ML19332C825
| ML19332C825 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 11/03/1989 |
| From: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | Rouse L NRC |
| References | |
| 26072, NUDOCS 8911290049 | |
| Download: ML19332C825 (16) | |
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TABLE OF CONTNETS iii 14 iii 20 vii 13 vii 20 Chapter 1 1-5 13 1-5 20 1-7 15 1-7 20 Chapter 10 10-47 13 10-47 20
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A6 Issue Date: 11/03/89 APPLICATION FOR RENEWAL'
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SPECIAL NUCLEAR MATERIAL LICENSE N0. SNM-1227 (NRC DOCKET N0. 70-1257)-
E DISTRIBUTION L. A. Bisping T. A. Bjernard B. N. Femreite
'E. L. Foster R. G. Frain C. J. Francis J. W.'Fredericks L. D. Gerrald-
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J. L. Glesener 1 V
'W.-V.-Jackson D. C. Kilian:
D. C. Lehfeldt C. W. Malody T. W. Patten J. E. Pieper T.. C. Probas::o (4)
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ANF2-jn SPECIAL NUCLEAR MATERIAL UCENSE NO. SNM 1227, NRC DOCKET NO. 701257
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n TABLE OF CONTENTS M V.
20 l
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FORWARD 01; PART I - LICENSE CONDITIONS
, CHAPTER.I'- STANDARD CONDITIONS AND SPECIAL-AUTHORIZATIONS I
c 1.1 Corporate Information 1 l 1.2
. Site Location 1-1 1.3 License Number and Period of License 1-l' t
- 1. 3.1 -
Special: Nuclear Materials License 1-1 1.4' Possession Limits; 1-2 1.4.1-Uranium-235 (20,000 Kilograms) 1-2
- 1. 4 ' 2
- Plutonium (Less Than 500 Grams) 1-2 1.5:
Authorized Activities 1-2 L
.l.6 Exemptions and Special Authorizations 1-2' L
1.6.1 Criticality Accident Alarm System Exemption 1-2 1.6.2 Special Processing of Uranium Enriched From 5 to g'
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19.99 wt% U-235 1-4 1.6.3-Plutonium Storage 1 l~
1.6.4' Posting Exemption 1-6 i
1.6.5 Waste Disposal 1-6 4
l'.
1.6.6 Special Nuclear-Material Safeguards.
1-6 1;6.7
. Authorization at Reactor Sites 1-7 '
1.6.8 Authorization Release Guidelines 1-7 l1 1.6.9 Authorized Criticality Alarm System Outage 1-7 l
CHAPTER 2 - ORGANIZATION AND ADMINISTRATION 2-1 2.1 Organizational Responsibilities and Authority 2-1 2.1.1 President and Chief Executive Officer 2-1 2.1.2 Vice President, Engineering and Production 2-1 2 ' l.' 3 Manager, Operations-Richland 2-1 1
ll 2.1.4 Manager, Plant Operations 2-2 y
i.
2.1.5 Manager, Process and Equipment Engineering 2-2 p
2.1.6 Manager, Facilities and Equipment Engineering 2-3 2.1. 7 ^
Manager, Chemical and Ceramic Development 2-3 2.1.8-Manager, Process Support Engineering 2-4 2.1.9 Manager, Equipment and Maintenance Engineering 2-4 i.
a 2.1.10 Manager, Materials Research 2-5 2.1.11 Manager, Plant Maintenance 2-5 2.1.12 Manager, Safety and Security Operations 2-6 l
2.1.13 Supervisor, Radiological and Industrial Safety 2-6 p
2.1.14 Health Phystes Technicians 2-7 j
AMEP.DMENT APPUCATION DATE:
PAGE NO.:
g jjj AhF 3830.051 A (546) i l
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4 1
ADuMCEDNUCLEARMEEACORPORATION
- ANF-3 SPECIAL NUCLEAR MATERIAL LICENSE.NO. SNM-1227, NRC DOCKET NO. 70-1257 TABLE OF CONTENTS REv.
