Abrormal e Loss of HVAC 0 to 4 min 3
151 to 155 1 to 30 0 to 3 psig Note 11 4 to 58 min 155 1 to 30 3 to 2 psig 58 min to 5 hr 155 to 151 1 to 30 2 to o psig e Loss of offsite No impact - Same as normal power (HVAC powered by Div Ng and Ny Buses - Normal power, DG backed, shed on 14CA only) g e Scram with and 1.2 x 10 4.4 x 10 without isolation w
Test 0 to 20 hr 12 100 20 to 90 3 psig c)
OM M
Accident M (/l H
M (n i
e Large HE pipe o to 1.5 see 1
151 to 330 0 to 10 psig Figure Figare W
break in drywell 1.5 to 40 sec 330 30 psig 3.11-4 3.11-4 N
40 to 45 sec 330 to 250 30 to 15 psig (Note 9)
(Note 9)
O 45 see to I hr 250 15 psig HH QH 1 hr to 1 day 250 15 to 5 os.g h
1 to 100 days 250 to 151 5 to o psig z
Zone DW-5 Drywell - Outside RPV 6tirt (Inside Shield Wall) g Normal HVAC 135 20 to 90
!2 psig 2x 10' 1x 10 14 Abnormal e Loss of HVAC 0 to 3 min 3
135 to 276 1 to 90 0 to 3 psig 3 to 58 min 276 to 251 1 to 90 3 to 2 psig 58 min to 5 hr 251 to 135 1 to 90 2 to O psig e Loss of offsite No impact - Same as normal power (HVAC powered by Div Ng and Ny Butes - Normal power, DG backed, shed on LOCA only) e Scram with and 1.2 x 10 4.4 x 10 without isolation Test 0 to 20 hrs 12 100 20 to 90 3 psig
%N
- (
) In this column refers to event number of Note 1 of Table 3.11-8 M
e M
O t-' O W4
Table 3.ll-2b ENVIRONMENTAL CONDITIONS FOR DRYWELL EQUIPMENT (Continued)
FH a Int beta
- nt Cama f'l u e nc e Condition Fregr Temperature Tfinal Fadiation Fadiation (Ntn Limitin M ondition*
Duration 40 Yrs
(*F)
(4)
Pressare tradsi l2 trads)2.3 cr23 Surr Data Zone DW-5 (Continuedi Accident e Large HE pipe O to 1.5 sec 1
135 to 339 Steat O to 30 psig Flaare Fi nre 0
break in d rywe ll 1.5 to 40 sec 130 Stean 30 psig 3.11-4 3.11-4 40 to 45 sec 330 to 250 Stear 30 to 15 psi :
.Nate 9#
(Note 93 45 see to I hr 250 Steam 15 psia 1 hr tc 1 day 250 100 15 to 5 psig 1 to 100 days 250 to 135 100 5 to o psig PJ Zone DW-6 Drywell - Annulus Between RPV and FPV Shield Wall LJ 10 10 '
Normal HVAC 5 :. /i 1 to 30
(-10.5 to 1.8 x 10 4 x
+1.5 inch HO
~
2 y
cc e
Abnormal e loss of HVAC 0 to 25 man 3
550 to 575 1 to 5 0 to 3 ps19 h
I 25 to 58 man 3
575 to 475 1 to 5 3 to 2 psig yy 58 min to 5 hr 3
475 to 135 6 to 90 2 to O psig HH e Ioss of offsite No impact - Sare as normal U1 M power (HVAC powered by Div Ng and Ny Buses - Normal power, DG backed, shed on LOCA only) e Scram with and 1.4 x 10 4.4 x 10 U
without isolation Accident e Large HE pipe O to 1.5 see 1
550 Steam 0 to 30 psig figure F11are o
break in drywell 1.5 to 40 sec 550 Steam 30 psig 3.11-4 3.11-4 40 to 45 sec 550 Steam 30 to 15 psig (Note 9)
(Note 91 45 see to I hr 550 to 250 Steam 15 psig I br to 1 day 250 109 15 psig 1 to 100 days 250 to 100 ICJ 15 to O psig
- (
) In this column refers to event number of Note 1 of Table 3.11-8 WN (D M
-J O
ld O W -J O
O O
l
(
Table 3.11-3 ENVIRONMENTAL CONDITIONS FOR AUXILIARY BUILDING EQUIPMENT RH 9 Int Beta Int Gamma Fluence
' Condition Freq/
Temperature Tfinal Radiat{og Radiatgog Wtn/
cm2)
Surp Data Limiting Condition
- Duration 40 Yrs
(*F)
(t)
Pressure (rads) '
trads) zone AB-1 Auxiliary Building - Electric Switchgear Area at 11'-0" El and Remote Shutdown Panel Room at
(-16*-10" El Normal HVAC Summer / Winter 20 to 60
(-)0.1 to
<1.2 x 10 0
90/60 0.25 inch H O 2
Abnormal e loss of HVAC No impact - (Has standby HVAC equipment for switch gear rooms, and remote shutdown panel room cooler only required to operate during evacuation of Control Building.)
e loss of offsite No impact - (HVAC equipment powered by Div *ESF" Buses) power w
w Accident CD e large HE pipe 0 to 100 days 1
104 8 to 60 0.25 to 0 inch Figure Z
break in drywell HO 3.11-5 CO 2
W (LOCA-DBA)
(Note 12)
OM (12)
MM H
M U1
'y zone AB-2 Auxiliary Building - LPCS, HPCS, and RHR "C" Rooms (ECCS Areas),
(-)32'-0" El Normal HVAC Summer / Winter 20 to 90
(-10.25 to 5.2 x 10 0
ys 104/60
(-)1.0 inch H O u3 H 2
Abnortaal e Loss of HVAC No impact - (Due to redundant nature and location of ECCS equipment, no standby HVAC equipment is required or provided)
U
.e Loss of offsite No impact - (HVAC equipment powered by Div "ESF" Buses) power 3
e Isolation events
'O to 2 min 133 104 to 122 8 to 35
(-10.25 to 5.2 x 10 0
(HPCS) 122 8 to 35
(-10.25 to
(-)1.0 inch H O (Note 13) 2 (1,2,3,5,8,9,11,:
2 to 30 min 12,14,23,28,29)
(-)1.0 inch H O 2
30 to 45 min 122 to 104 20 to 90
(-10.25 to
(-)1.0 inch H O 2
Test-0 to 2 min 1163 104 to 122 8 to 35
(-)0.25 to 0
(1,2,3,4,10,12)
(-)1.0 inch H O 2
2 min to 1 hr 122 8 to 35
(-)0.25 to
(-11.0 inch H O 2
1 to 1.5 hr 122 to 104 20 to 90
(-10.25 to
(-)1.0 inch H O 2
yg (D PJ
- ( ) In this column refers to eient number of Note 1 of Table 3.11-8 O
&O WM 1
Table 3.11-3 ENVIRONMENTAL CONDITIONS FOR AUXILIARY BUILDING EQUIPMENT (Continued)
RH #
Int Beta Int Garr.a Fluence Condition Freq/
Temperature Tfinal Radiat{cn Radiat(cq (Ntn/
Limiting Condition
- D ration 40 Yrs
('P)
(t)
Pressare trads!
