ML20073Q349
| ML20073Q349 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 04/28/1983 |
| From: | Longenecker J ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT |
| To: | Grace J Office of Nuclear Reactor Regulation |
| References | |
| HQ:S:83:246, NUDOCS 8304290052 | |
| Download: ML20073Q349 (17) | |
Text
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m Department of Energy Washington, D.C. 20545 Docket No. 50-537 APRgg pgg3 HQ:S:83:246 Dr. J. Nelson Grace, Director CRBR Program Office; Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
. Washington, D.C.-
20555
Dear Dr. Grace:
REVISED RESPONSE TO SAFETY EVALUATION REPORT (SER) ITEM N0. 6 - QUALITY ASSURANCE
Reference:
Letter HQ:S:83:241, J. R. Longenecker to J. N. Grace,
" Response to Safety Evaluation Report (SER) Item No. 6 -
Quality Assuranc.e, dated April 8,1983 Enclosed is a revision to a response previously submitted in the referenced letter that provides additional information regarding the identification of safety-related~. structures', systems, and components controlled by the Clinch River. Breeder Reactor Plant Quality Assurance Program. The revisions are
. indicated with bar lines in the margin and address connents offered by the Nuclear Regulatory Commission (NRC) staff. There are additional comments
..by the NRC staff that I believe can be best addressed by the project in a meeting between our staffs.during the week of May 9,1983. The enclosed infonnation and the proposed meeting should enable the staff to complete its review of the Quality Assurance list and close out SER Item No. 6 in Section 1.6 of the SER.
Any questions regarding the enclosed infonnation may be addressed to Mr. D. Robinson (FTS 626-6098) of the Project Office Oak Ridge staff.
Sincerely, l
b ohn R.' Longenecker Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy DOO[
Enclosure cc: Service List Standard Distribution Licensing Distribution 8304290052 830428 i ~
PDR ADOCK 05000537 E
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-Quality Assurance Branch Questions:
Section 17.1.2.2 of the standard format (Regulatory Guide 1.70) requires the identification of safety-related structures, systems, and components controlled by the QA program.
You are requested to.
supplement and clarify the'CRBRP PSAR in accordance with the
- f oll,o' wing :
a.
The following items do not appear on PSAR Table 3 2-1, 3.2-2, 3.2-3, or 7.1-1.
Add the appropriate items to the appropriate table or justify not doing so.
1.
Instrumentation and Controls for the following systems:
o Annulus Filtration System o
Reactor Service Building Filtration System o
Steam Generator Building Aerosol Release Mitigation System o
Outlet Steam Isolation System L
o Core Criticality Monitoring System o
Pressure Controlled Bypass Valves (AFW Pumps).
o AFW Isolation Valves & Pump Inlet Isolation Valves o
Steam - Feed Flow Mismatch-& Steam Drum Level Interlock Subsystem o
Remote Shutdown. system o
Emergency Plant Service Water System o ' Emergency Chilled Water System o
Failed Fuel Monitoring System Cover Gas Monitor L
Delayed Neutron Monitor L
Failed Fuel Location System I
o Leak Detection Systems o. Sodium Water Reaction Pressure Relief System o.
Containment Hydrogen Monitoring System o
Accident Monitoring System 2.
Reactor Service Building Filtration System 3.
Control Room Filtration System 4.
Radioactivity Monitoring " fixed and portable) i l
5.
Radioactivity Sampling (air, surfaces, liquids) 6.
Radioactive Contamination Measurement and Analysis
-7.
Personnel Monitoring Internal (e.g., whole body counter) and External (e.g., TLD system)
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8.
Instrument Storage, Calibration and Maintenance 9.
Decontamination (facilities, personnel and equipment) 10.
Respiratory Protection, Including Testing 11.
Contamination Control 12.
Radiation Shielding 13.
