ML20073S276
| ML20073S276 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 05/05/1983 |
| From: | Longenecker J ENERGY, DEPT. OF |
| To: | Grace J Office of Nuclear Reactor Regulation |
| References | |
| HQ:S:83:248, NUDOCS 8305060524 | |
| Download: ML20073S276 (18) | |
Text
'
I Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:248 MAY 0 5 1983 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 References :
(1) Letter HQ:S:83:241, J. R. Longenecker to J. N. Grace,
" Response to Safety Evaluation Report (SER) Item No. 6 - Quality Assurance," dated April 8,1983 (2) Letter HQ:S:83:246, J. R. Longenecker to J. N. Grace,
" Response to Safety Evaluation Report (SER) Item No. 6 - Quality Assurance,". dated April 28, 1983 Enclosed is a revision to responses previously submitted in the referenced letters that provides additional information to complete the identification of safety-related structures, systems, and components controlled by the Clinch River Breeder Reactor Plant-Quality Assurance Program for the Preliminary Safety Analysis Report. The revisions are indicated with bar lines in the margin and address comments offered by the Nuclear Regulatory Commission (NRC) staff. The enclosed information 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 information may be addressed to Mr. D. Robinson (FTS 626-6098) of the Project Office Oak Ridge staff.
Sincerely,
$b W
B305060524 830505 John R. Longenecker PDR ADOCK 05000 3 Acting Director, Office of E
Breeder Demonstration Projects Office of Nuclear Energy Enclosure cc: Service List Standard Distribution Licensing Distribution
f.
........_m._.....__....
Quality Assurance Branch Questions:
Section 17.1.2.3 of the standard format (Regulatory Guide 1.70) requires the identification of safety-related structures, systems, and components ontrolled by the QA program.
You are requested to supplement and clarify the CRBRP PSAR in accordance with the following:
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 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 Delayed Neutron Monitor Failed Fuel Location System o
Leak Detection Systems o
Sodium Water Reaction Pressure Relief System o
Containment Hydrogen Monitoring System I
o Accident Monitoring System h
2.
Reactor Service Building Filtration System L
3.
Control Room Filtration System l'
4.
Radioactivity Monitoring (fixed and portable) 5.
Radioactivity Sampling, (air, surfaces, liquids) 6.
Radioactive Contamination Measurement and Analysis l.
7.
Personnel Monitoring Internal (e.g., whole body counter) and External (e.g., TLD system)
~
i
. 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 lE) 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 und cable trays and their supports containing Class lE 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 protective devices.
o Emergency lighting battery packs o
AC vital bus distribution equipment 14.
DC Power Systems (Class lE) o Cables o
Conduit and cable trays and their supports containing lE cables and other raceway installations whose failure may damage other safety-related items.
o Battery racks o
DC switchgear, distribution panels and protective relays 15.
Containment o
Primary Containment Structure and Internal Cell Structures o
Access hatches /airlocks/ doors o
Penetration assemblies o
Reactor Cavity Vent System o
Reactor Containment Building Vacuum Relief System o
Confinement Filtration Systems
s.
. 16.
Emergency Plant Service Water System (adequacy of water supply).
17.
Component Supports for Safety Class 1, 2 and 3 systems (see paragraph NF-1214,Section III, ASME Boiler &
Pressure Vessel Code).
18.
Missile Barriers which protect safety-related structures, systems, and components.
19.
Biological Shielding 20.
Spent Fuel Pool and Liner 21.
Plant Safety-Parameter Display Console 22.
Equipment and other items associated with the emergency support facilitias, 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 Table 3.8-2 of the PSAR.
3.
Since foundation support materials (rock, soils, backfill and concrete fill) are not specifically identified in the QA program for Seismic Category I structures, expand Table 3.2-1 to include an entry which reada " Foundations and Foundation Support Material (rocks, soils, backfill, and concrete fill) for Seismic Category I Structures."
4.
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 I structures in PSAR Section 3.8.5.
5.
Expand 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.