'2 (rads)
cm')
Supp Data J
Zone AB-2 (Continued)
Accident e large HE pipe O to 2 min 1
104 to 122 8 to 35
(-)O.25 to (Note 14)
(Note 14) 0 break in drywell 0 inch H O 2
(LO:A-CBA) 2 min-100 days 122 8 te 35 0 to (12)
(-) 0.25 inch H O 2
e HE pipe break in 0 to 24 see 1
104 to 250 100 0 to 1.6 psig 2.0 x 10 1.3 x 10 0
adjacent zone 24 sec to 6 hr 250 to 212 100 1.6 psig IUIR "C" only 6 to 12 hr 212 to 150 100 1.6 to 0.5 psig N
(15) 12 hr to 100 days 150 to 104 100 0.5 to O psig y
Zone AB-3 Aaxiliary Building - FCIC Turbine and Pump Roe,m (ECCS Areal,
(-)32*-0" El h
Normal HVAC 6
g Summer / Winter 20 to 90 t-10.25 to 1.3 x 10 0
104/60
(-)l.0 inch H O 2
p gf3 Hg Abnormal M t/3 y>
l NN w
e Loss of :iVAC No impact - (Due to redundant nature and location of ECCS equip, no standby HVAC equipment is required or provided1 A
HH e Loss of offsite No impact - (hVAC equipment powered by Div "ESF" Bus)
C/1 H power 6
e Isolation events 0 to 6 min 136 104 to 122 8 to 35
(-)0.25 to 1.3 x 10 0
y (1,2,3,4,5,6,7,0,
(-11.0 inch H O (Note 13) 2 9,11,12,14,24,28) 6 to 30 min 122 8 to 35
(-)0.25 to
(-11.0 inch H O y
30 min to I hr 122 to 104 20 to 90
(-10.25 to
(-11.0 inch H O y
Test 0 to 12 min 663 104 to 122 8 to 35
(-10.25 to 2.8 x 10 0
(1,2,3,5,11)
(-)1.0 inch H O 2
12 to 45 min 122 to 104 20 to 90
(-10.25 to
(
'l.0 inch H o y
Accident 4
3 e HE pipe break in 0 to 0.6 see 1
104 to 160 All steam 0 to 2 psig 2.0 x 10 1.3 x 10 0
adjacent zone 0.6 see to 6 hr 160 to 212 100 2 psig (15) 6 hr to 100 days 212 to 104 100 2 to O psig e Large HE pipe O to 2 min 104 to 122 8 to 35
(-10.25 to (Note 14)
(Note 14) 0
%M break in drywell 0 inch H O (D N 2
(12) 2 min to 100 days 1 122 8 to 35 0 to
(-)0.25 inch H O
'J 2
O
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 i
i O
O O
i
'\\
(
w Table 3.11-3 ENVIRONMENTAL CONDITIONS FOR AUXILIARY BUILDING EQUIPMENT (Continued)
RH
- Int beta Int Camma Fluence Condition Freq/
Terperature Tfinal Radiation Radiation (Ntg/
Limiting Condition
- Duration _
4 B rs
_,y)_
,1%)_.
Pressure trads)l*2 (rads 12.3 cm 1 Supp Data Zone AB-4 Auxiliar'L_BM1,dirjg,- RHR PurLRooms "A" and "B"
(ECCS Area),
f-132'-0" El 3
Norral HVAC 151 Summer / Winter 8 to 90
(-10.25 to 5.d x 10 0
(including shutdown 104/60
(-11.0 inch H O 2
and refueling)
(9.11)
Abnormal-e !4ss of HVAC No impact - (Due to redundant nature and locationof ECCS equipment no standby HVAC equipment is required or provided) e N
o Ioss of offaite HVAC equipment powered by Div "ESF" Buses W
power e Isolation events O to 6.5 min 115 104 to 122 8 to 35
(-10.25 to 5.8 x 10 0
g (1,2.3.4.5.6,7,8,
(-)1.0 inch H O (Note 13)
CO 2
y e
14.27,28.29) 6.5 min to 49 hr 122 8 to 35
(-10.25 to ng g
H
(-)1.0 inch H O p (f3 2
H 49 to 52 hr 122 to 104 20 to 90
(-10.25 to M t/3 i
(-)1.0 inch H 0 y
l0 :c db Test' 0 to 6.5 min 2241 104 to 122 8 to 35
(-10.25 to 0
(
(1,2,3,16)
(-)1.0 inch H O HH 98 2
.6.5 min to 1 hr 122 8 to 35
(-)0.25 to C/1 M
(-11.0 inch H O 2
1 to 4 hr 122 to 104 20 to 90
(-)3.25 to
(-11.0 inch H2O g
Accident 4
e Large HE pipe O to 6.5 min 1
104 to 122 8 to 35
(-10.25 to (Note 14)
(Note 141 0
break in drywell 0 inch H O 2
(12) 6.5 min to 122
(-10.25 to 100 days 8 to 35 0 inch H O 2
4 e HE pipe break in.
.O to 24 see 1
104 to 250 All steam 0 to 1.6 psig 2.0 x 10 1.3 x 10 0
adjacent zone'
.24 see to 6 hr 250 to 212 All steam 1.6 psig (15).
-6 to 12 hr 212 to 150 100 1.6 to 0.5 psig 12 he to 100. days 150 to 104
-100 0.5 psig Zone AB-5 Auxiliary Building - RWCU Pump Rooms, (-16 '-10" El 5
Normal HVAC Summer / Winter 20 to 60
(-10.25 to 1.8 x 10 100/60
(-)1.0 inch H 0 y
- 23 M fD M
- ( 1-In this column refers to event number of Note 1 of Table 3.11-8 4>
+ 4 O
HO
@M i
i P
l Table 3.11-3 ENVIRONMENTAL CONDITIONS FOR AUXILIARY BUILDING EQUIPMENT (Continued) l F'i d h*,
- : ;c. r.a
'4 x r.,-
Ccr.diticr Treg' Teg erat re
!tira.
Ud**-
'; l T Lit,qing Canditic"*
Daration 40 Yrs
('
(;!
Trcss;:n rads y;2
'rgds g*
[gLpg l
Eme AS-5 (Continued)
Abnormal o
e Loss of HVAC 0 to 8 min 10 100 to 151 5 to to
-ic.13 ?
t-
..C 1 r. :r M,
8 to 20 man 151 to 100 5 tc 90
.-:0.25 t-(-il.0 incn tg a Loss of offsite O to 27 see 10 ICL to 104 17 ta CD i-)C.2'.
ta C
power 6'.0 1 r. cn L.,.
27 see to 17 mir-104 to 100 17 to 90
(-10.25 tc g
y
.f m
t-s1.0 I r.c h 1
(HVAC pcwered by Div Ng and Ny Bases - Normal power, DG t:a c k e d, shed : r. LX A cr.1 2
W CQ Accident OM H
t* tn H
e Large HE pipe O to 100 days 100 to 150 5 to 60 t-10.25 te
' - +,
.4
,e 14, o
M C/l I
break in drywell t-11.0 I r.ch jig
%N e HE pipe break in 2 " s
.0 x la 0
PWCL' compa rtr.ent t*
Zone AB-6 Auxiliary _Bu11 ding - Corridors Outside of ECCS Rooms
-)12'-0*
El t
Normal HVAC Summer / Winter 20 to 90 1-10.25 to 2 x 10 0
g 90/60 1-11.0 inch li O 2
Abnormal e Loss of HVAC 0 to 10 min 10 90 to 94 15 to 90 1 - > 0. 2 5 t o c
10 min to 10 hr 94 15 to 90 e Loss of offsite O to 10 min 10 96 to 94 15 to 90
(-10.25 tc O
power 0 inch H30 10 min to 2.5 hr 94 15 to 90 (HVAC - Pressure control supply suppressien and exhaast fans - Tcwere.i by Ncn-01*/
"N" Bas. Interrupt cffsite power)
Accident Large HE pipe break 0 to 100 days 1
90 20 to 90
(-10.25 te riaure 0
NN in drywell 0 inch H 0 3.11-5 3'
(LOCA-DBA)
(Note 12)
O
- (
) In this column refers to event number of Note 1 of Table 3.11-8 HC WW O
O O
~
.,O b
b x;
\\
Table 3.11-3 ENVIRONMENTAL CONDITIONS FOR AUXILIARY BUILDING EQUIPMENT (Continued)
RH e Int Beta Int Gamma Fluence Condition Freg/
Temperature Tfinal Radiation Radiation (Ntn/
Limiting Condition
- Duration 40 Yrs
(*F)
It)
Pressure jrads)le2 Qads)2.1 cm2)
Supp Data
_ Zone AB-7 Auxiliay Building - Sy am Tunnel 9'-0"613'-0" El g
Normal HVAC Summer / Winter 10 to 90
(-10.25 to 9.5 x 10 0
122/60 o inch H O y
. Abnormal e loss of HVAC 0 to 11 min 10 122 to 180 0.8 to 25
(-10.25 to 0
0 inch H O 2
11 min to 1 hr 180 0.8 to 25
(-10.25 to 0 inch H O 2
i i to 2.5 hr 180 to 122 10 to 90
(-10.25 to O inch H O g
2 y
CD e Loss of offsite O to 11 min 10 (Similar to normal HVAC since HVAC powered by Div Ng and Ny Buses = Normal power, power 11 min to 2.5 hr DG backed, shed on LOCA only) g y
2.5 to 4 hr CO O t4 p
Accident t1 1/3
' H
@ U1 I
e Large HE pipe O to I hr 1
122 to 180 0.8 to 25 0 to 2 psig Figure Figure 0
.P >
W break in drywell I hr to 100 days 180 to 150 4 to 42 2 to 0.5 psig 3.11-6 3.11-7 WW (LOCA-DBA)
(Note 12)
(Note 12)
O-HH e HE pipe break 0 to 0.5 see 1
122 to 240 All steam 0 to 5 psig (Not significantt 0
MH in steam tunnel 0.5 see to I hr 240 to 325 All steam 5 psig (Not significant)
I to 2 hr 325 All steam 5 psig (Not significant) 2 to 6 hr 325 to 212 All steam 5 to 2 psig (Not significant)
Q 6 hr to 100 days 212 to 150 100 2 to 0.5 psig (Not significant) e Tornado.
