ML20023E141
| ML20023E141 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 03/09/1983 |
| From: | Jennifer Ford BABCOCK & WILCOX CO. |
| To: | Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 22135, NUDOCS 8306140674 | |
| Download: ML20023E141 (11) | |
Text
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Nuclear Power Generation Division
- ,p Babcock & Wilcox commerciai nucioar ru.I Plant a McDermott company P. O. Box 800 LyMhburg, Virginia 24505
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(804) 522-6000 March 9, 1983 g
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United States Nuclear Regulatory Commission cb
[fg ATTN: Mr. R. G. Page, Chief s
Uranium Fuel Licensing g
Division of Fuel Cycle & Material Safety
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Washington, D. C.
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u.s NUCLEARREGULA og
SUBJECT:
Reactor Inspection Systems V
c0 las MailSection h
References:
(1) SNM-1168, Docket 70-1201 4
(2) Amendment 83-1 ro Gentlemen:
The Babcock & Wilcox Company, Commercial Nuclear Fuel Plant requests amend-ment of SNM-1168. Approval of the amendment request would allow receipt of reactor inspection equipment for storage and maintenance purposes. The revised and added pages of our license are attached to this letter. to this letter contains Pages 1, 56, 57, 58, and 59 of Section IV of our license.
. to this letter contains Pages Index 2,102a,l102b,and 102c of Section V of our license.
Enclosed with this letter is a check for $1400 to cover the minor amendment fee.
If there are any u ions, please feel free to call me at (804) 522-5966.
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Sincerely, 6
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B BABC0CK & WILC0X COMPANY E
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C0ff1ERCIAL NUCLEAR FUEL PLANT
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AM-C. D. Balentine i-Dick Stricklin (SPIS)
Attachment jgg C306140674 830309 PDR ADOCK 07001201 C
BABOXX & WILCDX C&PA#, C0ffERCIAL NUGEAR REL PLAIT USNRC LICENSE SNft-llb8 DOCKET /O-1201 IV HEALTH PHYSICS - INDEX SECTim Page Part 1
1 Introduction 1
2 Policy 2
3 Regulations References & Operating Procedures 3
4 Responsibilities 6
5 Operational Evaluation 7
6 Radiation Safety Equipment 9
7 Radiation Surveys 11 8
Personnel Dosimetry & Exposure Control 15 9
Airborne Contamination & Effluent-Control 25 10 Liquid Effluent Control 26 11 Solid WasteDisposal 28 12 Respiratory Protection
'30 13 Anticontamination Program 33 14 Medical and First Aid Program 34 15 Personnel Training 37 16 Records and Reports 39 17 Caution Signs, Labels, Area Control 42 18 Emergency Response 46 19 By-Product Material & Scaled Sources 49 20 Environmental Surveillance j
52 21 Shipment and Receipt of SNil l
56 22 Reactor Inspection Systems Appendix 1 - Summary of Health Physics Criteria Appendix 2 - Emergency Procedure Appendix 3 - CNFP Layout and Location of Criticality Detectors Appendix 4 - Neutron Emitting Sealed Sources Appendix 5 - Special Considerations Appendix 6 - Ventilation System l
index DATE 3-9-83 REVISIQ1 NO.
1 PAGE 1
CURRENT REVISIm :
SUPERSEDES: PAGE Index 1 USNRC APPROVAL REFERENCE DATE 4-30-75 REVISIc; O
TAC 0C< & WILWX C&PA#, C@tERCIAL NUCLEAR REL PLAlT USNRC LICENSE SNft-llb8 DOCKET 70-]201 IV HEALTH PHYSICS SECIm 22.
REACTOR INSPECTION SYSTEMS Various types of inspection equipment used to perform inspectionsat customer sites shall be stored, maintained and monitored as described in this section.
22.1 Description of Activities A designated area of the Special Products and Inspection Service-Facilities (SPIS) shall'be utilized for storage and maintenance of reactor inspection equipment.
The SPIS facilities are located in Lynchburg, Va. on Odd Fellows Road approximately 10 miles from the Commercial Nuclear Fuel-Plant.
The SPIS facilities are large metal paneled structures. A site layout of the SPIS facilities is shown in Figure 1 of this chapter.
22.2 Radiological Safety Upon receipt of the reactor inspection equipment at the SPIS site, a Radiation Control Zone (RCZ) will be established and physically defined within Building B (shown in Figure 1). All storage and maintenance of the reactor inspection equipment shall be performed within the RCZ. The action levels used for radiological control within the RCZ are given in Table 1, Part 8.9,Section V.