Standby AC Auxiliary Power Systems (Class 1E)-
o Diesel generator packages including auxiliaries (e.g.,
lube system, jacket cooling, air start systems, governor, voltage regulatory and excitation system).
o Instrumentation, control and power cables (including underground' cable system, cable splices, connectors and terminal blocks).
o Conduit and cable trays and their supports containing Class 1E cables and other raceway installations whose failure may damage other safety-related items.
o Valve operators o
Protective relays and control panels o
Electrical penetration for containment - vital and non-vital including primary and backup fault current i
protective devices.
l o
Emergency lighting battery packs o
AC vital bus distribution equipment 14.
DC Power Systems (Class 1E) o Cables o
Conduit and cable trays and their supports containing 1E cables and other raceway installations whose failure may damage other safety-related items.
o Battery racks l
o DC switchgear, distribution panels and protective relays
- 15.
Containment o
Primary Containment Structure and Internal Cell l
Structures l
-o Access hatches /airlocks/ doors i
o Penetration assemblies l
o Reactor Cavity Vent System o
Reactor Containment Building Vacuum Relief System o
Confinement Piltration Systems l
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Emergency Plant Service Water System.(adequacy of water supply).
h 17.
Component Supports for Safety Class'1, 2 and' 3 systems l-(see paragraph NF-1214,Section III, ASME Boiler &
l Pressure Vessel Code).
l l
.18.
Missile Barriers which. protect safety-related structures, L
~ systems, and components.
L 19.
Biological Shielding L20.
Spent Fuel Pool and Liner
- 21.. Plant Safety-Parameter Display Console
- 22.
Equipment and other items associated with.the emergency support facilities, b..
Clarify table entries as noted below or justify not doing so.
1.
Expand. Table 3.2-1 to include an entry for containment internal structures which have been identified as a Seismic Category I structure-in PSAR Section 3.8.3.
2.
. Expand Table 3.2-1 to include an entry for cable trays which'are. identified as Seismic Category I structures in l
Table 3.8-2 of the PSAR.
3.
Since foundation support materials (rock, soils, backfill l
-and concrete fill) are not specifically identified in the l.
QA program for Seismic Category I structures, expand l
Table 3.2-1 to include an' entry which reads " Foundations
~
i and Foundation Support Material (rocks, soils, backfill, i
and concrete fill) for Seismic Category I Structures."
14.
Expand Table 3.2-1 to include an entry for " Emergency Plant Service Water System Supply and Return Headers in the Yard," which have been identified as Seismic Category LI structures in PSAR Section 3.8.5.
p
/5.
Exp nd Table 3.2.1 to include an entry for "SGB Maintenance Bay" which has been identified as a seismic Category I structure in PSAR Section 3.8.4.
6.
Expand Table 3.2-1 to include an entry for " Underground Class IF. Electrical Ducting and Category I Pipe" which are identified as such in PSAR Section 3.8.5.1.1.
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All features of the plant building'and site having to do i
with the crainage of intense local precipitation should
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be. included in Table 3.2-1.
This includes roof drains, underground drainage ~ systems, paved ditches, culverts and site grading.
8.
The Emergency Chilled Water System is designated as Quality Group C in. Table 3.2.2.
We require the system to be Quality Group B (Safety Class 2).
[
. hesponse :'
I
'The following supplements and clarifications are being made to the
(
PSAR : to completely identify saf ety-related structures, systems, and components controlled by the CRBRP Quality Assurance Program.
l a.1_
Instrumentation and Controls
-All safety-related instrumentation and control systems and equipment for CRBRP are classified 1E.
Reference 13 to PSAR t.
Section 1.6, WARD-D-0165, " Requirements for Environmental Qualification of Class lE Equipment," provides the list of Class
-1E equipment for CRBRP.
PSAR Table 3.2-3 and 7.1-1 are more
' general in nature and were not intended to serve as the Project QA list.. WARD-D-0165 is presently being updated to include equipment recently designated Class 1E and this upcoming l
. revision will include all'the Class 1E instrumentation and o
control equipment listed in the question with some minor exceptions.
These exceptions are:
l o -The Failed Fuel Monitoring System is not safety-related, Class 1E, or included in WARD-D-0165.
Sections 7.5.2.3 and l-
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7.5.2.5 of the Safety Evaluation Report (SER) support the
'non-safety-related classification.
l
.o' ;CRBRP does not employ an accident monitoring system per se.
i
' Accident monitoring is accomplished through a defined set of I
instrumentation incorporated in other plant systems.