O to 1.5 see 1
0 to (-)3 psig 0
1.5 to 45 sec
(-)3 poig 45 to 46.5 see
(-)3 to o psig Zone AB-8 Auxiliar L BuildinJ d attery Rooms (D R 1ng4 and Non-Div),
11*-0" El 2
Normal Summer / Winter 20 to 60
(-10.25 to 1.2 x 10 0
96/66 0 inch H O 2
e (Exhaust vent only (Minimum 12 air changes / hour vent rate for battery rooms) from switchgear area)-
Abnormal e Loss of offsite No impact - (Has standby vent fan for each battery room.
Also, each div battery room has of.e f an powered ty power Div "ESF" Bus)
WM (D N
- (
)'In this column refers to event number of Note 1 of Table 3.11-8
[
~o W4
=
Y
Table 3.11-3 ENVIRONMENTAL CONDITIONS FOR AUXILIARY BUILDING EQUIPMENT (Continued) pH a Int Beta Int Gamma Fluence Condition Freq/
Temperatere Tfinal Radiation Rad <ation (Ntn/
Limiting _ Condition
- Duration 40 Yrs
("F1 (t)
Pressure (rads,1,2 (rads)2*3 2)
Supp_ Data em Zone AB-8 (Continued)
Accident e HE pipe break in 1
Fiqure O
drywell 3.11-5 (Note 12)
Zone AB-9 Auxiliary Building,-, Air Positive, Seal, System Room, 28*-6" El Normal HVAC Summer / Winter 10 to 90 0 to 0.25 inch 1.2 x,10 1,20/60 HO N
y W
Norma 1 CD I
e Loss of offsite No impact - 4HVAC pcwered by Div *ESF" Bus, cooling coil supplied by FSW)
Z w
mwer CO OM M
li Accident UI p
I e HE pipe break in 1
Figure O
ND drywell 3.11-5 (Note 12) yg fA H gne,$D,{0,$udl{a g,ggil,qtng_- CRD Maintenance Room, Corridors Cable Tunnel. Llev Tower, Elev Eq dpment Roome,h!6*-lO_" El t
Normal HVAC Summer / Winter C3 e CRD Maint 75/60 20 to 90 0 to (-10.25 M.4 x 10 0
inch H o y
e Corr and C Tunnel 90/60 20 to 90 0 to 0.25 1.2 x 10 0
inch H O 2
e Elev Tower 90/60 20 to 90 0 to 0.25 1.2 x 10 0
inch H O 2
3 e Elev Equilwent 104/60 20 to 90 0 to 0.25
- 1. 2~ x 10 0
Room (1C1'-6" EI) inch H C 2
' Abnormal e Loss of I!VAC (No' maximum temp. control and no pressure contrull Stairwell 9 0 to 1 hr-47 min 90 to 130 10 to 60 0
gg 28'-6" EL gy
< l>
e loss of off_ site (HVAC equipment and CRD exhaust fan powered by Non-Div "N" Bus, interrupt offsite power) t
.Q power.
o HO
- (
) In this column refers to event number of Note 1 of Table 3.11-8 WQ G
O G
w%.;
r Table 3.11-3 Y
ENVIRONMENTAL CONDITIONS FOR AUXILIARY BUILDING EQUIPMENT (Continued)
~;
RH e Int Beta Int Gamma Fluence Condition Freq/
Temperature Tfinal Radiat{on Radiation (Ntg/
Limiting Condition
- Duration 40 Yrs
(*F)
(t)
Pressure (rads)
- 2 (rads)2'3 cm )
Sepp Data I
y Zone AB-1(e(Continued)
?N cident u
. e HE pipe break in 1
Same as Loss of )fVAC Figure C
^Jrywell
'e 3.11-5 (Note 12)
Zoe Ak-ll Auxiliary Building - General HVAC Equipment Re-oms,
28'-6" El 3
' Normal liVAC -
Sum:aer/ Winter 10 to 90 0 to 0.25 inch 1.2 x 10 0
.(HEV only)
~,. -'
..\\
104160 HO N
2 w
(Supply air fans provide CJt3ide air for Ventilation about 80*F only)
CD Abnormal W
g OM l
e Ioss of HVAC pm.
)
(w/Div 1 oper) 0 to 1.2 hr 104 to 130 10 to 90 0.25 to 0 inch Mm g.
K2O I
(w/Div 2 oper) 0 to 1.2 hr.
104 to 114 10 to 90 0.25 to 0 inch WW g_
HO 2
HH
' ' ;e Loss of offsite Summer / Winter 10 to 90 0.25 to 0 inch MH power (w/Div 1 104/60 HO U
y h
j or Div 2) g 4
(Vent fans powered by Div N1 and N2 Buses - Normal power, DG backed, shed on IOCA only) Similar to normal HVAC.
' Accident' e HE pipe break in 1
Same as loss of HVAC Figure O
crywell 3.11-5 l
(Note 12) e
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 WN 2N
+4 O
t-d o WM
O J
Table 3.11-4 ENVIRONMENTAL CONDITIONS FOR FUEL BUILDING EQUIPMENT RH 9 Int Beta Int Gamma Fluence Condition
'Freq/
Temperature Tfinal Radiation Radiation (Ntn/
LimitinLCondition*
Duration 40 Yrs
(*F)
(%)
Pr63sure (rads)l*2 (rads)2*3 cm2)
Supp Data Zone FB-1 Fuel Building - Fuel Pool Pump Area (Recire. and F/D Backwash Drain Purp Roomsi t-132'-0* El g
F Formal HVAC Summer / winter 35 to 90
(-10.1 to 1.9 x 10 0
Note 15 80/60
(-11.0 inch H O t
2 i
Abnormal e Loss of HVAC 0 to 6 min 10 80 to 120 12 to 30
(-)0.1 to 0
Note 16
(-11.0 inch H O 2
6 min to 1 hr 120 12 to 30
(-10.1 to
(-11.0 inch H O 2
1 to 1.5 hr 120 to 80 35 to 90
(-10.1 to
(-11.0 inch H 0 y
y W
e Loss of offsite 0 to 8 min 10 80 to 120 12 to 30
(-10.1 to 0
Note 17 OD power 0 inch H O 2
8 min to 2.5 hr 120 12 to 30
(-10.1 to 0 inch H O CO 2
w
- 2. 5 to 3 h r 120 to 80 35 to 90
(-10.1 to OM e
H 2
UM 0 inch H O M
M
. Accident 1
l WW W
e Large '!E pipe
.') to 10 min 80 to 120' 12 to 30
(-10.1 to 4.0 x 10 5.3 x 10 0
Note 19 W
break in drywell
(-)1.0 inch H,0 (Note 18)
(Note 18) and 20 HH gg 10 min to 1 day 120 12 to 30
(-10.1 to (100 days)
(-)1.0 inch H O 2
1 day to 100 days 120 to 80 35 to 90
(-10.1 to
(-11.0 inch H O Q
2 o Fuel handlinq 0 to 10 min 80 to 120 12 to 30
(-10.1 to 3.0 x 10 1.5 x 10 0
Note 19 accident
(-11.0 inch H O (Note 21)
(Note 21) and 20 2
10 min to 1 day 120 12 to 30
(-10.1 to (100 days)
(-)1.0 inch H O 1 to 100 days 120 to 80 35 to 90 s-10.1 to l
2
(-)1.0 inch H O 2
Zone FB-1A Fuel Building - FPCCU Filter /Demineralizer Backwash Tank Room,
(-)32*-0* El Normal HVAC Summer / Winter 25 to 65
(-10.1 to 5.1 x 10 0
Note 15 92/60
(-11.0 inch H O 2
Abnormal e Loss of HVAC 0 to 9 min 10 92 to 112 12 to 35
(-10.1 to 0
.ete. 22
(-11.0 inch H O 2
9 min to I hr 112 12 to 35
(-10.1 to NN
(-11.0 inch H 0 y
1 to 1.5 hr 112 to 92 25 to 65
(-10.1 to
, q
(-11.0 inch H 0 3
o
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 HO WW I
l
