ML20073A120

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Forwards Responses to Questions Re Identification of safety- Related Structures,Sys & Components by Crbr QA Program.Info Should Enable NRC to Complete Review of QA List & Close Out SER Open Item 6
ML20073A120
Person / Time
Site: Clinch River
Issue date: 04/08/1983
From: Longenecker J
ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To: Grace J
Office of Nuclear Reactor Regulation
References
HQ:S:83:241, NUDOCS 8304110667
Download: ML20073A120 (22)
v • d • e


Text

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O Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:241 '0

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gpg 0B D63 Or. J. Nelson Grace, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Dr. Grace:

RESPONSE TO SAFETY EVALUATION REPORT (SER) ITE:4 NO. 6 - QUALITY ASSURANCE (QA)

Enclosed are responses to recent questions raised in discussicn with the Nuclear Regulatory Commission staff regarding the identification of safety-related structures, systems, and components controlled by the Clinch River Breeder Reactor Quality Assurance Program. The enclosed information should enable the staff to complete their review of the QA list and close out SER Open Item No. 6 listed in Section 1.6 of the SER. The encicsed Preliminary Safety Analysis Report (PSAR) change pages will be incorporatad in the riext scheduled PSAR amendment.

Any questions regarding the enclosed information may be addressed to Mr. D. Robinson (FTS 626-6098) of the Project Of fice Oak Ridge staff.

Sincerely, J n R. Longene er Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy Enclosure cc: Service List Standard Distribution Licensing Distribution pek

@ O4110667 83040s

{DRADDCK 05000537 PDR

, . 1 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 followings

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:

i o Annulus Filtration System

)

o Reactor Service Building Filtration System o Steam Generator Building Aerosol Release Mitigation System o Outlet Steam Isolation Syster o

o Core Criticality Nonitoring System Pressure Controlled Bypass Velves (AFN Pumps) o APR Isolation Valves & Pump Inlet Isolation Valves l o Steam - Feed Flow Mismatch & Steam Drun Level Interlock Subsystem o Remote Shutdown System

  • e Emergency Plant Service Water System o Emergency Chilled Water System o Failed Fuel Monitoring System Cover Gas Monitor Delayed Neutron Monitor l Failed Fuel Location System o Leak Detection Systems o Sodium Water Reaction Pressure Relief System ,

i 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)
5. Radioactivity Sampling (air, surfaces, liquids)
6. Radioactive Contamination Measurement and Analysis i
7. Personnel Monitoring Internal (e.g., whole body counter) and External (e.g., TLD system)
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, voltuge regulatory and ,

excitation system).

o Instrumentation, control and power cables (including underground cable system, cable splices, 4 connectors and terminal blocks).

'c Conduit and cable trays and their supports containing Class lE cables and other raceway installations whose failure may damage other ,

safety-related items.

o Valve oprators

' 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 1E) o Cables o Conduit and cable trays and their supports containing lE cables and other raceway installations whose failure may damage other i safety-related items.

o Battery racks o DC switchgear, distribution panels and protective relays d

15. Containment -

o Primary. Containment Structure and Internal Cell Structures o Access hatches / locks / doors o Penetration assemblies o Reactor Cavity Vent System o Reactor Containment Building Vacuum Relief System o Confinement Filtration Systems

16. Emergency Plant Service Water System (adequacy of water supply).

i

17. Component Supports for Safety Class 1, 2 and 3 systems (see paragraph NF-1214,Section III, ASME Boiler &

Pressure Vessel Code).

' 18. Miaalle Barriers which Irotect safety-related structures, systems, and componente.

19. Biological Shieldir.g
20. Spent Fuel Pool and Liner 21, Plant Safety-Parameter Display Console
22. Equipment and other items arsociated 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 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 reads " Foundations and Foundation Support Material (rocks, soils, backfill, and concrete fill) for Seismic Category I Structures."

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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 i

Class 1E Electrical Ducting and Category I Pipe" which are identified as such in PSAR Section 3.8.5.1.1.