All
. Category-I accident monitoring instrumentation of Regulatory Guide 1.97, which is required to be classified 1E, is
- included in WARD-D-0165.
o ' Those portions of the Remote Shutdown System which are required to remotely bring the plant to a safe shutdown are t
l classified as Class 1E and are listed in WARD-D-0165.
)
Section 7.4.2.7 of the SER supports the Remote Shutdown i
System safety classification.
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9 1
5-Also, fit should be noted that:
'o CRBRP has not designated a separate core criticality _ system; the function is performed by the Class lE Flux Monitoring System included in WARD-D-0165.
-o The Annulus and Reactor Service Building Filtration I&C Systems are included under HVAC systems in WARD-D-0165.
o PSAR Table 7.1-1 has been revised to refer to WARD-D-0165.
a.2 Reactor Service Building Filtration System'
.The Reactor Service Building (RSB) Filtration System, along with its safety and seismic classification, is listed in PSAR Table 9.6-5.
This system is a part of the Nuclear Island HVAC Systems, which has been added to PSAR Table 3.2-2 and references.
'back to PSAR Table 9.6-5.
i
-a.3 Control Room Filtration System The Control Room Filtration System, along with its safety and seismic classification, is listed in PSAR Table 9.6-1.
This
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system is a part of the Nuclear Island HVAC systems which.has been added to PSAR Table 3.2-2 and references are provided back to PSAR-Table 9.6-1.
5 Radioactivity Monitorina (Fixed and Portable)
-a.4 Fixed radiation monitors which are safety-related tre. identified in PSAR Table 11.4-1.
PSAR Table 7.1-1 has been revised to refer to Table 11.4-1 for this equipment.
Portablefradiation monitors (including in-plant iodine radioactivity monitoring) are not specifically addressed in the PSAR, however they will be j
addressed at -the Operating License stage.
f
'a.5 Radioactivity Samnling (Air, Surfaces. Lioulds)
Fixed process and ef fluent samplers which are safety-related are identified in PSAR Table 11.4-1.
PSAR Table 7.1-1 has been revised to refer to Table 11.4-1 for this equipment.
a.6 Radioactive Contamination Measurement and Analysis See item a.ll-c L
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f a.7 Personnel Monitorina Internal fe.a.. whole body counter) and External fe.a. TLD system)
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.1See item a.11 a.8 instrument Storace. Calibration and Maintenance See item a.11 a.9 Rgcpntamination (Facilities. Personnel and Eauipment See item a.11 a.10 Resoiratory Protection. Includina Testina See item a.11 a.11 Contamination Control j
Equipment and provisions for the above monitoring and functions i
are not included in the tables of PSAR Sections 3.2 and 7.1.
This equipment and provisions will be addressed in greater detail at the Operating License stage.
a.12 Radiation Shieldino Safety-related radiation shielding are integral parts of Seismic Category I structures as noted in revised PSAR Table 3.2-1.
a.13 Standby AC Auxiliary Power Systems (Class lE)
The diesel generator auxiliary mechanical systems (lube, jacket cooling, air start) are identified in PSAR Table 3.2-2.
The diesel generator auxiliary Class lE electrical systems are included in WARD-D-0165.
Class 1E cebles for the power system and for individual systems are identified in PSAR Table 3.2-3.
Raceways (conduits, cable trays) for safety-related systems are Seismic Category I and Class 1E as indicated in revised PSAR Table'3.2-3.
Component supports for Class 1E equipment are seismic Category I as indicated in modified PSAR Table 3.2-3.
Safety-related electric valve operators, protective relays and control panels, electrical penetrations for containment, and AC vital-bus distribution equipment are all identified in 1
WARD-D-0165.
The battery' packs of the Emergency Lighting System are not classified 1E and are not included in the table of 1E equipment.
Section 9.12 of the SER supports the classification of the' Emergency Lighting System.
p-n 4.,s a.14 DC Power Systems (Class lEL Cables, conduit, and cable trays for the DC Power System are
. - identified in revised PSAR Table 3.2-3.
