ML20125D071
| ML20125D071 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 05/07/1985 |
| From: | Watters J BABCOCK & WILCOX CO. |
| To: | Page R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25232, NUDOCS 8506120238 | |
| Download: ML20125D071 (18) | |
Text
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occam B$bcock & Wilcox
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May 7, 1985 O
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United States Nuclear Regulatory Commission C
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Mr.
R. G.
Page, Chief q.-
g,33ncttAR R?g[0 Uranium Fuel Licensing Branch CC"'9.
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Division of Fuel Cycle & Material Safety g
Washington, D.C.
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References:
(1)
SNM-1168, Docket 70-1201 I};;;.: 7 (2)
Letter to R.
G. Page from J.
P. Watters, dated December 14, 1984 (FFRDS Submittal)
(3)
Letter to R. G. Page from J.
P. Watters, i:
- . : I dated 9-11-84 b
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- : 4' Gentlemen:
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n The Babcock & Wilcox Company, Commercial Nuclear Fuel j 'Y $ $,
Plant requests amendment of SNM-1168.
These changes are nec-F ij35N cessary to allow storage and maintenance of a Failed Fuel Rod a jj s > 9 3 \\
Detection System (FFRDS) that is used at reactor sites.
The i Di"/NsM FFRDS, after first use, will contain contamination quantities ~
of by-product material.
Note that the name of the FFRDS has has been changed to " ECHO-330" which was done solely for market-ing purposes.
As a result, the pages submitted on December 14, 1984 (Reference 2) have been revised to note this change in nomenclature.
The original ECHO-330 amendment submittal (Reference 2) was also revised to address the questions and concerns expressed by Mr. Sean Soong of your staff.
The ECHO-330 submittal is to be incorporated into the 9-11-84 Section V amendment request (Reference 3) and subsequent revisions thereto.
Attachment I gives a brief outline of those pages from the 12-14-84 submittal that were revised to address Mr. Soong's questions.
Attachment II contains the following revised pages for the ECHO-330 amendment all dated May 7, 1985:
Section IV, Index Page 1, Appendix 4, Pages 1-2,Section V, Index Page 2, and Pages 3 and 67 through 75.
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If there'are'any! questions, please feel free to call L- -
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' Sincerely,.
BABCOCK-&'WILCOX~ COMPANY f
COMMERCIAL NUCLEAR FUEL' PLANT J. P. Watters License & Control Administrator
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2 ATTACHMENT I, Revision Summary Page 67 Para. 10.1 - A statement was added concerning proper packaging and labelling of: the FFRDS to prevent -contamination spread.. Page 68-Para. 10.2.7 - Revised ' the paragraph to indicate that radiological survey documents will.be, retained for a minimum of 2 years or longer if required by NRC regulations. 'Page 70 Para. 10.2.13 - Revised record. retention of cali-bration records to indicate a minimum 2 year retention or longer if required by NRC regulations. Page 71- ' Para. 10.2.14 - Revised paragraph to indicate that -the Respiratory Protection Program will be con-ducted in accord with 10 CFR 20.103. Page.72 Para. 10.2.16'- Revised paragraph to more clearly ~ define our bioassay program for by-product material. Page 75 Table 2 - Revised unrestricted' area contamination s levels. O +
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BABC00( & WILWX C&P##, C&iERCIAL NUCLEAR REL PIM USNRC LICENSE SNM-ll68 DOCKET 70-1201 SECTIQ4 IV HEALTH PHYSICS 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 21 10 Liquid Effluent Control 22 11 Solid Waste Disposal 23 12 Respiratory Protection 26 13 Anticontamination Program 28 14 Medical and First Aid Program 28 15 Personnel Training 31 16 Records and Reports 34 17 Caution Signs, Labels, Area Control 36 18 Emergency Response 39 19 By-Product Material & Sealed Sources 42 20 Environmental Surveillance Appendix 1 - Neutron Emitting Sealed Sources Appendix 2 - Special Considerations Appendix 3 - New Employee Training Verification Appendix 4 - By-Product Contaminated Equipment Index DATE 5-07-85 REVISIO1 NO. 1 PAGE 1 CURREfft REVISIQ1: SUPERSEDES: PAGE Index 1 USNRC APPROVAL REFERE!1CE DATE 12-16-82 REVISIQ1 0