Table 3.11-4 ENVIRONMENTAL CONDITIONS FOR FUEL BUILDING EQUIPMENT (Continued)
PH a Int Beta Int Gamma Fluence Condition Freq/
Temperature Tfinal Radiaticn Radiation (Ntg/
Limiting Condition
- Daration 40 Yrs
(*F)
(t)
Pressure (radskl.2 (rads)2e3 cm )
Supp Data Zone FB-1A (Continued) e Loss of offsite O to 15 min 10 92 to 106 17 to 42
(-)0.1 to 0
Note 23 power 0 inch H o y
15 min to 2.5 hr 106 17 to 42
(-10.1 to 0 inch H O 2
2.5 to 3 hr 106 to 92 25 to 65
(-10.1 to
(-11.0 inch H O 2
Accident e Large HE pipe O to 10.ain 92 to 106 17 to 42
(-10.1 to 4.0 x 10 5.3 x 10 0
Note *19 N
break in drywell
(-)1.0 inch H O (Note 18)
(Note 18) and 20 2
10 min to 1 da) 1 106 17 to 42
(-)0.1 to (100 days)
(-11.0 inch H O 2
g 1 to 100 days 106 to 92 25 to 65
(-10.1 to cg
(-11.0 inch H o gg y
4 5
MM e Fuel handling 0 to 10 min 1
92 to 112 12 to 35
(-10.1 to 3.G x 10 1.5 x 10 0
Note 19 trj tt) g accident
(-)1.0 inch H,0 (Note 21)
(Note 21) and 20 g
g 10 min to 1 day 112 12 to 35
(-10.1 to (100 days)
%W g
(-11.0 inch H O y
m 1 to 100 days 112 to 92 25 yo 65
(-10.1 to HH
(-)1.0 inch H o C/1 H y
tone FB-2 Fuel Building - Operator Floor (and Abovel, Above 11'-0" El U
Normal HVAC Summer / Winter 35 to 90
(-10.1 to 3.5 x 10 0
Note 15 80/60
(-11.0 inch H 0 and 24 y
Abnormal e Loss of HVAC 0 to 53 min 10 80 to 119 12 to 30
(-10.1 to 0
(-11.0 inch H 0 y
53 min to 14.5 hr 119 12 to 30
(-10.1 to
(-11.0 inch H O 2
14.5 hr to 26 hr 119 to 80 35 to 90
(-10.1 to
(-11.0 inch H O 2
e Loss of offsite O to 53 min 10 80 to 114 13 to 35
(-10.1 to 0
Note 15 power 0 inch H O 2
53 min to 2.5 hr 114 13 to 35
(-10.1 to 0 inch HyO 2.5 to 6 hr 114 to 80 35 to 90
(-10.1 to
(-)1.0 inch H O NN 2
'C >y
- (
) In this column refers to event 1.
.a r of Note 1 of Table 3.11-8 HO W4 I
I O
O O
s Table 3.11-4 ENVIRONMENTAL CONDITIONS FOR FUEL EUILDING EQUIPMENT (Continued)
PH 3 Int I-e t a Int C itr a Fluence Ccndition F r eq.'
Temperatore Tfinal Padiatlan Padiation (Ntn' Linitini Cordition*
D;rzation 40 Yrs
("Ft 66)
Tressare i r a ds 11. 2
' rads >2.3 c 2)
Sgp Cita Zone FB-1A IContinaed' Accident e Large I!E pipe O to 2 hr 1
Sl 0 to 150 i to 14
(-10.1 to 4 x 10 S.1 x 10 Nate 19 break in drywell
(-il.0 inch Hw te 181 Note 16) aN 20 2 hr to 100 days 150 to 80 35 to 90
(-10.4 to (100 days)
(-3 0 inch H.30 10*
e Fuel handlin 0 to 30 man 1
80 to 150 5 to 14
(-)0.1 to 3 x 6.3 x 10 Ncte 13 accident r
.l.0 inch H O (Note 21)
(Note 21) and 20 2
30 nin to 150 to 80 35 to 90
(-10.1 to (100 days) g 10J d ays
(-11.0 inch H O 2
W CD Zone FB-3 Fue l B ui l d i.ng - Be l ow Ope r a t i ng Fi r>c r frPCCU ifeat Exchan,er Areas. F/D, Hol d i nduy, P r e-Co it, g r'C1' F/D g l_flugp, Decon Waste Tank a nd Pump _R_oo_ns__),B. e__l o_w__11'-0" El t'.
Normal HVAC Summer / Winter 25 to 75
(- 10.. to (Note 25) 0 Nete 15 OM la 90/60
-)1.0 inch H,0 and 26 U U3 H
M fB 1
Abnormal w
WW e Loss of liVAC 0 to 24.rin 10 90 to 123 10 to 28
(-10.1 to 0
(-11.0 inch H O HH y
gg 24 min to I hr 123 10 to 28
(-10.1 to
(-11.0 inch H O y
1 to 1.5 hr 123 to 90 25 to 75
(-10.Y to
(-)1.0 inch H 0 y
Q e Loss of offsate O to 42 min 10 90 to 110 14 to 40
(-10.1 to 0
Note 15 power 0 inch H 0 y
42 min to 2.5 hr 110 14 to 40
(-10.1 to 0 inch H 0 y
2.5 to 3 hr 110 to 90 25 to 75
(-10.1 to
(-11.0 inch t>!y0 e Isolation events (Note 27)
Accident e Large HE pipe O to I hr 1
90 to 12 3 10 to 28
(-10.1 to 4.0 x 10
- 5. 3 x 10 0
Note 19 break in drywell
(-11.0 inch H O (Note 18)
(Note 18) and 20 2
1 to 2.5 hr 123 10 to 28
(-10.1 to (100 days)
(-11.0 inch H O y
b0 days I ch H o y
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 4
+
o HO w4
Table 3.11-4 ENVIRONMENTAL CONDITIONS FOR FUEL BUILDING EQUIPMENT (Continued)
Ph e Int Beta Int Ga ::-a Fluenre Condition Freq/
Terperature Trinat Radiation Radiation (Stn Limitang Condition
- Daration 40 Yrs
("F)
(nt Pressure (rads)l.2 (radsl2.3 cm2)
S ar p rata Zone FB-3 (Centinued) e Fuel handling 0 to 3 hr 90 to 150 5 to le
(-10.1 to 3.0 x 10 1.5 x 10 0
Nete 19 accident
(-)1.0 ir.ch H,0 (Note 21)
(Nate 21) and 23 3 hr to 100 d.nys
.150 to 90 25 to 75
(-10.1 to (100 days)
(-11.0 inch H o y
Zone FB-4 Fuel Building - SGTS Fan and Filter Rooms.
(-)5'-3*
and
(->17'-0" El Normal HVAC Summer / Winter 30 to 60
(-10.1 to 0
Note 2S 90/60
(-)1.0 inch H o y
N Abnormal W
03 e Loss of HVAC 120 nax 12 to 30
(-10.1 to 0
Note 16
(-)1.0 inch H O 2
2 CO W
e Wss of offsite 120 max 12 to 30
(-10.1 to 0
Note 17 OU 0 inch H 0 power y
e Isolation events 120 max 12 to 30
(-)0.1 to 3.9 x 10 0
(-)l.0 inch H 0 (Note 29) g y
Cn HH y
Accident f/3 H e Large HE pipe 1
break in drywell ZU
- SGTS filter room 120 max 12 to 30
(-10.1 to Figure 0
(-)1.0 inch H O 3.11-2 (Note 30)
- SGTS fan room 120 max 12 to 30
(-10.1 to 4.0 x 10 1.6 x 10 0
(-)l.0 inch 11 0 (Note 30)
(Note 30) 2
- ( ) In this column refers to event number of Note 1 of Table 3.11-9
%N (D hJ
+ 4 O
HO W4 O
O O
l_ _ _ ___-__. _ _ _.. _ _ _. _ _ _ _ _ _ _. _ _ _ _ _ _. _ _ _ _. _ _ _ _ _. _
t L-9 9
6
-i 1
I i
Table 3.11-4 f
L i
ENVIRONMENTAL CONDITIONS FOR FUEL BUILDING EQUIPMENT (Continued)
I I
i.
i RH 3 Int Beta Int Gar. ta Fluence
[
Condition Freq/
Temperature Tiinal Radiation Radiat*on (Ntq'
- Limiting Condition
- Duration 40 Yrs
(*F)
(%)
Pressure tradsile2 (rads) e3 cm')
Surp Data l
i' i
c zone FB-5 Fuel Building - Shield Annulus Exhaust Fan Rooms, 28'-6"_El i-2 r
i j.