Component supports (including battery racks for Class lE DC equipment)' are seismic Category I as indicated in revised PSAR Table 3.2-3.
Class lE DC Switchgear, distribution panels and protective relays are listed in WARD-D-0165.
a.15 Containment The containment vessel, internal cell structures, access hatches /airlocks/ doors, the Reactor Cavity Vent System, and mechanical penetrations are integral parts of the Reactor Containment Building (RCB) as indicated in modified PSAR Table 3.2-1.
The RCB electrical penetrations are Class lE and Seismic Category I as indicated in revised PSAR Table 3.2-3.
The Reactor Containment Building Vacuum Relief System is discussed in PSAR Section 6.2.
The safety-related Reactor Containment Vacuum Breaker Valves are included as Isolation Valves in PSAR Table 3.2-2.
The Containment Annulus Filtration System (there is no Confinemenc Filtration System) is listed in Table 3.2-2.
a.16 Emercency Plant Service Water System fadecuacy of water supply)
The source of water for the Emergency Service Water System is the' Emergency Cooling Tower Basin as discussed in PSAR Section 9.9.2.
The Emergency Cooling Tower Basin is listed in Table 3.2-1.
a.17 Component Suoports for Safety Class 1, 2, and 3 Systems Component Supports for Safety Class 1, 2, and 3 components meet-the ASME Code Section III, subsection NF requirements as discussed in PSAR Sections 3.9.1.6 and 3.9.2.6.
Table 3.2-5 has been modified to so indicate.
a.18 Missile Barriers Which Protect Safety-Related Structures, Systems, and Components Protective enclosures and barriers to missiles are identified in PSAR Table 3.5-1 and are integral parts of the Seismic category I str uctures of PSAR Table 3.2-1.
a.19 Biological Shieldina Safety-related radiation and biological shielding are integral parts of Seismic Category I buildings are indicated in revised PSAR. Table 3.2-1.
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a.20 Spent Fuel Pool and Liner The _ Ex-Vessel, Storage Tank (EVST) which stores spent CRBRP fuel
. l is included in PSAR Table 3.2-2.
a.21 Plant Safety Parameter Display Console See11 tem a.22^
a.22 Eauioment and Other Items Associated with the Emeraency Suonort Eisilities The Plant Safety Parameter Display Console and other equipment associated with the emergency support facilities are not safety-related are not included in the tables of Seismic Category I or Class 1E equipment.
This equipment conforms with the requirements of 10 CFR 50, Appendix E and the guidance of NUREG-0696 as confirmed in Section 13.3.2.6.of the SER.
b.1 PSAR Table 3.2-1 has been modified to indicate'that internal structures of seismic Category I structures are included as integral parts.of the seismic Category I structure.
b.2. Seismic Category _ I cable trays have been added to PSAR Table 3.2-3, " Preliminary list of System Components Classified lE" as a footnote..The seismic design of such equipment is discussed in PSAR Section 3.10.
t b.3 Foundation support materials for all Seismic Category I Structures are either bedrock, Class A backfill, or concrete fill.
A description of the inspection verification program during excavation ~and during fill and backfill are included in PSAR Sections 2.5.4.5.1.3 and 2.5.4.5.1.5 and figure 2.5-39.
Class A backfill and concrete fill are included in the CRBRP Quality Assurance Program and as a footnote on revised PSAR Table 3.2-1.
b.4 PSAR Table 3.2-2 has been modified to include the Emergency Plant Service Water System Pipes located in the yard.
-b.5 The SGB Maintenance Bay is a Seismic Category I structure included within the Steam Generator Building as it is defined in PSAR Section 3.8.4.1.3.
PSAR Table 3.2-1 lists the Steam
. Generator Building which by definition includes all the bays, l
including the Maintenance Bay.
l-b.6 PSAR Table 3.2-1 has been modified to include class 1E Electrical Duct Banks and Table 3.2-2 has been modified to include all Seismic Category I buried pipe.
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.b.7L Drainage scuppers which are integral parts of Seismic Category I Buildings (see revised PSAR. Table 3.2-1) control accumulated rainwater on' roofs of some Seismic Category I Buildings.