'l 13 Page CHAPTER 2 =- ORGANIZATION AND ADMINISTRATION (Cont.d) 2.1.15 Plant Criticality Safety Engineer 2-8 2.l.16-Monoger, Fuel Development and Testing 2-9 2.1.17 Manager, Operation's Planning and Scheduling 2-9 1
'2.1.18 Manager, Corporate Licensing 2-9-'
2.1.19 Health Physics Component 2-10 2.1.20 Criticality Safety Component 2-10 2.'2 Personnel Education and Experience Requirements 2-11 2.2.1 Radiological and Industrial Safety Supervisor 2-12 2.2.2 Health Physics Technician 2-12 2.2.3 Plant Criticality Safety Engineer 2-12 I
~2.2.4 Mionager, Corporate Licensing 2-12 2.2.5 Health Physics Specialist 2-12 2.2.6 Criticality. Safety Specialist 2-12 2.3 Safety Review Committees 2-13 2.3.1 Health and Safety Council 2-13 2.3.2 ALARA Committee 2-14 2.4
. Training 2-14 12.4.1 initial Training 2-15 2.4. 2.
Followup Training 2-15 2.4.3 Health Physics Technician Training 2-i5 2.4.4 Training Evaluations 2-15 2.5 Operating Procedures, Standards and Guides 2-16 2.6 Internal Audits and Inspections 2-16 2.6.1 Radiation Protection 2-16 2.6.2 Criticality Safety.
2-17 2.6.3 Hazardous Chemical Safety 2-17 2.6.4 Fire Protection 2-18 2.6.5 Environmental Protection Inspections 2-18 2.7 investigations and Reporting of Reportable incidents 2-18 2.8 Records 2-20 l
CHAPTER 3 - RADIATION PROTECTION 3-1 L
3.1 Special Administrative Requirements 3-1 l-3.1.1 ALARA Policy 3-1 3.1.2 Radiation Work Procedures 3-1 D
3.2 Technical Requirements 3-2 3.2.1 Controlled Areas 3-2 3.2.2 Ventilation 3-3 3.2.3 Work Area Air Sampling 3-4
(-
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l AMENDMENT ' APPLICATION DATE:
P AGE NO.:
L July 1987 iv XN-NF F01422 (6/87)
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END.
y (ja p SPECIAL NUCLEAR MATERIAL UCENSE NO SNM 1227, NRC DOCKET NO. 701267.-
_ ~ANF.2
}j TABLE OF' CONT [NTS.
u v.
20 EMR CHAPTER 9'- GENERAL INFORMATION (Cont,d) 9.4-
. Site Description.
9-4 9.5 Location--of Buildings On-Site
' 9-5 9.6-Maps and Plot Plans 95 9.7 License History 9-5
APPENDIX A - 12 CHAPTER 10 - FACILITY _ DESCRIPTION
' 10-1 10.1.
Plant-Layout 10-1 10.1.1
-SF Building Description 10-1 10.1.2
.U0 Building Description 10-3 2
10.1.3 ELO Building
Description:
10-6 10.1.4
-Contaminated clothing Laundry 10-6 10.1.5 Fuels Storage Warehouse 10-7 10.1.6 Radioactive Material Warehouse 10-7 10.1.7
. Fuel Cooling Test Facility (FCTF) 10-7 7]7-(
10.1.8 UF Receiving and Storage Facil.ity 10-8
~ 10. 2.