Normal HVAC-Summer / Winter 30 to 70
(-10.1 to 3.5 x 10 0
90/60
(-11.0 inch H O I
2 i
t Abnormal e loss of HVAC 120 max 12 to 30
(-1d.1 to 0
Note 16
(-31.0 inch H o y
~
e Loss of offsite 120 max 12 to 30
(-10.1 to 0
Note 17 power.
O inch H O y
2 i
W Accident c0 e Large HE pipe 1
120 max 12 to 30
(-)0.1 to 4.C x 10 5.3 x 10 0
Notes 19 2
i break in drywell
(-11.0 inch H 0 (Note 18)
(Note 19) and 20 CO y
O 11 I
j'
.W'
~ 1 120 max 12 to 30
(-10.1 to 3.0 x 10 6.0 x 10 0
Notes 19 UM 4
1'
'e Fuel handling l
accident
(-11.0 inch H 0 (Ncte 21)
(Note 21) and 20
[
y i'
l.
WW f
i' W
.m HH
[
- (
l In this column refers to event (11 H
[
i
O number of Note 1 of Table 3.11-8 4
i t
t i
i 5..
t I
i i
i-i r
i i.
h i
Ww I
ID w i
l i
^
. a 1
O l
P*O i
WM Y
5 h
l i
4
-.-,----.--m
n..
,,,.--v,.,-._-,__
,. ~...
/^%
t Table 3.11-5 e
ENVIRONMENTAL CONDITIONS FOR CONTROL BUILDING EQUIPMENT RH @
Int Beta Int Camru Fluence Condition Freq/
Temperature Tfinal Radiation Radiation (Mtn/
l Limiting condition
- Duration 40 Yrs
(*F)
(t)
Pressure trads)1.2 (rads)2,3 em2)
Surp Data i
~ ~ ~ d omen's Iounge/ Toilet / Locker / Shower Rooms. Men's Toil m Zone CB-1 Control Buildinj - Cable Tunnels, Office, Lunch Room, Kitchen
~
Janitor, Corridors (includ E access), Stairs, (-)ECIP El i
Normal HVAC Summer / Winter 10 to 60 0.1 to 0.5 inch 75/70 HO 2
j Abnormal e loss of HVAC
' No impact - Has standby divisional HVAC equipment e ! ass of offsite No impact - HVAC powered by Div "ESF" Bus j
Power y
LJ Accident CD e
i e Radiation Post-Summer / Winter 10 to 60 0.1 to 0.5 inch 75 200 0
Notes 31 Z
l LOCA (12) 90/50 H0 (180 days) and 32 O
y m -16*-10" EL
.p Zone CB-2 control Buildint-Control Room and Ccmputer Room t
Normal HVAC 75 10 to 60 0.1 to 0.5 inch W
HO 2
M HH 1
-Abnormal (t) H e toss of HVAC No impact - Has standby divisional HVAC equipment e loss of offsite No impact - HVAC powered by Div *ESF" Bus O
power Accident e Radiation. Post-Summer / Winter 10 to 60 0.1 to 0.5 inch 75 200 0
Notes 31 LOCA'(12) 80/50 H0 (180 days) and 32 y
Instrument Repair Room, Men's Toilet / Locker / Shower Rooms, Janitor, Storage, Zone CBj Control Building _- Div Elec Equip Roomsg Corridors, TI C " El 0
i Normal HVAC Summer / Winter 10 to 60 0.1 to 0.5 inch 75/70 HO 2
Abnormal e loss of HVAC No impact - Has standby divisional HVAC equipment e Loss of offsite No impact - HVAC powered by Div "ESF" Bus per 4y 1
- 4 O
i
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 PO i
W4 e
i s-
Table 3.11-5 ENVIRONMENTAL CONDITIONS FOR CONTROL BUILDING EQUIPMENT (Continued)
RH d int Peta Int Gamma Fluence Ccndition Freq/
Temperature Tfinal Padiation Radiatten (Ntn/
Limitinj Ccndition*
Duration 40 Yrs l'F)
(*)
Pressure (rads,1,2 (rads 12.'
a 21 sugDy Zone CB-3 (Continuedi Accident e Radiation Post-Summer Wintel 10 to 60 0.1 to 0.5 I r.ch 75 200 0
Notes 31 LOCA (12) 90/50 Ho (150 days) and 32 y
Zone CB-4 Control Buildin1 - Elec Control koom, 11*-0* El Normal HVAC Swrane r /Wi n t e r 10 to 60 0.1 to 0.5 Inch 75'70 Hoy Abnormal e Loss of HVAC No impact - Has standby divisional HVAC Equipment g
CO e Loss of offaite No impact - HVAC powered by Div "ESF" Bus
() trj y
power t-4 (/)
H CT1 Cl3 g
Accident l
W%
MD e Radiation Post-Summer / Winter 10 to 50 0.1 to 0.5 inch 75 200 0
Notes 31 00 LOCA (12) 80/50 HO (100 days) and 32 NH 2
t/) H Zone CB-5 Control BuildinL-Fan Rnnms, Chiller Rooms, Outdoor Air Filter Rooms, 28'-6" El Normal HVAC Summer / Winter 10 to 90 0 to 0.25 inch g
95/60 HO 2
Abnormal e Loss of HVAC No impact - Has standby divisional HVAC Equipment e Loss of offsite No ifnpact - HVAC powered by Div "ESF" Bus pcwer Accident e Radiation Post-Summer / Winter 10 to 90 0 to 0.25 inch LOCA 104/50 1 fan and chiller 75 200 0
Notes 31 2 outdoor air 75 8000 0
and 32 filter (180 day dose (12) in 100 days)
MN (D M
- (
) In this column refers to event number of Note 1 of Table 3.11-8 4>
- 4 O
HO WW 1
O O
O
Table 3.11-5 ENVIRONMENTAL CONDITIONS FOR CONTROL BUILDING EQUIPMENT (Continued)
RH @
Int Beta Int Camma Fluence Radiatgon (Ntn/
Condition Freq/
Temperature Tfinal Radiation (rads)
- 3 cm2)
Supp D R Limiting Condition
- Duration 40 Yrs i'F)
(4)
Pressure (rads)le2
- or.e CB-6 Control Building - Elev Equipment Room, 38*-6* El Normal HVAC Summer / Winter 10 to 90 0 to 0.25 inch 95/60 HO 2
Abnormal e Loss of f*VAC No 11tpact - Has standby divisional HVAC equipment e Loss of of f site No impact - HVAC powered by "ESF" Bus power N
Accident W
e Radiation Post-Summer / Winter 10 to 90 75 200 0
Notes 31 LOCA (12) 104/50 (180 day dose and 32 Z
in 180 days) gg w
M U3 H
M Cl3 Y
W
- ( ) In this column refers to event number of Note 1 of Table 3.11-8 HH t/1 H E
O l
l J3 M OM
+ 4 O
>-* C
@M
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 1.
PLANT EVENTS AND FREQUENCY Frequency /40 yrs i
NORMAL 1.
Bolt Up 123 2.
Cold Startup and Heatup to Low Pressure 1
Hot Standby 120 3.
Heatup to High Pressure Hot Standby 120 4.
Increase to Full Power 120 5.
Daily Load Reduction and Recovery 10,000 6.
Special Load Reduction and Recovery 2,000 7.
Non-Scram Reduction to High Pressure Hot Standby 111
)
8.
Non-Scram Reduction from High Pressure to Low Pressure Hot Standby 111 9.
Cooldown from Low Pressure Hot Standby to Vessel Flood 111 10.
Unbolt 123 11.
Refuel 40 ABNORMAL 1.
Pressure Regulator Fails Open 26 2.