BABC0CK a WILC0X C0WA% C0ffERCIAL NUCLEAR FUEL PLAllT USNRC LICENSE SNfi-ll68 DOCKET 70-1201 SE Q 0N IV HEALTH PHYSICS APPENDIX 4, PAGE 1 A. By-Product Contaminated Equipment 1. General The CNFP may perform ' limited operations on equipment that con-tains by-product material in contamination quantities. Typically, this equipment is that used to perform on-site inspections at nuclear reactors. Section B of Appendix 4 specifically lists the types of equipment the CNFP will be working with. B. Types of Equipment 1. Failed Fuel Rod Detection System (ECH0-330) The Failed Fuel Rod Detection System is a computerized manipu-lator used to perform ultrasonic inspection of fuel assemblies to detect failed fuel rods. A schematic of the equipment is shown on Page 2 of Appendix 4. The equipment is sent to reactor sites where the insp'ections are performed and is returned to the CNFP for storage and maintenance during periods of inactivity. The ECH0-330 is subject to by-product contamination because of use at reactor sites. By-product materials are authorized as indi-cated in Part 3.10 of Section V. PAGF DATE 5-07-85 REVISION t10. O App. 4. Pace 1 CURREllT REVISION: SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISION
P BABC0CK a WILCOX C0 Walt CQ1TRCIAL NUCLEAR FUEL PLM USNRC LICENSE SNft-ll68 DOCKET 70-1201 ' IV HEALTH PHYSICS APPENDIX 4, PAGE 2 2 ELECTRONIC CONTROL MODULES-Failed Fu'el Rod Detection System (ECH0-33d) f, ( SHOWN IN USE AT REACTOR Hol!T = .,: b.....:;,g.2.,...;....,, D .g PCCL v v 4 Futt A!!IMBLT = } k UNC[Rfli[A CCTy ( f. ULTRA! CHIC PACBI =K./ I. WANIPUL ATOR # p,q .ag g_ - tAICH MICHAN!!M y ,.c, r, SUPPORT PLAT [ M LCTIR hollLE S ] N STORACE RACR DATE RWISION NO. PAGg,, m E 7 5-07-85 O CURRENT REVISION: SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISION
r BAB000( & WILIDX C0W#ff, QWERCIAL NUCLEAR FLEL PLM USNRC LICENSE SNM-ll68 DOCKER b1201 ONDITIONS - INDEX SECTim Page Part-38 7.11 Development Operations 38 7.12 Shipping 39 7.13 Waste Storage 39, 7.14 In-process Storage -40l 39 7.15 Transport 7.16 UF, Storage 41 8 Te6hnical Specifications - Radiation Safety 41 8.1 Fffluents to Unrestricted Areas 47 8.2 Ventilation, Containment, and Airborne Activity Control 52 8.3 Instrumentation 54 8.4 Personnel Monitoring & Contamination Control 58 8.5 Receiving Inspection 59 8.6 Non-Exempt Sealed Source Control 63 8.7 Fire Protection 65 9 Shipment and Receipt of Licensed Material 67 10 Failad Fuel Rod Detection Systen (ECll0-330) f Index DATE 5-07-85; REVISI m NO. 2 PAGE 2 CLRRENT REVISION: SUPERSEmS: PAGE Index 2 USNRC APPROVAL REFERENCE 8-2-84 I DATE REVISICH
r BABCOCK a WILCOX COWAWj C0f?ERCIAL NUCLEAR FIEL PLM USNRC LICENSE SNft-ll68 DOCKET 70-1201 V CONDITIONS 3.0 Nuclear and By-product Materials are authorized as follows: 235 3.1 25,000 kilograms of 0 contained in Special Nuclear Material 235 of a pellet or powder form and with a maximum U enrichment 235 of 4.05% U. Chemical form to be uranium oxide. 235 3.2 5,000 kilograms of 0 enriched as UF6 (max. 5.00% enrichment) for storage only. 3.3 20,000 kilograms of uranium as depleted our source material in powder or pellet form and composed of uranium oxides. 3.4 3,000,000 lbs. uranium as natural UF for storage only. 6 'T 3.5 Up.to 51 curies of encapsulated by-product material contained in one or more sealed sources. Atomic numbers 3 to 83 inclusive. 3.6 By-product material in contamination quantities on returned, unirradiated fuel components. 3.7 Up to 6.0 grams of encapsulated plutonium contained in one or more sealed sources. 3.8 Up to 3.0 milligrams' of californium-252 contained in one or more sealed sources. 235 3.9 Up to 100 grams 0 without limit on chemical, physical, or isotopic composition, for analytical purposes. 3.10 Up to 0.1 curies of By-product material as contamination on/within equipment, and/or as waste. i. 3 REVISION NO. 1 PAGE 3 DATE 5-07-85 CURRENT REVISION: SUPERSEDES: PAGE 3 USNRC APPROVAL REFERENCE 6-25-82 0 DATE REVISION