Ut lities and Support Systems 10-8
- 10.2.1 Electrical - Power
~
10-9 10.2.2-Compressed Air System 10-12 10.2.3 Water 10-13 10.2.4 Sewer' System 10-14 10.2.5 Gas and. Chemical; Storage 14 4
10.2.6 Communications and Annunciations 10-15 10.2.7 Breathing Air 10-16 10.3 Heating, Ventilation and Air Conditioning (HVAC)
' 10-16 10.3.1 Cr teria-10-16 10.3.2' SF Building HVAC Systems 10 ~10.3.3 U0 Building (North) HVAC Systems 10-22 10.3.4 U0 Building (South Addition) HVAC Systems 10-26 1
10.3.5~
.U0 Building Line 2 Conversion HVAC Systems 10-29 l
10.3.6-U3 8 Facility HVAC Systems 10-31' 10.3.7 EL _ Building HVAC Systems 10-33 10.3.8 -
ELO Addition HVAC Systems 10-35 10.3.9
_ Contaminated Clothing Laundry HVAC System 10-37 10.4-Radioactive Waste Handling 10-38 10.4.1 Lagoon System Description 10-38 10.4.2 Ammonia Recovery Description 10-40 10.4.3 Lagoon Uranium Recovery (LUR) Facility Description 10-42 10.4.4 Solids Uranium Recovery Facility 43 10.4.5 Solid Waste Uranium Recovery Facility Description 10-44 10.4.6 Plutonium-Contaminated Waste Storage 10-47 l
AMENDMENT APPUCATION DATE' PAGE NO.:
yjj ANF-3830.061A 15/88)
J. Y.
7-t MMNNRARMM& CORPORATION gnp,,
. SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET No. 701257 -
nev.
TABLE OF CONTENTS 17
~
EL92 CHAPTER 10 - FACILITY DESCRIPTION (Cont.d)
'10.5 Fire Protection
- 10-47 10.5.1-Building Codes and Standards
.10 47 10~5.2 Fire Protection Liability Inspections 10-48 10.5.3 Fire Protection Program 10-48 APPENDIX A 10-85 CHAPTER 11 - ORGANIZATION.AND PERSONNEL 11-1 11.1 Organizational Resionsibilities 11 1 i
11-.2 Functions of Key Personnel 11-1 11.3 Education and Experience of Key Personnel 11-1 11.3.1 President and Chief Executive Officer -
4 R. B. Stephenson 11-2 1
11.3.2 Vice President, Engineering and Production -
R. W. McCullugh 11-4 11.3.3 Manager, Operations-Richland - R. G. Frain 11-6 I' 1 11.3.4 Manager, Plant Operations - T. W. Patten 11-7 I
11.3.5 Manager, Safety and Security Operations -
R. H. Purcell 11-9 i
11.3.6 Manager, Plant Maintenance
.J. L. Glesener 11-10 11.3.7-Supervisor, Radiological and Industrial Safety -
T. C. Probasco 11-12 11.3.8 Industrial Hygienist and Plant Criticality i
Engineer - S. R. Lockhaven 11-13 i
11.3.9 Health Physics Technician - D. L. Belt 11-14 l
11.3.10 Health Physics Technician - J. D. Cudmore 11-16 i
11.3.11 Radiological Safety Specialist - E. L. Foster 11-18 11.3.12 Health Physics Technician - D. A. Marlin 11-20 11.3.13 Health Physics Technician - J. Rosscup 11-22 l
ll 3.13a Health Physics Technician - L. G. Bradley ll-22a l
l' 11.3.14 Health Physics. Technician - W. W. Smith 11-23 11.3.15 Health Physics Technician - G. A. York 11-24 11.3.16 Manager, Materials and Scheduling -
l
- 1. J. Samaritano 11-25 l
11.3.17 Manager, Operations Planning and Scheduling -
D. C. Lehfeldt 11-27 11.3.18 Manager, Process and Equipment Engineering -
H. L. Caudill 11-28 11.3.19 Manager, Process Support Engineering - R. B. McLees 11-30' 11.3.20 Manager, Equipment and Maintenance Engineering -
J. H. Fastabend 11-31 9
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-SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257
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V PART I - LICENSE CONDITIONS
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'l.6.2.3 Enrichment Blendino Some of-these materials may be used to adjust the enrichments of uranium less than or equal-to 5 wt% U-235.
The rules on segregation of
. materials by enrichment obviously cannot apply to the blending operation; however, the blending operation will be subject' to a criticality safety analysis.and a Criticality Safety Specification.
Isotopic analysis shall be performed on each batch of blended material to assure that it is less than or equal to 5 wt% U-235.
The l
blended material shall be handled as for the highest enrichment input to L
the blend until an isotopic analysis is obtained.