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 l drains, underground drainage systems, paved ditches,
culverts and site grading.
8. The Emergency Chilled Pater System is designifad as Quality Group C in Table 3.2.2. We require the system to be Quality Group B (Safety Class 2) .

j

Response

The following supplements and clarifications are being made to the i PSAR to completely identify safety-related structures, systems, and i

components controlled by de CRBRP Quality Assurance Program.

a.1 Instrumentation and Controln All safety-related instrumentation and control systems and equipent for CRBRP are classified lE. Reference 13 to PSAR Section 1.6, WARD-D-0165, " Requirements for Environmental Qualification of Class IE 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-0165 is presently being updated to include equipment recently designated Class lE and thir upcoming revision will include all the Class lE instrumentation and control equipment listed in the question with some minor

. exceptions. These exceptions ares o The Failed Fuel Monitoring System is not safety-related, i Class lE, or included in WARD-D-0165. Sections 7.5.2.3 and 7.5.2.5 of the Safety Evaluation Report (SER) support the i

non-safety-related classification.

l l

r 5-l i

o CRBRP does not employ an accident monitoring system per se.

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 lE, is included in WARD-D-0165.

o The Remote Shutdown Systeu is not classified lE in its entirety, however, the Class 1E portions are listed in l

WARD-D-0165. Section 7.4.2.7 of the SER supports the Remote Shutdown System safety classification.

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 honitoring System included in WARD-D-0165.

! o The Annulus and Reactor Service Building Filtration I&C I Systema 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 Buildino Filtration System l The Reacter 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 Room Filtration 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.

d a.4 Radioactivity Monitorino (Fixed 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 will not be safety-related and are not specifically addressed in the PSAP., however they will be addressed at the Operating License stage.

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a a.5 Radioactivity Samplino (Air, Surfaces. Liouids) -

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 See item a.11 a.7 Personnel Monitorino Internal (e.o., whole body counter) and External (e.o. TLD system)

See item a.ll a.8 Instrument storage. Calibration and Maintenance See item a.11 i

Decontamination (Facilities. Personnel and Eculoment a.9 See-item a.ll '

a.10 Resoiratory Protection, includine Testino Contamination Cinirsl Ecuipment See item a.11 a.11 Contamination control Equipment and pr,ovisions for the above monitoring and f unctions

! are not considered safety-related and are not included in the tables of PSAR Sections 3.2 and 7.1. This equipment and l

provisions will be addressed in greater detail at the Operating License stage.

a.12 Radiation Shielding Safety-related radiation shielding are integral

  • parts of Seismic Category I structures as noted in revised PSAR Table 3.2-1.

e.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 4

. . ...: . j included in WARD-D-0165. I system Class lE cables for the power and for individual systems are identified in PSAR Table 3g c3.

Raceways, e.g. conduit and cable trays, for safety-relate'd systems  ;

are seismic category I and Class lE as indicated in revised PSAR Table 3.2- 3. Component supports for Class lE 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. Section 9.12 of the SER supports the classification of the Emergency Lighting System.

a.14 E Jpwer Systems (Class lE)

Cables, conduit, and cable trays for the DC Power System are identified in revised PSAR Table 3.2-3. Component cupports (including battery lacks for Class 13 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 fontainment '

f l The containment vessel, internal cell structures, access -

hatches / doors, and mechanical penetrations are integral parts of i

the Reactor Containment Building as indicated in modified PSAR Table 3.2-1. The Reactor Cavity Vent System is provided to mitigate accidents which are beyond the design base and is listed along with other such features in figure 1-1 of Reference 10b of PSAR Section 1.6. 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 suoply)

The source of water for the Emergency Service Water System is the Emergency Cooling Tower Basin as discussed in PSM Section 9.9.2. The Emergency Cooling Tower Basin is listed in Table 3.2-1. .

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a.17 Component supports for safety class 1, 2. and 5 Systems 1

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 f

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 structures of PSAR Table 3.2-1.

a.19 Biolocical Shielding Safety-related radiation and biological shielding are integral parts of Seismic Category I buildings and are indicated in revised PSAR Table 3.2-1.

a.20 .Soent Ftm1Jg.gl an6__Liwt1 The Ex-Vessel Storage Tank (EVST) which stores spent CR3RP f uel is included in PSAR Table 3.2-2.

St.21 f.Jant Sa h l E.Amst m Disolay Console

! See item a.22 a.22 Eauinment and Other Items Associated with the Emercency Sucoort Ficilitigg The Plant Safety Parameter Display Console and other equipment associated with the emergency support facilities are not i safety-related and-are not included in the tables of Seismic .