All reactor inspection equipment shall be surveyed for external radiation and removable contamination as they are unloaded and placed in the RCZ.
DATE 3-9-83 REVISION NO.
PAGE 56 CURRENT REVISION:
SUPERSELES: PAGE USNRC APPROVAL REFERENCE DATE REVISICtl
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BMCDCK & WILGX COM/, CORERCIAL,1UCLEAR REL PLAfT USNRC LICENSE SNM-llb8 IXXLtT 70-]201 IV HEALTH PHYSICS SECTIQ4 22.2 All personnel entering the RCZ shall wear as a minimum protective lab coats and shoe covers.
All personnel handling contaminated equipment shall also wear protective gloves. Upon exiting the RCZ, all personnel shall be surveyed to assure they meet Unrestricted Area Release Limits given in Table 1 of Part 8.9,Section V.
During periods of long term storage, weekly surveys of the RCZ for external radiation and removable contamination shall be performed. When in long term storage, contaminated components /
equipment shall be contained in sealed, double-wrapped plastic.
During periods of maintenance on the contaminated equipment, the radiological surveys shall be performed at least daily and as necessary throughout the maintenance activity.. Contaminated wastes generated by these activities shall be transfered to the CNFP for subsequent disposal. The action levels used for radiological control are given in Table 1, Part 8.9,Section V.
When the RCZ is not to be used for storage as maintenance of contaminated equipment for extended periods of time, the RCZ will be surveyed for both external radiation and removable contamination.
When it has been confirmed via a documented survey that the RCZ meets the Unrestricted Area Release Limits in Table 1, Part 8.9,Section V, only then will the RCZ designation of this area be eliminated and any physical markings (e.g., rope and changeline 57 DATE 3-9-83 REVISION NO.
PAGE CURRENT REVISICf4:
SUPERSEDES: PAGE USNRC APPROVAL REFEREllCE EATE REV!SICfi
BABC0C< & WILWX C&PM/, CORERCIAL.'luClfAR FLEL PLAIT USNRC LICENSE SNtt-ll68 DOCKET 70-1201 SECTICN 22.2 tape) be removed.
All access doors to the RCZ area when not in use, shall be locked and alarmed. Access to the RCZ area will require notification of CNFP Facilities Control.
The radiological controls placed upon the handling and operation of the reactor inspection equipment at an inservice (after nuclear fuel loading) utility site shall be determined by the utility licensee receiving the inspection. These radiological controls shall be in accordance with the utility's NRC license and shall be implemented by the responsible utility personnel.
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58 EATE 3-9-83 REVISIQ1 NO.
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SUPERSEDES: PAGE USNRC APPROVAL REFeE1CE j
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i BABCDC< & i!ILWX CGPR#, C@lERCIAL NUCLEAR REL PIM USNRC LICENSE SNft-ll68 DOCKET 70-]201 SECTICN IV HEALTH PHYSICS
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CURRBir REVISICN:
SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REyISIg;
BABCOG( & illLQX C& pat /, CCRERCIAL NUCifAR REL PIM USNRC LICENSE SNM-ll68 DOCKET 70-1201 SECTICN V CONDITIONS Page Part 72 7.11 Laboratory operations 72 7.12 Development Operations 72 7.13 Shipping 73 7.14 Waste Storage 73 7.15 In-Process Storage 73 7.16 Transport 75 8.0 Technical Specifications - Radiation Safety 75 8.1 Effluents 79 8.2 Ventilation, Containment, and Airborne Activity Control 90 8.3 Instrumentation 91 8.4 Personnel Monitoring 95 8.5 Receiving Inspection 95 8.6 Non-Exempt Sealed Source Control 99 8.7 Sintering 100 8.8 Fire Protection 102 8.9 Reactor Inspection Systems 103 9.0 Packaging and Shipping DATE 3-9-83 I
I"d"* 2 REVISIO4 NO.
PAGE CURRENT REVISION:
SUPERSEDES: PAGE Index 2 USNRC APPROVAL REFERENCE DATE 4-30-75 p3yg3;g; O
B/ ECOG ( & WILCDX C&PA#, CCMEPLIAL.1UCEAR FLEL PIM USNRC LICENSE SNtt-ll68 DOCKER F1201 SECTION V CONDITIONS 8.9 Reactor Inspection Systems Storage and maintenance of reactor inspection equipment. The following specific conditions apply:
a.