Inadvertent Closure (All MSIV) 10 3.
Loss of Auxiliary Transformer (Loss of Power) 5 4.
Loss of Grid Connection (Loss of Power) 5 5.
Loss of Condenser Vacuum 26 6.
Turbine Trip Without Bypass 1
7.
Generator Load Rejection Without Bypass 1
8.
Single Safety Relief Valve Opens -
O.
(,j Depress (SORV) 8 3.11-103
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued)
ABNORMAL (Continued) 9.
Trip of Both Recirc Pumps 10 10.
Generator Load Rejection With Bypass 29 11.
Recirculation Failure - Decrease Flow 5
12.
Feedwater Controller Fails - Max Demand 10 13.
Turbine Trip With Bypass 10 14.
Loss of All Feedwater 10 15.
Recirculation Failure - Increase Flow 10 16.
Inadvertent Closure of MSIV (One) 6 17.
Worst In-Sequence Rod Error 3
18.
Instrument Ranging Error 3
19.
Inadvertent (or Manual) Scram 20 20.
Loss of Feedwater Heater - Auto 3
21.
Loss of Feedwater Heater - Manual 3
22.
Rod Withdrawal Error at Power 3
23.
Inadvertent HPCS Injection 10 24.
Inadvertent RCIC Injection 10 25.
Grid Tie-Line Disturb. and Recovery 50 26.
Trip One FW Pump and Recovery 25 27.
Restart of Both Recirc Pumps 10 28.
Loss of HVAC in Steam Tunnel 10 29.
Loss of HVAC in Drywell 3
30.
Loss of HVAC in Containment 3
31.
Loss of HVAC in Auxiliary Building 10 32.
Loss of HVAC in Fuel Building 10 33.
Loss of HVAC in Turbine Building 10 TESTS 1.
Preoperation Test 1
2.
Start-Up Leak Te,st 120 3.
Refueling Outage Test 40 4.
HPCS Injection Test 76 5.
RCIC Injection Test 76 3.11-104
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued)
TESTS (Continued) 6.
Test Open/Close Individual S/R Valve (No Blowdown) 40 ea 7.
Diesel Generator Test 1000 8.
Individual MSIV Closure Test 1824 9.
Turbine Containment V/V Test (Sets of 8) 456 10.
HPCS Non-Injection Test 426 11.
RCIC Non-Injection Test 426 12.
LPCS Non-Injection Test 500 13.
LPCI Non-Injection Test 500 14.
SLCS Non-Injection Test 12 15.
Scram Test 300 16.
Rod Notch Test 2080 17.
Drywell Leak Test 12
/"'}
18.
CTMT Leak Test 12 19.
MSIV Leak Test 40 20.
, Secondary Containment Leak Test 12 ACCIDENT 1.
Open Recirc Valves in Cold Loop (Reverse Flow) 1 2.
Start Pump in Cold Loop (Forward Loop) 1 3.
Inadvertent LPCS Injection 1
4.
Reactor Overpressure Backup Scram 1
5.
Inadvertent ADS - Depress.
1 6.
Inadvertent SLCS Injection 1
7.
Improper Startup of Plant Hot RWCU 1
8.
Reactor Drain Shut-off 1
9.
Alternate (RHR) Shutdown Mode (Shutdown with RHR Suction Through S/R Valve and Suppression Pool) l 10.
Seizure of One Recirc Pump 1
3.ll-104a j
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued)
ACCIDENT (Continued) 11.
Small HE Pipe Break in Drywell 1
12.
Large HE Pipe Break in Drywell 1
13.
Large HE Pipe Break in CTMT Outside Drywell 1
14.
Small Line Break in Containment Outside Drywell 1
15.
HE Pipe Break Outside Containment 1
16.
Fuel Handling Accident in Containment 1
17.
Control Rod Accident (Drop) l 18.
Fuel Handling Accident in Fuel Building 1
19.
Tornado (With Loss of Preferred Power) 1 20.
Worst ATWS - MSIV Closure No Scram, Two Pump Trip 1
21.
Inadvertent LPCI Injection 1
2.
The dose is based conservatively on the scram with turbine isolation event.
It is assumed that there shall be 200 such events throughout the life of the plant.
3.
The dose is based on the loss-of-coolant accident utilizing the assumptions of Regulatory Guides 1.3 and 1.7.
4.
The normal operating 40-yr dose to equipment located in 5
the traversing incore probe cubicle is 8.2 x 10 rads (gamma).
The dose for the remaining area in this volume is 1.8 x 10 rads (gamma).
5.
For the Zone CT-2 Abnormal condition of " Isolation Events,"
the suppression pool temperature was assumed to be 150"F due to the 19 SRV's opening.
3.ll-104b
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19
)
Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued) 6.
The following normal operating 40-yr doses should be used for the RWCU System equipment located in the following rooms.
a.
RWCU R/D Cubicle 1.5 x 10 rads (gamma) 4 b.
RWCU F/D Valve Gallery 1.6 x 10 rads (gamma) 4 c.
RWCU F/D Drain Room 3.5 x 10 rads (gamma) d.
RWCU Backwash Tank Room 1.1 x 10 rads (gamma) e.
RWCU Heat Exchanger Room 1.9 x 10 rads (gamma) 7.
The normal operating 40-yr dose in the drywell between the reactor shield wall and a radial distance of 24'-0" from l
the reactor centerline, and vertically between elevations 7
(+)8"-0" to an elevation of (+)46'-0" is 5.I. x 10 rads 15 (gamma) and 1.1 x 10 nyt (Neutron > 1 MeV).
The normal operating 40-yr doses in the drywell outside the reactor shield wall and outside the region defined above 14 is 2.7 x 10 rads (gamma) and 6.0 x 10 nyt (Neutron > 1 MeV).
8.
Abnormal isolation events for Zones DW-1 and 2, are based on "19 SRV's open with scram" and with 150*F suppression pool temperature.
9.
The dose is based on NUREG-0588 assumptions.
10.
Normal HVAC temperature for Zone DW-4 is based on a fuel pool temperature of 126 F.
11.
Abnormal Loss of HVAC temperature is based on a fuel pool l
temperature rise to 128.5*F.
l 1
l v l
l 3.ll-104c
GESSAR II 22A7007 238 NUCLEAR ISLAND Rnv. 19 Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued) 12.
The dose is based on the loss-of-coolant accident using the assumptions of Regulatory Guides 1.3 and 1.7.
13.
The dose is based on the scram with turbine isolation event.
It is assumed that there shall be 200 such events throughout the life of the plant.
14.
The following doses are based on the loss-of-coolant accident using the assumptions of Regulatory Guides 1.3 and 1.7.
The following curves should be used depending on the location of the equipment being specified.
Equipment Location Gamma Dose Beta Dose Equipment in contact Figure 3.11-8 Figure 3.11-8 with suppression pool fluid.
Equipment within 3'-0" Figure 3.11-8 Figure 3.11-9 of equipment contain-ing suppression pool fluid but not in con-tact with fluid.
Remaining volume of Figure 3.11-10 Figure 3.11-9 room.
l l
15.
A negative static pressure level is maintained within the Fuel Building during normal HVAC operation by the Pressure Control Exhaust System in conjunction with the main upper and lower level air conditioning systems.
These systems are powered by the Non-Divisional "N" Buses, interruptible off-site power, and thus there is no pressure control during the abnormal loss of offsite power condition.
3.ll-104d
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued) 16.
Area has supplementary standby divisional HVAC equipment, with cooling coils supplied by ESW, to maintain the maximum temperature noted when the normal HVAC is lost.
17.
Supplementary HVAC equipment, powered by Divisional "ESF" Buses, will maintain the area at the maximum temperature noteo.
The area pressure will rise to 0-in.WG due to loss of interruptible "N" Buses powering the normal HVAC and pressure control exhaust fans.
18.
The loss-of-coolant accident dose is based on Regulatory Guide 1.3 assumptions.
Bypass leakage from the containment is assumed to enter the Fuel Building exclusively.
19.
The pressure control exhaust fans, the upper and lower level HVAC units, and the isolation valves in the main outside air inlet duct, will automatically close during a LOCA condition or if higher airborne radiation is detected in the exhaust air.
20.
The SGTS will start automatically from a LOCA signal or high airborne radiation signal, and thus will maintain a negative static pressure within the building.
21.
The fuel handling accident is calculated based on Regulatory Guide 1.25 assumptions.