Category I or Class lE 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 bee.. modified to indicate that internal i structures of Seismic Category I structures are included as
. integral parts of the Seismic Category I structure.

4

9-b.2 Seismic Category I cable trays have been added to PSAR Table 3.2-3, " Preliminary list of System Components Classified IE" as a footnote. The seismic design of such equipment is discussed in PSAR Section 3.10.

b.3 Foundation support matericls were not included in PSAR Table 3.2-1, " Seismic Category I Structures", however the requirements and a description of the inspection verification program during excavation and during fill and backfill are included in PSAR Seccions 2.5.4.5.1.3 and 2.5.4.5.1.5 and figure 2.5-39.

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 Class lE Electrical Duct Banks and Table 3.2-2 has been modified to include all Seismic Category I buried pipe.

b.7 Features of the plant buildings and sits h'aving to do uith drainage of intense local precipitation are not Soisnic Category .

I and have not been included in "able 3.2-1. Justification of the classification of these features is found in PSAR Section 2.4.2.3. SER Section 2.4.3.2 suoports this position.

b.8 The Emergency Chilled Water System is designed as Quality Group C, except for the containment isolation valves and i

interconnecting piping which are Quality Group B. Section 9.7.2 of the SER supports the conclusion that the requirements of Regulatory Guide 1.2 6 have been satisfied. PSAR Table 3.2-2 is '

correct as written.

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4 TABLE 3.2-1 .

SEISMIC CATEGORY I STRUCTURES

1. Containment Building 61l 18 2. Confinement Structure (D 61 l 3. Reactor Syvice Area of the Reactor Service But I ding u)
4. Control Bullding
5. O Steam Generator Building g

%.. 8Tec4rical QAteme~d Baih*

6. Diesel-Generator Building l0 l 43l 33\7. Emergency Cooling Tcwer Basin
8. Diesel Fuel Storage Tenk Foundation l 9. Electric Hanholes 43 32l /O' l

i.

ihr AA S /

(l') Q 9ettrwth, b e teSS \ t 5f j

r h% 3d ce' takOM P'N dh A N *

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3.2-8 Amend. 61 Sept. 1981

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TABLE 3.2-2 (Continued) ~ ' l

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PRELIMINARY LIST OF SEISMIC CATEGORY I MECHANICAL SYSTEM

[,

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COMPONENTS AND ASSIGNED SAFETY CLASSES (3)

Safety Quality.

Con , onents CIass(1), Group (11)~ Location (2)

Intrt Gas Receiving and Processing System . ,

Primary)

Argon Cover Gas Lines (Recycle 2 .

B RC8 Equalization Line Between Reactor .

Vessel Primary Pump and Overf low 2 B RC8 Vessel RAPS (Outside Containment) 3 C RSB 36 RAPS (Inside Containment) 3 C RC8

  • CADS (Outside Contelnment) 3 C ,

RSB l bloc f. gar .a d ifVAc. s e e, /> M /0 7

i f

J Eraer anncy Plea 1 Ter vnce Water Systun (5) 3 C SGB,0GB, f20 Emergency Cooling Towe' yard (bm/) ~

Emsrgency Chitled Water Syst m (5) 3 C SGB, CB, DGB l20 RSB, RCB g Auxiliary Mechanical Systems for Diesel G:nerators 3 C DGB Fust Oil Storage and Transfer System les uel Oil Storage Tanks SEE Mob /3 YeN Fuel Oil Transfer Pumps 3 C DGB Fuel Oil Day Tanks 3 C DGB Cooling' Water Systs including:

Water Expansion Tank 3 C DGB Jackets. Cooling Heat Exchanger 3 C DGB l Water Temperature Regulating Valve 3 C DGB Stcrting Air System including: ,

Air Storage Tanks 3 C DGB Lubrication System including:

t Lubricating Oil Hoat Exchanger 3 C DGB Lube Oil Filters and Streiner_s 3 C DGB ,

s ^

I l 3.2-10s . Amend. 6'1 Sept. 1981

TABLE 3.2-2 (Continued) b) PRELIMINARY LIST OF SEISMIC CATEGORY l KuiANICAL SYSTEM I3 COMPONENTS AND ASSIGNED SAFETY Q. ASSES Safety Quality .