Other features of the plant buildings and site having to do-with
. drainage. of intense local. precipitation are not Seismic Category I and have not been included in Table 3.2-1.
Justification of
'the classification of these features is found in PSAR Section.
2.4.2.3.
.The NRC staff review 1 SER Section 2.4.3.2 has agreed with ~ this position.
b.8 _The Emergency Chilled Water System'is designed.as Quality Group C, except for the containment isolation valves and interconnecting piping which are Quality Group B.
Section 9.7.2 of the'SER supports the conclusion that the requirements of
' Regulatory Guide 1.29 have been satisfied.
PSAR Table 3.2-2 is correct as written.
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S TABLE 3.2-1 SEISHIC CATEGORY I STRUCT, 'JRES 1.
Containment Building M IN 61l 18 l 2.
Confinement Structure (U 61 l 3.
Reactor Service Area of the Reactor Service Bull ding (1D t
l 4.
Control Bullding (L) 5.
Steam Generator Buildi (N
Building (L)s 'O
. +ewt Mi*
Reeh scal E 6.
Diesel-Genehat 43l 33l 7.
Emergency Cooling Tower Basin 8.
Diesel Fuel Storage Tank Foundation
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33l9.
Electric Manholes
-43 32l /o.
Cless IE B ecfr a l M f S *" ks ( s u d eJO l
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l 5 (C/o.ss A Qg/(*
II IAdudes bMm sw poet wdeNd l
h&. co^e.eeds f.lt l
Y ack Seamk Co%
5 ts5hrnsl huNrej, sa$
Z l
rel raA,edik One t<j, ACCets $alches q{ clock Aors, a+J ram'wder scupr.s eded. gre. 'i.ip/ [s I
,.6 l
e s. u,ng.
I3D self wekanicsl s.fra % s u d & bcb 4'"Y O*'b dent g%f as.4.a m i d eg m / /a4 OA A s b u ki c,4, 3
3.2-8 Amend. 61 Sept. 1981
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4 TABLE 3.2-2 (Continued)
PRELIMINARY LIST OF SEISMIC CATEGORY l ME01ANICAL SYSTEM I3)
COMPONENT 3 AND ASSIGNED SAFETY (1. ASSES Safety Quality III IIII Components Ciass Group Location (2)
Inert Gas Receiving and Processing System Primary Cover Gas Lines (Recycle Argon) 2 B
Rm t
Equalization Line Between Reactor Vessel Primary Pump and Overflow Vessel 2
B R2 RAPS Components (Except Compressors RAPS Large LN Dewars, and Recycle 2
Argon Storage Vessels) 3 C
Rm Recycle Argon Storage Vessels 2
B RCD CAPS Components (Except Compressors) 3 C
RW Y C*
W W
W lb Emergency Plant Service Water System _(5) 3 C
SGB,0GB, Emergency l
hn Emergency Chilled Water System (5) 3 C
SGB, m, DGB RSB, RG l-Auxillary Mechanical Systems f or Diesel Generators 3
C DGB l'
Oll' Storage and Transfer System l
Including:
l DIesei Fue1 01i Storage Tanks SEE Nag /3 YARD Fuel Oil Transfer Pumps 3
C DGB I
Fuel Oil Day Tanks 3
C DGB Cooling Water System Including:
l Water Expansion Tank 3
C DGB Jacints Cooling Heat Exchanger 3
C DGB Water Temperature Regulating Valve 3
C DGB l
Starting Air System including:
Air Storage Tanks 3
C DGB Lubrication System including:
(-
Lubricating Oil Heat Exchanger 3
C DGB
,I Lube Oil Filters and Strainers 3
C DGB Ihk 3.2-10a Amend. 74 Dec. 1982
.a.