..-. ~
i.
7.
All features of the plant building and site having to do with the drainage of intense local precipitation should 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).
Response
The following supplements and clarifications are being made to the PSAR to completely identify safety-related structures, systems, and components controlled by the CRBRP Quality Assurance Program, a.1 Instrumentation and Controls All safety-related instrumentation and control systems and equipment for CRBRP are classified lE.
Reference 13 to PSAR Section 1.6, WARD-D-0165, " Requirements for Environmental Qualification of Class 1E Equipment," provides the list of Class
.lE 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-01G5 is presently being updated to include equipment recently designated Class lE and this upcoming revision will include all the Class 1E instrumentation and control equipment listed in the question with some minor exceptions.
These exceptions are:
o The Failed Fuel Monitoring System is not safety-related, Class 1E, or included in WARD-D-0165.
Sections 7.5.2.3 and 7.5.2.5 of the Safety Evaluation Report (SER) support the non-safety-related classification.
o CRBRP does not employ an accident monitoring system per se.
Accident monitoring is accomplished through a defined set of instrumentation incorporated in other plant systems.
All Category I accident monitoring instrumentation of Regulatory Guide 1.97, which is required to be classified lE, 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 classified as Class lE and are listed in WARD-D-0165.
Section 7.4.2.7 of the SER supports the Remote Shutdown System safety classification.
..._......_e.
5-Also, it 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 Piltration 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.
a.3 Control Recom Piltration System The Control Room Filtration System, along with its safety and seismic classification, is listed in PSAR Table 9.6-1.
This 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.
a.4 Radioactivity Monitoring (Pixed and Portable)
Fixed radiation monitors 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.
Portable radiation monitors (including in-plant iodine radioactivity monitoring) are not specifically addressed in the PSAR, however they will be addressed at the Operating License stage.
a.5 Radioactivity Sampling (Air. Surf aces, Liquids) i Fixed process and effluent 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
(
l See item a.ll l
n _ _ _ ; ;. ; -.. -.. _.. _ :
"J.
. a.7 Personnel Monitorina Internal fe.g.
whole body counter) and External (e.g. TLD system)
See item a.ll a.8 IDrtrument Storage. Calibration and Maintenance See item a.ll a.9 Decontamination (Pacilities. Personnel and Eauipment See item a.ll a.10 Respiratory Protection. Including Testina See item a.ll a.ll Contamination Control Equipment and provisions for the above monitoring and functions 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 Shielding 4
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) a're identified in PSAR Table 3.2-2.
The diesel generator auxiliary Class lE electrical systems are included in WARD-D-0165.
Class lE cables for the power system and for individual systems are identified in PSAR Table 3.2-3.
l Raceways (conduits, cable trays) for safety-related systems are l
Seismic Category I and Class 1E as indicated in revised PSAR L
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 WARD-D-0165.
The battery packs of the Emergency Lighting System
[
are not classified lE and are not included in the table of lE equipment.
However, the Standby Lighting System is classified Class lE up to and including the standby lighting panels, which l
have been added to revised PSAR Table 3.2-3.
Section 9.12 of l
the SER supports the classification of the Emergency Lighting
[
System.
I
~
t
. a.14 DC Power Systems (Class lE)
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 Confinement Filtration System) is listed in Table 3.2-2.
a.16 Emergency Plant Service Water System fadequacy 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 comoonent Supports 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 l
been modified to so indicate.
a.18 Missile Barriers Which Protect Safety-Related Structures.
Systems, and Components L-L Protective enclosures and barriers to missiles are identified in PSAR Table 3.5-1 and are integral parts of the Seismic Category l
I structures of PSAR Table 3.2-1.
E a.19 Biological Shielding l
Safety-related radiation and biological shielding are integral parts of Seismic Category I buildings are indicated in revised PSAR Table 3.2-1.
l
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o.