Class IU Group (IU Location (2)

Ccrnponents _

Recirculating Gas Cooling System 3 C RSB, RG

,- (Subsystems SeryIng: Na makeup pump cold trap pipeways, Na makeup pump and vessels, EVS pump and cold trap, EYS pumps ,

and pipeways)

Non-Soditrn Fire Protection System 3 C DGB Piping and Valves Connecting to the Emergency Plant Service Water System

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Notest (1) Saf ety Classes are def ined in Sections 3.2.2.1 through 3.2.2.3 (2) RG - Reactor Containment Building f B - Intermediate Bay of the SGB SGB - Steam Generator Building i . -

RSB - Reactor Service Building i G - Control Building DGB - Diesel Generatcr Building .

(3) All components will be seismically quellfled by analysis unless I

otherwise noted; motors are included with the mechanical components

they drive.

(4) The SWRPRS rupture disc assemblies will be seismically quallfled by analysis based on rupture data obtained during dynamic testing.

l (5) Control panel attached to chillors w11I be qualIfled by test.

l (6) Out to Second Isolation Valve (7) Within Dual Isolation Valves *

(8) Downstrem of isolation Yelve (9) Downstreern of Second Isolation Valve Q(10) Identification of saf ety-related ventilation equipment is provided in Tables 9.6-1, 9.6-4, 9.6-5, 9.6-6 and 9.6-8.

(11) Based on Regulatory Guide 1.26, as Interpreted f or an LMFBR (12) The contalrunent annulus cooling system and cont'airunent clennup systen shall meet the saf ety cl ass 3 requirements. However, these systems l

are provided for the mitigation of an accident beyond the design l basis. Therefore, they are not classified as scc 3, but wlil be built

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to ASE lil/3.

(13) Quality assurance is in accordance with Reg Guide 1.137 3.2-10b Amend. 74 Dec. 1982 l

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TABLE 3.2-3 PRELIMINARY LIST OF SYSTEM COMPONENTS CLASSIFIED 1E N

Building Electric Power System Motor Control Centers Unit Substations 125V DC Distributton Panel Battery Charges ,

Inverters -

Vital Reg. Transformers Estteries 4

4.16 KV Switchgear Diesel Generator Sets

,, Diesel Ge.nsrator XFMR cnd Resistors I

Fuel Oil Transfer Pumps v Na Pump Drive Breaker Trips i Connectors and Terminations -

Cabt es, Ca Us frays, ennd Conduif }h Emergency Chilled Water System isolation Valve Operators

  • Pressure Control Valve Operators ,

Pressure Rollef Yalves .

Emergency Chilled Water Pump Control and Instrumentation Cabies,C.aflaDays,an Cone l0f f ,

  • The equipment contained in this list are generically Identified. The specific, detailed listing of all Class IE equipment, along with the environmental quellfication program to which they are subjected, is provided 61' in Reference 13 of PSAR Section 1.6. Class lE systems, raceways, battery racks, and their supports are seismic category I.

3.2-11 Amend. 61 Sept. 1981

TABLE 3.2-3 (Continued) i Heating, Ventilating, and Air Conditioning System Unit Coolers '

. Energency Chillers Supply Fans Exhaust Fans J.*r Handling Units Control Room i'llter Fans Control Room Filter Units

'catr'o! Room HVAC Mcnitors -

r Control Rc:n Air Cenditiosiing Units Aux. Buildir.g HX Air Conditioning Units Control and Instrumentation

~

Cabies, cad /c Tor, < n./ C#ft.M.E[ [ (

Reactor Contelnment Eystein RCB TMBDB instrumentation Panels Containment instrumentation Panels Cables >Co Ycb*Yh and Conddl }p ,

Recirculating Gas Cooling System .

Local Control Panels d

Solenold Valves Moisture Switches Liquid Level Switches Cold Trap Flow Switches 61 3.2-11a Amend. 61 Sept. 1981

TABLE 3.2-3 (Continued)

Cold Trap Temperature Switches Pump Temp. Switch.