1.6.3 Plutonium Storaae Advanced Nuclear Fuels is presently in possession of plutonium, as Pu02 and Pu0 2
' waste stored 2-UO.
This material is in the form of contaminated solid in drums.
These containers shall be stored in the SF Building, Room 162
^
autoclave pit in accordance with the following controls:
J 1.
These stored containers shall be sealed with gaskets.
2.
The SF Building storage pit shall be exhausted by the building l
HVAC system.
Two stages of HEPA filtration are provided prior to exiting the exhaust stack.
3.
The air exiting the SF Building storage pit shall be l
continuously monitored and sampled, and the samples ' analyzed' weekly for radioactive material content.
Assurance of containment shall be verified at least once every six months by visual inspection and smear survey of the stored waste drums.
The inspection and surveys will be documented.
All indications of drum leakage will be. investigated and appropriate action taken.
4.
In order to provide continued containment, Advanced Nuclear Fuels may find it necessary to repackage the containers.
These activities shall be performed using a special RWP.
5.
All alpha discovered by smear surveys or air sampling within the pit area shall be considered as plutonium alpha unless l
proven otherwise.
mo AMENDMENT APPUCATION DATE:
dung },
1989 PAGE No :
1-5 ANF 3630.051 A (5,88)
ADVANCEDNUCLEARFUELS CORPORATION ANF-s -
SPECIAL NUCLEAR MATERIAL LICENSE 'NO. SNM-1227, NRC DOCKET NO. 75-125h j
REV.
PART I - LICENSE CONDITIONS 15 1.6.4 Postino Exemotion All areas in which radioactive materials are stored, handled or used shall be posted with signs meeting the requirements of Title 10, CFR Part 20.203, except that of 20,203(f).
In lieu of 20.203(f) requirements, a sign bearing the legend, "Every container or vessel in this area, unless otherwise identified, may contain radioactive material," may be posted at entrances to each building in which radioactive materials are used, stored or handled.
1.6.5 -Waste Discosal Pursuant to 10 CFR 20.302, disposal of solid waste material con-taining 30.pCi/ gram or less to other than a licensed waste disposal facility is authorized. The low enriched uranium shall not exceed 30 pCi/ gram of dry solid waste material.
The uranium shall be essentially uniformly distributed throughout the waste material.
1.6.6' Soecial Nuclear Material Safeauards Specific safeguards requirements for special nuclear material are given in Safeguards Amendment SG-2 issued pursuant to 10 CFR Parts 70, I
'73, 74 and 75.
Those conditions are not affected by this licensing action.
l l
1.6.6.1 Physical Security i
Advanced - Nuclear Fuels shall follow the special safeguards con-l-
ditions given in the Safeguards Amendment SG-2 and the NRC approved I
security plan submitted in accordance with the provisions of 10'CFR Part 73.67(c)(1). The NRC approved security plan is:
L 1.
XN-NF-538,
" Physical Protection Plan for Material of Low i~
Strategic Significance."
This document shall be maintained in l
a current and approved status and shall be properly imple-i mented.
1.6.6.2 Material Control and Accountina t-L Advanced Nuclear Fuels shall follow the special safeguards con-ditions given in the Safeguards Amendment SG-2 and the NRC approved Fundamental Nuclear Material Control Plan (FNMC) submitted in accordance with 10 CFR Part 74.31(b). The NRC approved FNMC Plan is:
AMENDMENT APPLICATION DATE:
February 22, 1988 l-6 XN-NF-F01-822 (6/87)
i
',' ADM6MlllEDMJCLEARPERLSCCRPORATION gnp.y
,% ' SPECIAL NUCLEAR MATERIAL LICENSE NO.'SNM 1227, NRC DOCKET NO.-701257 A
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V-PART I ' LICENSE CONDITIONS nev.
20 1.
ANF-12, " Nuclear' Material Safeguards Procedures Description for the Fuels Fabrication Plant," (Revision 18).
This document i
shall. be maintained in a current and approved status and shall
- be properly. implemented.