I C.Vj a cx TABLE 3.2-2 (Continued) 4
- )3
' PRELIMINARY LIST OF SEISHsC CATIGORY I ECHANICAL SYSTEM COMPONENTS AND ASSIGNED SAFETY CLASSES (33 Sefety Quality -
IN IIII Location (2)
Camponents Class Group Recirculating Gas Cooling System
'3 C
RSB, RCB
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(Subsystem: Serving: Na makeup I
pump cold trap pipeways, Na makeup pump and vessels, EVS pump and cold trap, EVS pumps and pipeways)
Non-Sodlun Fire Protection System l
Piping and Valves Connecting to the 31 C
DGB 3
l Emergency Plant Service Water System Notest
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. (1) Saf ety Classes are defined In Sections 3.2.2.1 through 3.2.2.3 (2) RCB - Reactor Contalnment Bullding IB - Intermediate Bay of the SGB SGB - Steam Generator Building
(.-
RSB - Reactor Service Building
)
CB - Control Bullding DGB - Diesel Generator Building (3) All components will be selsmically quellfled by analysts unless otherwise noted; motors are included with the mechanical compononts they drive.
(4) The SWRPRS rupture disc assembiles wilI be setsmically qualIfled by I
analysis based on rupture data obtained during dynamic testing.
I (5) Cont. ol panel attached to chlt lors w11I be qualIfled by test.
l (6) Out to Second Isolation Valve l
(7) Within Dual isolation Valvet (8) Downstream of Isolation Valve (9) Downstream of Second Isolatton Valye ad Clb4Im
%-(10) Identification of safety-related ventilation 9.6-1, 9.6-4, 9.6-5, 9.6-6 and 9.6 Tables (11) Based on Regulatory Guide 1.26, as Interpreted for an LMFBR (12) The contalmnent annulus cooling system and contaltnent cleanup system shall meet the safety class 3 requirements.
However, these systes are provided for the mitigation of an accident beyond the design basis. Therefore, they are not classified as 50-3, but will be built to ASE 111/3.
(13) Quality assurance is In accordance with Reg Guide 1.137 r
L-3.2-10b Amend. 74 Dec. 1982 L
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Y TABLE 3.2-3 PRELIMINARY LIST OF SYSTEM COMPONENTS CLASSIFl$D 1E Building Electric Power Systea Hotor Control Centers Unit Substations y
125Y DC Distribution Panel Battery Charges inverters Vital Reg. Transformers Batterles
(
4.16 KY Switchgear I
Diesel Generator Sets Diesel Generator XFMR and Resistors r'
Fuel 011 Transfer Pumps l
Na Pump Drive Breaker Trips l
l Connectors and Terminations Cabies, Co Lls frays, and Canofull-
}h Emergency Chilled Water System Isolation Valve Operators Pressure Control Valve Operators Pressure Rollef Valves Emergency Ch!! led Water Pump i
l Control and instrumentation Cabies, c.a bla Tuy.s,.w,I condvil-
]P
- The equipment contained in ihls list are generically Idantifled. The specific, detailed listing of all Class 1E equipment, along with the i
l environmental qualification program to which they are subjected, is provided l
61.
In Reference 13 of PSAR Seeiton 1.6.
Class 1E systems, raceways, l
battery racks,yand their supports are seismic category I.
CAmet elecird gjg4tnS Scend. 61 I
Se@t. 1981
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TABLE 3.2-5 f-PRE 1.lMINARY LIST OF ASE 3STRUCT10N CODES, CODE Q.ASSIFICATIONS, k
AND CODE CASE FOR SEISMIC CATEGCRY I EOiANICAL SYSTEM CO Code / Code Class Code Case Comnonent Fdition/ Addends Revision _
Reittcr Vesse! & Primary Heat Transport System Reactor. Vessel (1)
ASE-Il I/1 1521-1,1592-1,1593-0, 1974/ Winter '74-f 1594-1,1595-1,1596-1, 1682,1690 Closure Head (1)
ASE-Il l/1 1521-1,1592-4,1593-1, 1974/ Winter '74 1682,1690 Primary.Sodlum Past.p Casing (1) ASE 111/1-1521-1,1592-1,1593, 1974/ Winter '74 1594,1595-1,1596-1, 1682 Intermediate Heat Exchangers, ASE 111/1 1521-1,1592-1,1593, lHX (Tubes and Shell) 1974/Stanmer '74 1594-1,1595,1596-1 Primary PIplng ASE Ill/1 1592-7,1593-1,1594-1, 1974/ Summer '75 1595-1,1596-1,1644-4.