BABC0CK a WILC0X C0f1%% C0t1TRCIAL NUCifAR REL PLMff USNRC LICENSE SNti-ll68 DOCKET 70-1201 V CONDITIONS ? 10. Failed Fuel Rod Detection System 10.1 Description of Activities A Radiation Control Zone (RCZ) will be established for acti'iities with the ECH0-330 when it is out of the storage configuration. Typical activities _ performed on the ECHO-330 equipment in the RCZ include decontamination, repair, testing, and packaging. The ECH0-330 will be appropriately packaged and labeled to prevent j l contamination spread when in the storage configuration. I 10.2 Radiation Control Zone (RCZ) The following conditions apply to the establishment and maintenance d of the RCZ. 10.2.1 The RCZ will be physically defined (rope and/or changeline tape)attheCNFPplantsite. 10.2.2 All maintenance of contaminated ECH0-330 equipment f shall be per'fdrmed within the RCZ. 10.2.3 The action levels used for radiological control within the RCZ are given in Table 1 of this part. 10.2.4 Access to the RCZ area shall require notification and approval of Regulatory Control. DATE 5-07-85 REVISION No. PAGE O g CURRENT REVISION: SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISION
BABC0CK a WILC0X C0ffN#, C0fifRCIAL NUCLEAR REL Pl#lT USNRC LICENSE SNft-ll68 DOCKET 70-1201 SEGION i V CONDITIONS S 10. Failed Fuel Rod Detection System 10.2.5 Radiological surveys shall be performed as contaminated ECH0-330 equipment is unloaded prior to transport to the RCZ area. I 10.2.6 Contaminated equipment that exceeds the Radiation Control Zone limits in Table 1 shall be immediately decontaminated or transported to a facility that can receive such contamination. 10.2.7 Radiological surveys shall be documented and maintained by-Regulatory Control personnel for a minimum of 2 years or longer if required by Federal Regulations. 10.2.8 During periods of maintenance on the contaminated equip-ment, radiological surveys shall be performed at least daily and as necessary throughout the maintenance ~ activity. 10.2.9 During perio'ds o.f long term storage, weekly surveys of the contaminated equipment containers for external radi-ation and removable contamination shall be performed, except during CNFP plant shutdown of a week or longer, but not to exceed 3 weeks. DATE 5-07-85 REVISION NO. PAGE O 68 CURRENT REVISION: SUPERSEDES:. PAGE USNRC APPROVAL REFERENCE DATE-REVISION
m BABC0CK a VILC0X C0fFA% C0fERCIAL NUCTAR FUEL PLAllT USNRCl.ICENSESNM-ll68 DOCKET 70-1201 SEGION V CONDITIONS t 10. Failed Fuel Rod Detection System 10.2.10 Removal of RCZ designation (including physical markings like ropes and changelines) shall require a documented survey that the RCZ area meets the Unrestricted Area Release limits in Table 2 of this part. 10.2.11 All personnel entering the RCZ shall wear as a minimum pro-tective lab coats and shoe covers. All personnel handling contaminated equipment shall also wear protective gloves. Upon exiting the RCZ, personnel shall survey to assure they meet unrestricted area release limits given in Table 2 cf this part. 10.2.12 Radiation workers shall receive initial indoctrination training before they are allowed to work in the RCZ. Radi-ation workers shall receive annual retraining. The training as a minimum, shall include the following: - Radiatio'n ' Fundamentals - Biological Effects of Radiation - Federal Regulations and License Requirements PAGE DATE 5-07-85 REVISION NO. O 69 CURRENT REVISION: SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISION
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s BABC0CK & WILQX COWANY, CGtERCIAL NUClFA FUEL PLM USNRC LICE'4SE Stit-ll68 DOCKET 70-1201 i ' -V CONDITIONS S-10.1 Failed Fuel Rod Detection System
- 10.2.12
- Facility Operating Procedures? - Exposure Control - Contamination Control - Respiratory Prctection - Waste Management - Shipment, Receipt, and Storage of Radioactive Material - Facilities Emergency Procedure Annual' retraining covering the same items listed above ll will be conducted after initial indoctrination. sr 10.2.13 Instrumentation shall be calibrated semi-annually and n p:q following major maintenance. Calibration records p shall be maintained for a minimum of 2 years, or i longer if required by federal regulations. 10.2.14 Respirators, may be. used in unusual conditions where air-a borne conce'nt' rations of radioactive material may cause ~ personnel to receive exposures in excess of permissible levels. Typical unusual conditions may be certain maintenance operations, short-term operations, etc._ Pro- .cedures for maintenance of the respirators and training-of personnel using respirators shall be under the-cognizance of Regulatory Control. \\ IlaTE RMSM M. MGE 5-07 n ,g CURRENT-REVISION: SUPERSEDES: '.PAGE-USNRC APPROVAL REFERENCE REVISION DATE-