1.6.7 Authorization at Reactor Sites.
__ Advanced Nuclear Fuels is authorized to possess fuel assemblies or fuel rods at reactor sites for the purpose of loading them.into shipping containers and delivering them to a carrier for transport.
1.6.8 ~ Authorized Release Guidelines
~ Advanced Nuclear Fuels is authorized to release equipment, scrap or facilities for unrestricted use, or for termination of license according to the " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material" as published by the - U.S. Nuclear Regulatory Commission dated August 1987.
A copy of these guidelines is contained in Appendix'A to Chapter 3.
_ /].
=,
V 1.6.9 Authorized Criticality Alarm System Outaae Advanced Nuclear Fuels is granted an exemption from 10 CFR 70.24(a) for the - purpose. of performing maintenance on-the, criticality al arm i
system.
Sections of the criticality alarm system may be taken out-of-service provided that all movement or processing of fissile material in affected areas is halted for the duration of the outage.
Health Physics Technicians will conduct periodic surveys of the areas during the criticality alarm system outage.
.1 O
AMENDMENT APPuCAYlON DATE:
June 1, 1989 PAGE NO.:
1-/
ANF.3830.051 A (Seet a - --
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ADM4NCED ARJCLEAR FtMLS CORPORATION t
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__. PART I - LICENSE CONDITIONS ngy*
Table I-l.l. Specific Locations of Authorized Activities.
13 Location -
SNM Authorized Activity i
SF: Bldg.
Pu & PuO -UO2 Storage and repackaging._
2
~'
contaminated waste UO2 (up to 19.99 Storage, blending, pressing,'
t wt% U-235) sintering, fuel rod loading and downloading, fuel rod' welding, f uel element assembly; process tests; associated quality control activi-t les.
Uranium Compounds' Waste storage, sorting, incinera--
(up to 5 wt%
tion, packaging and associated U-235) quality control activities.
UO2 Bldg.
Uranium Compounds All operational steps of fuel (including -
(up to 5 wt%
manufacturing from.UF -UO2 6
Powder Storage)
U-235) conversion to packaging finished fuel elements, scrap recycling and reprocessing; process-tests; associ-ated. quality control activities, y
UO.(5 to 19.99 All operational steps of fuel 2
wt% U-235) manuf acturing involving UO 3 2
including associated quality control activities.
ELO Bldg.
Uranium Compound All operational' steps of fuel-(up to 19.99 wt%
manufacturing involving uranium j
U-235) compounds; including process tests.
FCTF Bldg.
UO2 (up to 5 Hydraulic flow tests involving.
wt% U-235) single fuel elements.
Packaged Radio-Uranium Compounds Storage of closed, and externally -
active Materials (up to 5 wt%
free of significant contamintion Storage Bldg.
U-235) containers of product, scrap and waste materials.
1 AMENDMENT APPLICATION DATE:
PAGE NO.:
July 1987 l-8 XN-NF F01-822 (6/87)
'AYHUMDMCLEARPLELSCORPORATIONI
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^ SPECIAL NUCLEAR MATERIAL UCENSE NO. SNM 1227, NRC DOCKET NO. 701257 r
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PART'II - SAFETY DEMONSTRATION REV.
20 10.4.5.4 Ash Handlina f
Ash-formed from the combustion of wastes is pushed along the hearth lbyiincoming feed and by an internal ash plow.
The ash is pushed through an ash gate into an ash pit located at the end of the hearth.
The ash is cooled in an isolation chamber that discharges periodically into a drum.
The drummed ash is transported to an ash screening and milling area
'where oversize and/or metallic klinkers are separated.
The oversize material-is milled and combined with the ash in the drum.
The drum is assayed for uranium content and stored and/or transported to-the U0 -2 Building ash dissolution-packaging area.
Drums of ash, low in uranium-
-content, are not leached.
c
-10.4.5.5 Incinerator Ash leachina Combustion ash' is leached with a
sodium carbonate-sodium,
-bicarbonate-sodium hypochlorite solution at elevated temperature in an agitated vessel' that is operated on a batch basis for criticality control.