!( 1 Reactor Guard Yessel (1)
ASE 111/2 (2) 1521-1,1592-4,1593-1, A
l 1974/Stanmer '75 1594-1,1682-1 Ptsnp and IHX Guard Vessels ASE III/2 1592-4,1593-1,1594-1 1974/Stanmer '74 Upper Reactor Yessei ASE IIl/1 1592-12,1593-1, Internals 1977/Stsnmer 877 1594-1 o Class 1 Appurtenances ASE 111/1 l
1974/ Winter '74 Lower Reactor Vessel ASE 111/1 Internals Hcrizontal Baf fle Assembly 1974/ Winter '76 1592-11 o
o Bypess FIow Module 1974/ Winter '76 1592-11 o Lower Inlet Module 1974/ Winter '76 1592-10 o Fixed Radial Shield 1977/ Winter '77 N-47-16
- Applicable to Safety Class 1, 2 or 3 components.
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Clot,t I 2,0'13 Ctsv wen ~ weef ASME, CwwkT2, f b %
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^W rqude~eds as ktsca.sse0 m PSM Sach 3.9.I.4 s.9. 2. S.
3.2-14 Amend. 74
.Dec. 1982
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TABt.E 7.1-1 A
P SAFETY-RELATED INSTRUMENTATION AND CONTROL SYSTEMS
- Reactor shutdown Svntama i
includes all RSS sensorsi signal conditioning calculation units, comparators, L
buffers, 2/3 logier scram actuators, scran breakers, control rods, back.
contacts on scram breakers, HTS shutdown logic, coolant pisnp breakers, and mechanical mounting hardware (equipment racks).
t Onntainment isolation system.
Includes radiation monitoring sensors, signal conditioning, comparators, 2/3 togic, containment Isolation valve actuators and valves.
Decaw Heat Removal Evstem Instri ntetton and Centrol su b -
L
.. Includes Initiating sensors, signal conditioning, calculation units, l
comparators, logic, auxillary feedwater pump actuators and controls including feedwater turbine pump, PACC DHX actuatccs and controls, steam relief valve actuators _and valves; sensors, signal conditioning, logic and actuators related to decay heat removal functions of DHRS Including control of sodlum and NaK pumps and air blast heat exchangers; and sensors, signal conditioning, log 1c and actuators related to removal of heet from the EVST.
.sg.f uerwater Reaction Pressure Rel f af S tren (swims)
~
The Instrunentation, Initiation and control logic which achievas adequate Isolation and blow-down of the waterside of a superheater or evaporator In the event of a soditan/ water reaction is Class 1E.
The Instrumentation used to initiate the Isolation and blow-down valves are the rupture disc pressure detectors located downstreau of the rupture discs.
The other temperature Instrisnentation distributed throughout the sodlun/ pressure and water reaction pressure relief. subsystem Is used for statur Indication end is' not Class IE.
eThe Cilnch River Breeder Reactor Plant (CRMP) safety-related structures, systems, and components are designed to remain functional In the event of a Safe Shutdown Earthquake (SSE).
These include, but are not limited to, those structures, systems and components which are r.ecessary:
Te assure the Integrity of the Reactor Coolant Boundarys Ja.
b.
To shutdown the reactor and maintain it In a safe shutdown condition
'c.
To prevent or mitigate the consequences of accidents which could
. result in potential of f-site exposures comparable to the guidellne exposures of 10CFR100 NOTE:
Class IE equipment loads.are identlfled.In Chapter 8.
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1 Other Safe +v-Rotated Instrumentetton and control includes Instrtmentation and Controls for portions of the following. functions I.
to assure the plant is maintained in a safe shutdown condition:
"o Emergency Chilled Water System Emergency Piant Ieryles Water System
~ o Instrinnentation necessary to assure plant is maintained in safe o
shutdown status (See Table 7.5-4)
'o Heating, Ventilating, and Air Conditioning Systern
~
Recirculating Gas Cooling System o
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7.1-7a Amend. 74 Dec. 1982 1
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