Fan Motor Cables; C # )# -

Nuclear Island General Purpose Maintenance Equipment System Contalrvnent isolation Yalve Operators Cables , G ble Trays , a n d Conclutl ]P Steem Generator Auxiliary Heat Renoval System Auxiliary Feedwater Pump Hotors ,

Auxillary Feedwater Flow Meter Protected Air Cooled Condenser Condensate Flow Motor Auxillary Feedwater Valve Operators

, Vent Control Valve Operators '

Water Storage Tank Fill Valve Operator AFW Turbine Steam Supply Valve Operator AFW Turbine Pressure Control Valve Operator Cabies, Ca h N $roy$ , a n) Cees NVt f Steam Generator System Feedwater Valve Operators ,

, Superheater Outlet Yalve Operator s ,

Steam Drum Drain Yalve Operators Cables, Cab l< NOV5 ; O nN CoNEb p l Sodium-Water Reaction Pressure Relief Systcnn Instrumentation and Controls Amend. 76

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TABLE 3.2-3 (Continued)

Reactor Heat Transport InstrumenEetion System E6 actor inte1 Pressure Transe.itter Reactor Ytssel Na Level Transmitter Na Flow Sensor ,

PRI IHX Outlet Na Tent Sensor Signal Conditioning, PHTS Pony Motors Primary Ptap Tachometer instrument Rocks Instrumentation

! Reaction Products Dump Line Pressure Switches IHTS FM F1ow Sensoi-Superheater and Steam Drum Vent Control Yalve Operator Temperature / Leak Detection Instrumentation Steam Flow Meter I

Superheated Steam Temperature Sensor

Superheater Steam Pressure Sensor ,

l l Feedwater Flow Meter Feedwater Flow Meter l

Feedwater Temp. Sensor Evap. Outlet Sodium Temp. Sensors 61 Cables, c A l< [ra ,,) gj,,)

  • l Amend. 61 3.2-11c Sept. 1981

. .. a >. .. . . -. . . . . . .

TABLE 3.2-3 (Continued)

Emergency Pl ant Service Water Sys, tem Pump Motors '

ECT Fans

  • Makeup Pump Motors Temp. Control Yalve Operators Temp. Transmitters .

' Temp. Indicator Controllers

' Pressure Differential Switches i Level Switches Cables j CcgheINV?s On #

Auxillary Liquid Metal System Valve Operators

  • k OverfIow TherreocwpIes Local Panels Pump Motors l Control Cabinets Capacitor Cabinets l

l Transformer Cabinets 1

i EYST Thermocouples Control Room Panels .

Cables y Co{lc Troy 3, an) (sodylt EVST Cell Termperature Thermocouples i

l 1

i l

3.2-11d l Amend 62 i

Nev. 1981

4 ..

TABLE 3.2-3 (Continued)

Inert Gas Receiving and Frocessing Systems Containmer.t isolation Yelve Operators Ev ansion Tank Equalization Valve Operator Cabies, Coo l< Trays > G n) Conc lvW }f Plant Control System Main Control Panet SCRAM Breaker Cubicle Cat.Ies, Cdl<. Yats, onY 0# "'

Reactor and Vessel Instrumentation System Reactr Coolant Operating Level Instrumentation Cabies; labf< Tray 5, Qr$ ConYVih Flux Monitoring System

(

Flux Monitoring Instrumentatfor.

Cabinets instrument Drawers Cables, lob < h a y.S on Dn ub h Plant Protection System Containment Isolation System Cabinets Reactor Shutdown System Cabinets ,

Plant Protection System Cabinets 61 Cables, Cob /c [roy3, a n M CoMai [ p I

I 3.2-11e Amend. 61 Sept. 1981

i TABLE 3.2-5

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PRE 1.lMINARY LIST OF ASE (X)NSTRUCTION CODES, CX)DE Q.ASSIFICATIONS,

k AND CODE CASE FOR SEISMIC CATEGORY I E04ANICAL SYSTEM COMPONENTS
  • Code / Code Class Code Case Comnenent Edition / Addenda Reviston Reactor Vessel & Primary Heat Transport System Reactor . Vessel (1) ASE-l l I/1 1521-1,1592-1,1593-0, 1974/ Winter '.74 1594-1,1595-1,1596-1, 1682,1690 Closure Head (1) ASE-I l l/1 1521-1,1592-4,1593-1, 1974/ Winter '74 1682,1690 Priinary Sodlun Punp Casing (1) ASE 111/1 1521-1,1592-1,1593, 1974/ Winter '74 1594,1595-1,1596-1, 1682 Intennediate Heat Exchangers, ASE 111/1 1521-1,1592-1,1593, IHX (Tubes and Shel1) 1974/Strnmer '74 1594-1,1595,1596-1 Primary Piping ASE 111/1 1592-7,1593-1,1594-1, 1974/Stenmer '75 1595-1,1596-1,1644-4 Reactor Guard Vessel (1) ASE 111/2 (2) 1521-1,1592-4,159 -1, 1974/Sunmer '75 1594-1,1682-1 Punp and lHX Guard Vessels ASE 111/2 1592-4,1593-1,1594-1