The Radiation Control Zone (RCZ) will be physically l
defined (e.g., rope and changeline tape).
.i b.
All ' storage and maintenance of contaminated reactor inspection equipment shall be performed within the RCZ.
c.
The action levels used for radiological control within the RCZ are given in Table 1 of this part.
d.
Radiological Surveys shall be performed as contaminattd reactor inspection equipment is unloaded and placed in the RCZ.
e.
Personnel entering the RCZ shall wear protective clothing.
f.
Upon exiting the RCZ, personnel shall survey to assure they meet unrestricted area release limits given in Table 1 of this part.
g.
During periods of long term storage, weekly surveys of 4
the RCZ for external radiation and removaSle contamination shall be performed, except during CNFP plant shutdown of i
a week or longer.
h.
When in long term storage, contaminated components. equipment l
shall be contained in sealed, double-wrapped plastic.
1.
During periods of maintenance on the contaminated equipment, radiological surveys shall be performed at least daily.
DATE 3-9-83 REVISICN NO.
PAGE 102a CURRENT REVISION:
SUPERSEmS: PAGE USNRC APPROVAL REFERENCE DATE REVISICN
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BABCOG( & WILCDX C&PA#, GRERCIAL,'luCLEAR REL PLAlT USNRC LICENSE SNtt-ll68 DOCKET 70-]201 V CONDITIONS SECTIOJ 8.9 Reactor Inspection Systems j.
Ccutaminated wastes generated by these activities shall be transferred to the CNFP for subsequent disposal.
k.
All access doors to the RCZ area, when not in use, shall be locked and alarmed.
l.
Access to the RCZ area shall require notification of CNFP Facilities Control.
m.
Removal of the RCZ designation shall require a documented survey that the RCZ meets the Unrestricted Area Release Limits in Table 1 of this part.
102b DATE 3-9-83 REVISIG4 NO.
PAGE CURREffr REVISIO1:
SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISICfi
BABCOG( & WIL(DX CEPAW, C0fERCIAL NUCLEAR FEL PlM USNRC LICENSE SNM-31b8 DOCKET 70-]201 SECTIa4 V CONDITIONS 8,9 Reactor Inspection Systems TABLE 1 RADIATION CONTROL ZONE LIMITS itPHA BETA GAMMA Direct Reading Removable Total Removable Floors. Walls and 2
5000 DPM/100CM2 other surfaces 1000 OPM/50CM 100 DPM/100 CM2 12,500 DPM/50CM 2
2 Protective Clothing 1000 DMP/50CM2 2,500 DPM/50CM 2
Equipment Maintenance 1000 DMP/50CM2 100 DPH/100 CM2 50 MR/HR 9 l' 500,000 CPM /100 CM UNRESTRICTED AREA RELEASE LIMITS ALPHA BETA GAMMA Total Removable Total Removable Floors, Walls and 2
10 DPM/100 CH 2500 DPM/50 CH2 10006PM/100CM2 2
other surfaces 100 DPM/50 CM Skin, Hair, and 2
personal clothing 100 DPM/50 CM2 250 DPM/50 CH Equipment 100 DPM/50 CM2 10 DPM/100 CM2 2500 DPM/50 CM2 1000 DPM/100 CM2 DATE 3-9-83 REVISIQ4 NO.
PAGE 102c CURRENT REVISION:
SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISICU
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'" LICENSE ~ AMENDMENTS" Docket No. 7(j -/ 2. o /
]m William O. Miller, License Fee Management Branch, ADM
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MATERIALS LICENSE AMENDMENT CLASSIFICATION iif Y si. f Applicant:
b"O License No:
Su* -it be Fee Category:
t6 jv.t Application Dated:
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Received:
3/tr//)
?g Applicant's Classification:'
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L The above application for amendment has been reviewed by NMSS in
]@j accordance with S170.31 of part 170, and is classified as follows:
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Safety and Environmental Amendments to Licenses in Fee 4p;;j Categories 1A throuch 1H,'2A, 2B, 2C,'and 4A
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(a)
Major safety and environmental (b) i hinop safety and environmental (c)
Safety and environmental (Categories ID through 1G only)
(d)
Administrative-2 Justification for reclassification:
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3.
The application was filed (a) pursuant to written NRC request and the amendment is being issued for the convenience of the Commission, or (b)
Other (State reason):
r Signature !b Od Division of Fuel Cycle & Material Safety
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