. a.20 Spent Fuel Pool and Liner The Ex-Vessel Storage Tank (EVST) which stores spent CRBRP fuel is included.in PSAR Table 3.2-2.
a.21 Plant Safety Parameter Display Console See item a.22 a.22 Eauioment and Other Items Associated with the Emercency Suonort Facilities
~~
The Plant Safety Parameter Display Console and other equipment associated with the emergency support facilities are not safety-related and thus are not included in the tables of Seismic Category I or Class lE equipment.
Appropriate portions of the owner's QA program are applied to this equipment as discussed in revised PSAR Page 17A-1 attached.
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.
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, including the Maintenance Bay, b.6 PSAR Table 3.2-1 has been modified to include Clas~s lE Electrical Duct Banks and Table 3.2-2 has been modified to include all Seismic Category I buried pipe.
. b.7 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.
I Quality Assurance of other features of the plant buildings and the site necessary to provide drainage of intense local precipitation is included by footnote in Table 3.2-1.
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.
l I
...f.J_......__._.._._....
9 TABLE 3.2-1 SEISMIC CATEGORY l STRUCTURES 1.
Containment Building 61l 18 l 2.
Confinement Structure (n 61 l 3.
Reactor Service Area of the Reactor Service BuildingtC 4.
Control Bullding (M 5.
Steam Generator Bullding Diesel-Generktc[me,J&<(Jong *)
Eledrued & u I
64 Building (9 6.
43l 33l '7.
Emergency Cooling Tower Basin 8.
Diesei Fuel Storage Tank Foundation 33l 9.
Electric Manholes i
Clasr /E E/ec/nca/ Ouef Sachs (due
~
32l /s.
43 l
Cl) r,J45 fee 4.% suffect mdm'Ab CDla55A b"*
cc yeades %n e they3 ta hrw I d'"'N' % 5 % -'* & rodi k Y
sktilde*q, access ldches ' f 4QUceIct, $0S, G~~l f***U ulick are enegra/ pae4s
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6 m*//t4,
e 4
3
.L clude) leeckanica/ pent,bbm3 et/
IdegynlpahoN%-kecclyCNlnonnNfAk (And see 1
b irahre; ef L lMf bur.We s <~d 3 Ye f
i drno nece>Se
>{,
,gife ef os ecce
- re/4S/ eg 4'ged d cay 4 c*// le n 4%y/en
/ced rec'efshG 4 preve e.
f St&
d
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AgrifrIs$t-frodesok of bSfi c~d co%skac% Qua[*
[ ' sd[ci h N l
Assurwce Wy!"$.
3.2-8 Amend. 61 Sept. 1981 i
e.
=
TABLE 3.2-2 (Continued)
(-
PRELIMINARY LIST OF SEISMIC CATEGORY I PE01ANICAL SYSTEM COMPONENTS AND ASSIGNED SAFETY CLASSESI3I Safety Quality UI Cmp:>nents Class Group (U Location (2)
Inert Gas Receiving and Processing System Primary Cover Gas Lines (Recycle Argon) 2 B
RG Equalization Line Between Reactor Vessel Primary Pump and Overflow Vessel 2
B Rm RAPS Components (Except Compressors 9
RAPS Large LN Dewars, and Recycle 2
}
Argon Storage Vessels) 3 C
Rm Recycle Argon Storage Vessels 2
B R@
CAPS Cmponents (Except Compressors) 3 C
.W Nc7E Jo '^
Emergency P1 ant Service Water System (5) 3 C
SGB,0GB, Emergency Cooling Tower' yard Arb4)
Emergency Chilled Water System (5) 3 C
SGB, G, DGB RSB, RW Auxillary Mechanical Systems for Diesel Generators 3
C DGB l
( ~ Fuel Oil Storage and Transfer System including:
j Diesel Fuel Oil Storage Tanks SE - /VG /3 YARD g
Fuel O!! Transfer Pumps 3
C DGB l
g Fuei Oii Day Tanks 3
C DGB
' Cooling Water System including:
Water Expansion Tank 3
C DGB Jackets Cooling Heat Exchanger 3
C DGB l
Water Tenperature Regulating Valve 3
C DGB h
Starting Air System including:
Air Storage Tanks 3
C DGB l
Lubrication System including:
I Lubricating Oil Heat Exchanger 3
C DGB
(
Lube Oil Filters and Strainers 3
C DGB
\\
!'hkd -
3.2-10a ivnend. 74 ucc, um>
l
.o
TABLE 3.2-2 (Continued) h
' PRE!.lMINARY LIST OF SEISMIC,CATIGORY I E0iANICAL SYSTEM I3I COMPONENTS AND ASSIGNED SAFETY C1. ASSES Safety Quality -
III IIII Ccaponents Class Group Location (2)
Recircut ating Gas Cooling System 3
C RSB, RCB q
(Subsystem: Serving: Na makeup pump mld trap pipeways, Na makeup pump and vessels, EYS pump and cold trap, EVS pumps and pipeways)
Non-Sodle Fire Protection System
.3 Piping and Valves Connecting to the 3:
C DGB j
Emergency Plant Service Water System P
Notesr (1) Saf ety Classes are def ined in Sections 3.2.2.1 through 3.2.2.3 (2) RCB - Reactor Contalnment Bul1 ding IB - Intermediate Bay of the SGB SGB - Stean Generator ButIding
~
RSB - Reactor Service Bullding
)
CS - Control ButIding DGB - Diesel Generator Bullding (3) All components will be seismically quellfled by analysis unless otherwise noted; motors are included with the mechanical components they drive.
.(4) The SWRPRS rupture dise assembiles wilI be setsmically qualIfled by analysis based on rupture data obtained during dynamic testing.
(5) Control panel attached to chillors wilI be qualIfled by test.
l (6) Out to Second Isolatlon Valve l
(7) Within Dual isolation Valves (8) Downstrean of Isolation Yalve i
/
(9) Downstream of Semnd Isolation Valve cod Olbb 1
l I
Q(1D) Identification of saf ety-related ventilation 9.6-1, 9.6-4, 9.6-5, 9.6-6 and 9.6-B.Aequipment is provided in l
Tables h
(11) Based on Regulatory Guide 1.26, as Interpreted f or an 1.MFBR f
(12) The containment annulus cooling system and containment cleanup system-
{
shall faaet the safety class 3 requirenents.
However, these systens
(
are provided for the mitigation of an accident beyond the design basis.
Therefore, they are.not classified as.SC-3, but will be built 7
to Asg lll/3,
~
g (13) QdalIty assiurance ~Is ~in accordan~ce ~with R5g GGide i~.~137
- ~ ~ ~
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e S
8 0 g
"h L-
e
..-a TABLE 3.2-3
(
PRELIMINARY LIST OF SYSTEM COMPONENTS CLASSIFl5D 1E l
/ Building Electric Power System Motor Control Centers l
Unit Substations 125V DC Distribution Panel f
Battery Charges inverters Vital Reg. Transformers BaMerles
\\
4.16 KV Switchgear i
Diesel Generator Sets Diesel Generator XFMR and Resistors Fuel Oil Transfer Pumps Na Pump Drive Breaker Trips Connectors and Terminations suL a Ue. Trays ennd C.enaltai-3P Cables C l
3 kak+ m kets Emergency Chilled Water System Isolation Valve Operators l
Pressure Control Valve Operators 1
Pressure Rollef Valves Emergency Chilled Water Pump.
Control and Instrumentation 1
Cabies, Cab ls h y.s,asn Con)Nh f
- The equipment contained in this list are generically ident! fled. The I
specific, detailed listing of all Class IE equipment, along with the environmental quellfication program to which they are subjected, is provided l
61.
In Ref erence 13 of PSAR Section 1.6.
Class lE systems, raceways, battery racks,yand their supports are seismic category I.