The fuel is assumed to have operated for 3 years.
For equipment submerged in the fuel pool or in contact with fuel pool water, a 1.7 x 10 rads (gamma) and a 4
3.0 x 10 rads (beta) dose should be used.
22.
Pressurc control exhaust fans will draw 120*F ventilation
()
air from the adjacent pump area, which results in the maximum tank room temperature as noted.
3.ll-104e
GESSAR II 22A7007 238 NUCLEAR ISLAND Rt.v. 19 Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued) 23.
Since the pressure control exhaust fans are on the interrupt-ible "N" Buses, no ventilation air from the adjacent area will be drawn through this room and this results in the maximum room temperature as noted.
The area pressure will rise to 0-in.WG without an exhaust.
24.
For the areas above the operating floor at 11"-0" elevation, a differential pressure controller (RR602) throttles a damper in the branch outdoor air make-up duct to the upper level air conditioning system.
This enables the exhaust system fan to maintain the upper areas at a negative pressure with respect to the outside ambient atmosphere.
25.
The following normal operating 40-yr doses should be used for the equipment in the areas listed below.
Area Dose (rads) 4 FPCC F/D Drain Area 1.9 x 10 FPCC Precoat Pump Room 7.7 x 10 5
FPCC F/D Cubicle 2.5 x 10 8
Fuel Transfer Tube Cubicle 2.0 x 10 2
FPCC HX Alcove Area 8.5 x 10 FPCC Surge Tank Area 9.1 x 10 3
l Decon Tank Room 7.0 x 10 l
4 New Fuel Vault 1.0 x 10 l
Cask Decon Vault 1.4 x 10 4
SPCU F/D Room 1.4 x 10 2
Remaining Areas 3.5 x 10 0
3.ll-104f
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19
- f Table 3.11-8 NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued) 26.
For the areas below the operating floor elevation a differential pressure controller (RR603) throttles a damper in the branch outdoor air make-up duct to the lower level air conditioning system.
This enables the exhaust system fan to maintain the lower areas at a negative pressure with respect to the outside ambient atmosphere.
27.
These doses are based on the scram with turbine isolation event.
It is assumed that there shall be 200 such events throughout the life of the plant.
The following areas are affected.
Gamma Dose Area (rads) 5 SPCU F/D Room 5.2 x 10
-s
(,,)
SPCU Pump Area 1.7 x 10 28.
The heat load for this area is absorbed by the transferred air from the adjacent area at 90*F which is exhausted to the atmosphere by the pressure control exhaust system.
29.
The dose is based on the purge of the containment following the turbine isolation event.
30.
The loss-of-coolant accident is based on Regulatory Guide 1.3.
The source term on the SGTS Filter is based on no mixing of the containment atmosphere in the Shield Building prior to entering the filter.
31.
If there is a high radiation level in the building outdoor air supply, such as may be possible during a LOCA,.the normal outdoor air supply to the building A/C units is shut-off and g
)
the outdoor air supply is provided through the Outdoor Air 3.ll-104g
GESSAR II 22A7007 238 NUCLERR ISLAND Rev. 19 Table 3.8-11 ll NOTES FOR TABLES 3.11-2 THROUGH 3.11-7 (Continued)
Cleanup Units.
This highly filtered outdoor air is of a sufficient quantity to pressurize the building, since it provides the corresponding leakage rate for the building.
32.
The radiation doses are based on the loss-of-coolant accident utilizing Regulatory Guide 1.3 assumptions.
O l
l
\\
O 3.ll-104h
i l~
GESSAR II 22A7007
{
238 NUCLEAR ISLAND Rev. 19*
Table 3.11-10 l
SELECTED GE POSITIONS ON NUREG-0588 j
t 1
I I
t i
I i
I i
i I
i l
l GE PROPRIETARY - provided under separate cover i
l l
- Revision 5 - Page 3.11-160 Revision 6 - Pages 3.11-153, 3.11-154, 3.11-156, 3.11-158 Revision 19 - 3.11-155, 3.11-157, 3.11-159 3.11-153 through 3.11-160
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
1012 109 l
108 1011
~
l l
I 107 g010
=
DOSE RATE 106
, j 5
1 m
DOSE O
0 105 j
s 104 g7 3
~
10 106 l
102 i
e i
j 0.1 1.0 10 100 1D00 10A00 TIME (hr) 0 Figure 3.11-2.
Post-LOCA Contain!; tent Semi-Infinite Beta-Dose 3.11-165
l GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 l
O l
108 3010 l
10 108
?
10 DOSE RATE AT Id 6
~
EL237 FT 11N.
DOSE AT EL 2 37 FT 1 IN.
l DOSE RATE AT EL < 37 FT 1 IN.
5 107 10
/
DOSE AT EL< 37 FT 1 IN.
w W
8 8
o 4
10 106 103 go5 102 104 1
10 103 0.1 1.0 10 100 1 A00 10A00 TIME (hr)
Figure 3.11-3.
Post-LOCA Containment Gamma Dose Rates and Doses 3.11-166
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
jo11 1010 l
BETA DOSE 9
10 i
GAMMA DOSE O
7 10 l
6 10 I
l 105 1
0.f j,o 10 io-1 #00 1o 300 TIME FOLLOWING LOCA thr)
O.
Figure 3.11-4.
Post-LOCA Drywell Doses 3.11-167
GESSAR II 22A7007 238 NUCLEAR TSLAND Rev. 19 O
0 10 105 no 4
10 8
O 3
10 102 1
10 0
1 I
l l
10 0.1 1D 10 100 1D00 10000 TIME FOLLOWING LOCA (hr) l Figure 3.11-5.
Post-LOCA Doses for Remaining Areas of Auxiliary Building i
3.11-168
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
108 7
10 106 0
105 8
104
~
103 102 I
I i
1 0.1 1.0 10 100 1A00 10D00 TIME FOLLOWING LOCA (hr)
' O Figure 3.11-6.
Post-LOCA Steam Tunnel Beta Dose l
l 3.11-169
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 9
7
~
10 6
10 105 4
8 10
~
O 3
10 102 10 1
I 1
I I
0.1 1.0 10 100 1 #00 10S00 TIME FOLLOWING LOCA (hr)
O 1
l Figure 3.11-7.
Post-LOCA Steam Tunnel Gamma Dose 3.11-170
{
OmMm>W gH wN>4oO wW 2CoMm>W gCtyzO MO<.
)*
I O
4 E
i 0
S 1
O E
D S
O A
D MM AT A
E G
S sesoD tca 3
t I
0 n
1 oC d
iu l
F
)
l rh o
(
o AC P
O L
n G
o N
O I
i W
s O
s 2
L e
0 L
I 1
O r
F p
E p
MI u
T S
ACOL
-tsoP 8
1 f
0 1
1 1
3 e
r u
g i
F
~
8 O
1 6
f 0
1 j
O32 w oa W HYH4W
GESSAR II 22A7007 238 NUC1. EAR ISLAND Rev. 19 O
100
/
I 10 0
10 2
R b
5 10 4
10 i
3 10 s
102 I
I I
0.1 1.0 10 100 IF 10/)00 j
l TIME FOLLOWING LOCA (hr)
Figure 3.11-9.
Post-LOCA Deta Dose v
3.11-172
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
9 10 108 NON ECCS PUMP 107 RELATED EQUIPMENT 2
ECCS PUMP 8
RELAT ED EQUlPMENT 106 5
10
{
4 l
10 l
r 103 I
I I
I 0.1 1.0 10 100 1 S00 10A00 1
TIME FOLLOWING LOCA (hr)
O Figure 3.11-10.
Post-LOCA Gamma Dose 3.11-173
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 10 1010 10 109
- 109 ios 108 GAMMA DOSE 7
7
~
~
10 10 s
1 GAMMA DOSE RATE W
O 6
6 10 10 BETA DOSE RATE l
s 20s 20 BETA DOSE 104 104
~
~
\\
\\
103 I
103 0.1 1.0 10 100 1400 10400 TIME FOLLOWING LOCA (hr)
Figure 3.11-11.