'974/Stenmer '74 Upper Reactor Vessel ASE. II l/1 1592-12,1593-1, Internals 1977/ Summer '77 1594-1 o C1 ass 1 Appurtenances ASE III/1 j 1974/ Winter '74 Lower Reactor Vessel ASE lil/1 Internals o Horizontal Baf fle Assembly 1974/ Winter '76 1592-11 o Bypass Flow Module 1974/ Winter '76 1592-11 o Lower inlet Module 1974/ Winter '76 1592-10 o Flxed Radial Shield 1977/ Winter '77 N-47-16 .

  • Applicable to Saf ety Cl ass 1, 2 or 3 components.

C q% uod  % Tlt s e t er Sokgclass I, z,n 3 cru hads mee/ $#E, I Useek ^tF y qwiweds as ks casse0 is P5*&

, S ec. h s , 3.9. /.4 o + J 3 9. 2. Fa. '

k 3.2-14 Amend. 74

.Dec. 1982

i TABLE 7.1-1 SAFETY-RELATED INSTRUMENTATION AND CX)NTROL SYSTEMSe

. i J

Reactor St utdown Swatama

' includes all RSS sensors, signal conditioning calculation units, comparators, buf fors, 2/3 togle, scram actuators, scran breakers, control reds, back

  • l contacts on scram breakers, HTS shutdown logic, coolant punp breakers, and mechanical mounting hardware (uquipment rocks).

Containmant isolation Svstem includes radiation monitoring sensors, signal conditioning, comparators, 2/3 logic, contaltnent isolation valve actuators and valves.

Decaw Heat Removal Svstem Instrumentation and Control System includes initiatina sensors, signal conditioning, calculation units, <

comparators, logic, auxillary feedwater pump actuators and controls including feedwater turbine pump, PACC DHX actuators and controls, steam relief valve 4 actuators and valves; sensors, signal conditioning, logic and actuators related to decay heat removal functions of DHRS Including control of sodlum and NeK pumps and air blast heat exchangers; and sensors, signal conditioning, logic and actuators related to removal of heat f rom the EVST.

sodlum-water Reac+1on Pressure Raffef Svstem (SwRPRS) i The Instrunentation, Initiation and control logic which achieves adequate Isolation and blow-dow . of the waterside of a superheater or evaporator in the even^ of a sodium / water reaction Is Class IE. The Instrunentation used to Initiate the Isolation and blow-down valves are the rupture disc pressure detectors located downstream of the rupture discs. The other pressure and temperature Instrunentation distributed throughout the sodlum/ water reaction i pressure relief subsystem is used for status Indication and is not Class IE.

  • The Clinch River Breeder Reactor P1 ant (CRBRP) saf ety-related structures, systems, and components are designed to remain functional In the event of a Safe Shutdown Earthquake (SSE). These include, but are not,Ilmited to, those
structures, systems and components which are necessary

! a. To assure the Integrity of the Reactor Coolant Boundary; l b. To shutdown the reactor and maintain It In a safe shutdown mndition; I

c. To prevent or mitigate the conesquences of accidents which could result in potential of f-site exposures comparable to the guideline exposures of 10CFR100 NOTE: Class IE equipment loads.are identified in Chapter 8.

s ap.c wm a a e n w 1.a s s J C & l 3 y& t\ f t&tk th $tbeNte R ch PSU $*CY5 Y.

i I 7.1-7 rhlh3

Other Safetv-Related Instrumentation and Control includes Instruentation and Controls for portions of the following functions I.

to assure the plant Is maintained in a safe shutdown conditions q Emergency Chilled Water System o Emergency Plant Service Water System '

o Instruentation necessary to assure plant is maintained in safe shutdown status (See Table 7.5-4) o Heating, Ventilating, and Air Conditioning System o Recirculating Gas Cooling System o Process na E+Ylued hbuk %krs \

u & % yler.s C % 7&le. It.t-I ) \

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l 1

7.1-7a Amand. 74 l

1 Dec. 1982

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