2 $+
f Codm**edt elec4NcAI ga
/cend. 61 L
Sept. 1981
1 TABLE 3.2-5 PRE 1.lMINARY LIST OF ASE ::0NSTRUCTION CODES, CODE Q.ASSIFICATIONS, AND CODE CASE FOR SEISHIC CATEGORY I EOMNICAL SYS Code / Code Class Code Case Comnonent Fdition//ddenda Revtsten i
Reactor Yesse! & Primary Heat Transport System Reactor. Vessel (1)
ASE-li 1/1 1974/ Winter '74 1521-1,1592-1,1593-0, 1594-1,1595-1,1596-1, 1682,1690 Closure Head (1)
ASE-ll I/1 1
1521 1,1592-4,1593-1, 1974/ Winter '74 1682,1690 Primary.Sodlun Punp Casing (1) ASE 111/1 1974/ Winter '74 1521-1,1592-1,1593, 1594,1595-1,1596-1,.
1682 Inte. mediate Heat Exchangers, ASE II I/1 1521-1,1592-1,1593, lHX (Tubes and Shel1) 1974/Strnmer '74 1594-1,1595,1596-1 Primary Piping ASE 111/1 1592-7,1593-1,1594-1, 1974/Sunmer '75 1595-1,1596-1,1644-4 Reactor Guard Yessel (1)
ASE 111/2 (2) 1521-1,1592-4,1593-1, 1974/Sunmer '75 1594-1,1682-1 I
Punp and IHX Guard Vessels ASE 111/2 1592-4,1593-1,1594-1 1974/Sunmer '74 Upper Reactor Vessei ASE III/1 1592-12,1593-1, Internals 1977/Strnmer '77 1594-1 o Class 1 Appurtenances ASE III/1 1974/ Winter '74 l
Lover Reactor Vessel ASE 111/1 Internals Herizontal Beffle Assembly 1974/ Winter '76 1592-11 o
o Bypass Flow Module 1974/ Winter '76 1592-11 o 1.ower Inlet Module 1974/ Winter '76 1592-10 o F1xed Radial Shield 1977/ Winter '77 N-47-16
- Applicable to Saf tely 'Cl ass 1, 2' or 3 ' components.
9 e dt s +
- p h e r S o fe g @ *cwhI!!, NJSeek W rep
~,c4e as Auca:t z,e 3 ereeds {
C sac'h ms 3.t /.4 d 3 9. 2. M.
Se$
r.* F5e
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3.2-14 A.end. 7 4.
~
J. 1982
TABl.E 7.1-1 SAFETY-RE!.ATED INSTRIJfENTATION AND CONTROL SYSTEMS
- 4 Reee+or Shutdown Svsta==
Incli. des all RSS sensors, signal conditioning calculation units, comparators, buf fers, 2/3 logic, scram actuators, scram breakers, control rods, back contacts on scram breakers, HTS shutdown logic, coolant ptsnp breakers, and mechanical mounting hardware (equipment racks).
Contelnment isoletion System includes radiation monitoring sensors, signal condt' loning, 'comparators, 2/3 t
logic, contairrnent Isolation valve actuators and valves.
r>ecey Heat Removal Svstem Instrumentetton end Control 1vs1 -
i includes initiating sensors, signal conditioning, calculation units, comparators, logic, auxiliary feedwater pump actuators and controls including feedwater turbine pump, PACC CHX actuators and controls, steam relief valve actuators and valves; sensors, signal conditioning, logic and actuators related to decay haat removal functions of DHRS Including control of sodlum and NaK pumps and air blast heat exchangers; and sensors, signal conditioning, logic and actuators related to removal of heat from the EYST.
p( glum-Weter Rea'-tf on proceure Rallef System (SWRDRS)
(
l "lho Instrisnentation, initiation and control logic which echieves adequate (k lualation and blow-down of the waterside of a superheater or evapor
[ cyc.at of a sodlisn/ water reaction is Class 1E.
The Instrinnentation used to Initiate the Isolation and blow-down vanes are the rupture disc pressure detectors located downstrean of the rupture discs.