Post-LOCA SGTS Filter Cubicle Dose Rates and Doses i
3.11-174
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 5 APPENDIX 3I CONTENTS Section Title Page 3I ENVIRONMENTAL QUALIFICATION TESTING EFFORT ADMINISTRATIVE CONTROLS 31.1 PRODUCT PERFORMANCE QUALIFICATION SPECIFICATION GUIDELINES 3I.1-1 3I.l.1 Scope 3I.1-1 3I.1.2 Documents 3I.1-1 3I.1.2.1 Applicable Documents 3I.1-1 3I.1.2.2 Reference Documents 3I.1-1 3I.1.3 Performance Specification 3I.1-2 3I.l.3.1 Product Description 3I.1-2 3I.1.3.2 Interface Definition 3I.1-2 3I.1.3.3 Mounting 3I.1-2
\\
31.1.3.4 Performance Requirements 3I.1-2 3I.l.3.5 Physical Characteristics 3I.1-3 3I.1.3.6 Maintenance Requirements 3I.1-3 3I.1.3.7 Service Conditions 3I.1-3 3I.1.4 Qualification Specification 3I.1-3 3I.l.4.1 Test Sample Description 3I.1-4 31.1.4.2 Quality Assurance 3I.1-4 3I.l.4.3 Set-Up Requirements 3I.1-4 3I.l.4.4 Test Sequence 3I.1-4 31.1.4.5 Baseline Tests 3I.1-4 3I.l.4.6 Abnormal Conditions 3I.1-5 3I.l.4.7 Aging 3I.1-5 31.1.4.8
. Dynamic Test 3I.1-5 3I.1.4.9 Design Basis Event Test 3I.1-5 3I.l.4.10' Disassembly and Inspection 3I.1-5 3I.l.4.11 Acceptance Criteria
.3I.1-5' 3I.1.4.12 Test Report 3I.1-6
-w g
N._ /
3I.l.4.13 Test Specimen Deposition-3I.1-6 l
GESSRR II 22A7007 238 NUCLEAR ISLAND Rev. 19 CONTENTS (Continued)
Section Title Page 3I.2 PRODUCT ANALYSIS REPORT GUIDELINES 3I.2-1 3I.2-1 3I.2.1 Scope 3I.2-1 3I.2.2 Report Format 3I.2.2.1 Cover Sheet 3I.2-1 3I.2.2.2 Table of Contents 3I.2-1 3I.2-1 3I.2.2.3 Scope 3I.2.2.4 Product Description 3I.2-1 3I.2.2.5 Environment 3I.2-2 3I.2.2.6 Summary of Results 3I.2-2 3I.2.2.7 Detailed Analyses 3I.2-2 3I.2.2.7.1 Aging Analysis 3I.2-2 3I.2.2.'7.2 Similarity / Traceability Analysis 3I.2-3 3I.2.2.7.3 Other Analyses 3I.2-4 3I.2.2.8 Acceptance Criteria 3I.2-4 3I.2.2.9 References 31.2-4 3I.3 SIMILARITY / TRACEABILITY PROCEDURE 3I.3-1 3I.3.1 Scope 3I.3-1 3I.3.2 Traceability Analysis 3I.3-1 3I.3.2.1 Purchase 3I.3-1 3I.3.2.2 Manufacturer's Compliance 3I.3-1 3I.3.2.2.1 Manufacturer 3I.3-1 3I.3.2.2-2 Testing 3I.3-la 3I.3.2.3 Installed Parts 31.3-la 3I.3.2.4 Summary of Traceability 3I.3-la 3I.3.3 Establishment of Family of Products 3I.3-lb 3I.3.3.1 Primary Considerations 31.3-lb 3I.3.3.1.1 Manufacturer 3I.3-lb 3I.3.3.1.2 Function 3I.3-lb 3I.3.3.1.3 Quality Assurance Program 3I.3-lb 3I.3.3.1.4 Functional Mechanism 3I.3-2 3I.3.4 Similarity Analysis 3I.3-2 3I-il
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 OV CONTENTS (Continued)
Section Title Page 3I.3.4.1 Service / Application and Configuration 3I.3-2 3I.3.4.2 Range / Rating 3I.3-2 3I.3.4.3 Interface 3I.3-3 3I.3.4.4 Stresses 3I.3-3 3I.3.4.5 Materials 3I.3-4 3I.3.5 Summary 3I.3-5 3I.3.6 Attachments 3I.3-5 3I.3.6.1 - Quality Assurance 3I.3-5 3I.3.6.2 - Manufacturer's Specifications 3I.3-6 3I.3.6.3 - Application Specifications 3I.3-6 3I.3.6.4 - Environmental Specifications 3I.3-6 3I.3.6.5 - Supporting Analysis and Data 3I.3-6 3I.4 FORMAT AND CONTENT OF PRODUCT APPLICATION FUNCTIONAL REQUIREliENTS 3I.4-1 3I.4.1 Purpose 3I.4-1 3I.4.2 Introduction 3I.4-1 3I.4.3 Format 3I.4-1 3I.4.3.1 Product Identification 3I.4-1 3I.4.3.2 Basic Function 3I.4-2 3I.4.3.3 Product Application Requirements 3I.4-2 3I.4'.3.3.1 Circuit Description 3I.4-2 3I.4.3.3.2 Interfaces 3I.4-2 3I.4.3.3.3 Functional Performance Requirements for Normal Operation' 3I.4-2 3I.4.3.3.4 Mounting 3I.4-3' 3I.4.3.4 Functional Performance _ Requirements i
for Design Basis Events 3I.4-3 j
3I.4.3.4.1 General Safety Functions 3I.4-3
(%
(_j; 3I.4.3.4.2 Specific Safety Function Tabulation 3I.4-3 3I-iii g-4
GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 19 O
CONTENTS (Continued)
Section Title Page 3I.4.3.5 Effect of Product Failure 3I.4-3
~
3I.4.3.5.1 Potential Failure Modes During the Portion of the DBE Environment for which This Product Will Not be Qualified 3I.4-4 3I.4.3.5.2 Effect of Failure Modes of the General Safety Function of This Product 3I.4-6 3I.4.4.5.3 Secondary Electrical Effects of Failure Modes 3I.4-6 3I.4.4.5.4 Effect of Failure Modes on Operator Usage 3I.4-6 3I.4.4.6 Reference Documents 3I.4-7 3I.5 PRETEST EVALUATION 31.5-1 3I.5.1 Scope 3I.5-1 3I.5.2 Requirements 3I.5-1 3I.5.2.1 Test Conditions 3I.5-1 3I.5.2.2 Functional Requirements 3I.5-1 3I.5.2.3 Product Description 3I.5-2 3I.5.2.4 Method of Evaluation 3I.5-2 3I.5.2.4.1 Manufacturer's Data 3I.5-2 3I.5.2.4.2 Test Data 3I.5-3 3I.5.2.4.3 Evaluation by Operating Experience 3I.5-4 3I.5.2.4.4 Evaluation by Component 3I.5-4 3I.5.2.4.5 Recommendations 3I.5-5 3I.5.3 Documentation 3I.5-5 3I.5.3.1 Records 3I.5-5 l
3I.5.3.2 Evaluation Report 3I.5-6 3I.5.4 Appendices 3I.5-6 3I.6 TEST PLAN AND PROCEDURES GUIDELINES 3I.6-1 i
3I.6-1 31.6.1 Scope 3I.6.1.1 Purpose 3I.6-1 3I.6.1.2 Use 3I.6-1 0
m h-A t
m.
- m 4
- ~~
-m' m
a GESSAR II 22A7007 4
238 NUCLEAR ISLAND Rev. 19 O
CONTENTS (Continued)
Section Title Page 3I.6.2 Document Control 3I.6-1 3I.6.3 Format and Content 3I.6-1 3I.6.3.1 Cover Sheet 3I.6-2 3I.6.3.2 Table of Contents 3I.6-2 3I.6.3.3 Test Plan 3I.6-2 i
3I.6.3.4 Test Procedure 3I.6-4 3I.7 TEST REPORT GUIDELINES 3I.7-1 3I.7.1 Scope 3I.7-1 3I.7.2 Report Format 3I.7-1 3I.7.2.1 Cover Sheet 3I.7-1 3I.7.2.2 Table of Contents 3I.7-1 3I.8
. ENVIRONMENTAL QUALIFICATION REPORT GUIDELINES 3I.8-1 O
4 s
l 3I-iva.
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.=-_._ _ =...
i i
GESSAR II 22A7007 i
238 NUCLEAR ISLAND Rev. 19 t
- O l
3I.2 PRODUCT ANALYSIS REPORT GUIDELINES (Continued) l P
i i
l l
1 J
i t
i t
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