V)
- (
The leaching solution and solids are separated by a rotary drum-filter.
Following separation, the solids are mixed with drying and solidifying agents and loaded into containers for disposal. The leaching' solution is treated with an acid at an elevated temperature and air-sparged-to destroy' carbonates.
After destruction of the carbonates, the solution is routed _ to the miscellaneous uranium recovery system for precipitation and recovery of the uranium.-
10.4.6 Plutonium-Contaminated Waste Storace A waste storage facility is provided for storing plutonium-contaminated waste which remains from a previous mixed oxide fuel fabrications facility.
The plutonium concentration in the contaminated waste is greater than allowed for Class C waste and therefore, no disposal site exists which is licensed to receive this waste.
The facility is described below and depicted in Figure 11-10.33.
The storage facility is located in Room 162 of the SF Building.
The facility is a
below-grade room (approximately 12'x20'x20' deep) constructed of reinforced concrete and covered by steel floor grating
, overlaid with steel pl ate.
The room contains a sump for liquid collection which is monitored by a liquid level alarm.
A sump pump is installed which can be manually activated and which discharges to a p
waste retention tank south of the U02 Building.
O auenousar amcation oare.
June 1, 1989 10-47 ANP 3830.05t A (5/88)
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SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 9
PART II~- SAFETY DEMONSTRATION u v.
20 Drum ' storage will-be on steel grating to support the drums off the concrete floor and on a mezzanine also fabricated of steel grating.
Ingress and ' egress for personnel and equipment is from the top of the room..
The room is ventilated.
Air is drawn down from the roof and exhausted near floor level through one stage of HEPA filtration into the-
-SF Building exhaust system.
The exhaust air is continuously sampled and monitored prior to the installed HEPA filter.
The air sample is also analyzed weekly.
E 10.5 Fire Protection 10.5.1 Buildina Codes and Standards
~
All permanent buildings at the fuel fabrication plant were constructed in accordance with the applicable sections of the following building codes and standards.
Uniform Building Code (Seismic Zone II)
Uniform Plumbing Code Uniform Mechanical Code Uniform Fire Code National Fire Codes (NFPA)
National Electrical Code ANSI-Cl ASHRAE Standards Washington Administrative Code, Chapter 296-24 Washington Administrative Code, Chapter 296-44 Richland Municipal Code and Zoning Regulations Richland Municipal Ordinances Number:
3777 (adopt. Building Code) 3877 (adopt. Plumbing. Code) 3977 (adopt. Mechanical Code) 10,5 ~. 2 Fire Protection Liability Inspections Advanced Nuclear Fuels has elected to self-insure with regard to property damage.
Exxon Corporate Headquarters scheduled a
fire protection audit of its' affiliate subsidiaries approximately every three years by an acknowledged fire protection consultant.
The City of Richland's Department of Fire and Emergency Services conducts annual fire protection inspections of Advanced Nuclear Fuels' fuel fabrication plant facilities, auenoueuraneucaronoare' June 1, 1989 10-48 ANF 3830 061 A ($/86)
~.
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~ ANF2 f, N.
SPECIAL NUCLEAR MATERIAL LICENSE NO, SNM 1227, NRC DOCKET NO. 701257 4
- Qf.
PART II - SAFETY DEMONSTRATION REV.
20 The most 'recent copies of these audits and inspections, along with Advanced. Nuclear Fuels' reply, are appended (see Appendix A).
.10.5.3 Fire Protection Proaram 10.5.3.1-Combustible Solid Waste Handlina and Storaae 1
Outside metal waste containers. are provided by the City of Richland
_ for clean wastes.
Contaminated - combustible wastes-are properly sorted into metal boxes -or drums, sealed and stored on an outside pad for future uranium recovery 'or disposal per approved procedures.
Additional contaminated combustible wastes are stored in a fire-resistant metal-building near the waste barrel / box storage pad.
Combustible wastes generated inside the process and other buildings (either clean or contaminated) are collected in metal waste containers and emptied daily into the appropriate waste storage containers.