The other pressure and temperature Instrisnentation d!stributed throughout the sodlum/ water reaction pressure relief subsystem is used for status indication and is not Class 1E.
- The Cilnch River Breeder Reactor Plant (CRBRP) safety-related structures, systems, and components are designed to reeln f uncticnst in the event of a Safe Shutdown Earthquake (SSE).
structures, systems and components which are necessary:These incl u i
To assure the integrity of the Reactor Coolant Boundary; a.
b.
To shutdown the reactor and maintain it in a safe shutdown condition; To prevent or mitigate the consequences of accidents which could c.
result-la potential of f-site exposures comparable to the guideline exposures of 10CFR100.
NOTE-Class IE equipment loads are Identifled in Chapter 8
(
A ele b 4 0 ( M g c 9 a S C. W s 1 6 lobu.d$/w ad CMW b.
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9p4 4 h proJJe) tA te$veste S. of PsM &cM M-
.w-a. ' r.
- 7. i-r March-~1983
...-.....-._--..~...va...
other Safe +v-Rolated Instromantation andMrgi
'to assure the plant is maintained in a safe shutdown cond o
Emergency Chilled Water System Emergency P!an? Servira Water System o
Instrinnentation necessary to assure plant is maintained in safe o
shutdown status (See Table 7.5-4) 7 Heating, Ventilating, and Air Conditioning Syst'em o
Recircutating Gas Cooling System o
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g "O %pler.s C See T&le. ft.t-1) gi g,a %L, k ra-die A
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CLIN 01 RIVER BREE0ER REACTOR PLMIT r
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A DESCRIPTION OF THE OWNER QUALITY ASSURANCE PROGRAM 0.
_ INTRODUCTION 0.1 SCOPE Contained heroin is a description of the plans and actions by the Owner to assure the olualIty of structuren, systems, and components of the Clinch River Breeder Reactor Plant (CRBRP)., These plans and actions constitute the Owner's Qual Ity Ar,surance Progran.
0.2 HASIS The progran described herein has been planned, structured and defined to f ul fili the responsibiity for ultiteate of fectiveness and adequacy of the over el l Project Qual ity Assur6nce Pr ogr an.
ResponsibiIty for estabiIshing and executing portions of the overail Project Quality Assurance Progran has been or wIlI be delegated to'others parti 61pating in the Project wIth ultimate responsibility for the adequacy of their performance retained by the Owner.
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0.3 ADPLICATI'ON The Owner's Quality Assurance Progran ~ described herein is applicable to the planning, design, procuranent, manuf acturing, construction including testing,
.C and operation of those saf ety-related structures, systons, and components g identif ied in Section 3.2, 7.1.end 9.13 of this PSAR.
For the Owner's purposes the progran described heroin is not, limited to this application alone, however, and is or will, be appropriately applied by the Owner to the OtBRP in its entirety including alI structures, systons and components where satisf actory perf ormance is required f or the plant to operate rollably sa f,e.t y fcSe$ ybdm3, and with minimum environmental of fects. Spaefc, Erdwlc/rs af cA26M AM=
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N 1.0 ORGANIZATION
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Tha Owner is ESPONSIBLE foF the overalI management of the Project to design, build, and operate the Clinch River Breeder Reactor Plant (CRBRP). The execution of this responsibility rests wIth the CRBRP Project Director, who is the principal operations of ficer of the Owner.
Part of this responsibi!Ity is
- to assure that tha plant is. designed, built and operated in a way that will provide adequate conf idence that it wil l perf orm satisf actorily in service.
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To provide for this assurance, the Project Director has directed the establ ishment and conduct of an overal I Integrated qual Ity assurance progran which shalI have the objectives, carry out the f unctions, and be executed as s
hercafter defined.'
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1.1 FUNCTIQU The f unctions fhat the Ownei will perf orm in order to achieve the stated objectives of the Qual ity Assurance Progran and f ul fil l its ultimate responsibil ity for progran adequacy are as f ollows:
l 17A-1 Amend. 70
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Aug. 1982