10.5.3.2 Flammable Liauid Storaae l
7._4 1
1 V
Flammable liquids are stored in approved safety containers or cabinets near the final use location.
Additional storage for flammable liquids is provided for in a fire-resistant metal warehouse located away from any radioactive material storage area, i
10.5.3.3 [ombustible Liauid Storaae
- Combustible liquids are stored in approved metal containers near the final use location.
Additional storage for combustible liquids is provided for on an outside storage pad.
10.5.3.4 Fire Prevention
-The manifolds for supplying combustible gases to the facility, including backup hydrogen for the sintering furnaces, are located outside the main building structure.
All combustible gas distribution piping meets applicable NFPA codes.
Combustible gas burn-off devices and combustible gas detection equipment are used where necessary to prevent explosion and fires around sintering furnaces and ovens.
auanousav anucaron omre.
June 1, 1989 10-49 ANF 3810.05 t A (5/66)
y MMRN;LEARMMSCORPORATION gn 7.,
' SPECIAL~ NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 I
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q PART II - SAFETY DEMONSTRATION M V-I 20 J
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TheEHEPA exhaust filters in the U02 and SF Buildings are protected l'
from high temperatures and burning debris in the event of fire by automatic deluge systems in the exhaust plenums immediately upstream of the final filter bank.
10.5.3.5 <. Fire Detection and Alarm f~
Rate-of-rise / fixed temperature heat detectors are used in the L
facility to detect fires.
This fire alarm equipment _is installed to.
l; provide automatic, as well as manual, alarm signals in event of a fire.
l The - system includes an annunciator in the Central Guard Station which indicates which zone in the system has actuated (see Figure 11-10.32).
A signal is also automatically transmitted to.the Richland Fire Department, i
The fire alarm is a multiple-strike gong (two strokes per second).
The l
fire alarm-system is inspected and tested in accordance with the applicable preventive maintenance procedures.
10.5.3.6 Fire Defenses The Advanced Nuclear Fuels' Facility is lo'cated within the city limits of Richland, and thus is served by the Richland Fire Department.
The Washington Surveying and Rating Bureau has graded the City as Class 3
.in.its last survey.
The (.losest Richland fire station is located at the intersection of McMurray and Jadwin, about five road miles from th'e l
plant.
l The Fire Department estimates running time to the plant to be about
.six minutes. - The. City has Mutual Assistance Agreements with surrounding communities, counties, and the DOE '(which has a fire station at the Hanford 300 Area located two miles nortneast of the plant site).
The DOE L
fire-fighting staff is well trained in nuclear fire safety precautions and has available equipment for radioactive _ fire fighting.
The Richland Fire Department receives annual training in radiological safety precautions from' Advanced Nuclear Fuels personnel, The plant site is fed water from the North Richland water grid through 10-inch diameter water pipes. which enter the plant site from the north and south.
The plant loop to the hydrants is an 8-inch diameter pipe.
There are 11 fire hydrant; on plant site (see Figure 11-10.18).
There are Multipurpose ABC, Halon, Met-L-x, CO, BC Dry Chemical, 2
Purple-K Dry Chemical, and AFFF fire extinguishers provided throughout the facility at selected locations.
These fire extinguishers are inspected and tested in accordance with the applicable preventive maintenance procedure.
AW 3630 051 A (54ai i
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- hANJCLEARMELSCON ANF.2 7 x-SPECIAL NUCLEAR MATERIAL UCENSE NO SNM 1227, NRC DOCKET NO. 701257 i
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PART II
. SAFETY DEMONSTRATION REY.
20 The: Advanced Nuclear Fuels Plant Emergency Response Teams receive annual training in first aid (or incipient) fire-fighting techniques.
The Richland. Fire Department. has the main responsibility for fighting fires on the plant site.
10.5.3.7 Responsibilities The Manager, Safety, Security, and Licensing, has the responsibility for inspecting and testing the plant fire extinguishers.
The
- Manager, Plant Maintenance, has 'the responsibility for inspecting and testing the plant fire alarm system.
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June 1, 1989 10-50a ANF.3830 051 A (sis 6) 1 l
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