m BABC0CK a WILC0X C0f?A% G1TRCIAL NUCLEAR REL PLAllT USNRC LICENSE SNtt-ll68 DOCKET 70-1201 9 -V CONDITIONS e 10. Failed Fuel Rod Detection System 10.2.14 The Respiratory Protection Program shall be conducted in accord with 10 IFR 20.103. 10.2.15 Personnel and/or fixed air samplers shall be used to deter-mine exposure to airborne radioactivity during maintenance cperations. Health-Safety shall specify frequency of per-sonnel sampling based on operational experience and Health Physics judgement to keep exposures within 10 CFR 20.103(a) limits. Boundary air samples around the RCZ shall be used to determine compliance with 10 CFR 20.106(a). Fixed boundary and RCZ air samples shall be run daily during maintenance operations. HEPA filtered containment facili-ties such as disposable tents or enclosures, shall be used in accord with cood Health Physics practice as required by Regulat.ory Control to control airborne radioac-tivity. HEPA' filters shall ta changed when the differential pressure exceeds 4" of water. Differential pressure shall be recorded weekly when containment facilities are in use. DATE R M S M N0' E 5-07-85 n 71 CURRENT REVISION:- SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE. REVISION
BABC0CK a WILCOX C0fPANY, C0iERCIAL NUCLEAR REL PLMff USNRC LICENSE SNti-ll68 DOCKET 70-1201 SECTION V CONDITIONS 2 S 10. Failed Fuel Rod Detection System 10.2.16 Personnel worki.ng directly in the RCZ shall 'be included in the bioassay program of at least one in vivo measurement per year, if they work in an area which is designated as an airborne radioactivity area as defined in 10 CFR 20.203(d). Additional bioassays shall be performed when, in the Judgement of Health-Safety that conditions during work were such that significant internal exposure may have occurred. Such conditions include but are not limited to: 1. Nasal smear results indicating facial contamination in excess of 10,000 DPM. 2. An internal exposure in excess of 40 MPC. Hr. in any seven consecutive days. 3. Any 'accidenta.1 internal exposure, whether real or suspec'ted. Immediate followup bioassay (excreta) measurements shall be performed if any of the 3 conditions noted above exist. If the followup measurements confirm the presence of greater than 10% of the maximum permissible organ burden, the worker will be restricted from radiation work until the maximum permissible organ burden is under 10%. PAGE DATE 5-07-85 REVISION No. g 72 CURRENT REVISION: SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISION
BABC0CK a WILCOX CQ1%T(, CGif_RCIAL NUCLEAR FUEL PLM USNRCLICENSESNti-ll68 DOCKET 70-1201 S ON V CONDITIONS 10. Failed Fuel Rod Detection System 10.2.16 Prior to Health-Safety approval of an individual to work in the RCZ, the individual's occupational radiation exposure history (both internal and external) shall be reviewed. ~ 10.2.17 The radiological controls placed upon the handling and operation of the reactor inspection equipment at an inser-vice utility site (after nuclear fuel loading) shall be determined by the utility licensee receiving the inspection. These radiological controls shall be implemented by the responsible utility personnel. 10.2.18 The reactor inspection equipment contain only contamination quantities of by-product material and there-fore does not require special handling with regard to nuclear criticality safety. 10.2.19 Contaminated wa'stes that_ cannot be disposed of under the current condition's'in Section V will be transferred to a licensed facility for subsequent disposition. DATE-5-07-85 REVISION NO. PAGE O 73 CURRENT REVISION: SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISION
BABC0CK a WILCOX C0WA's C0fPERCIAL NUClfAR FUEL PLM USNRC LICENSE SNft-ll68 DOCKET 70-1201 V CONDITIONS t-TABLE 1: ' RADIATION CONTROL ZONE (RCZ) LIMITS
- Beta-Gamma Total (Fixed & Removable)
Item External Radiation Removable Contamination 2 1.. Pro'tective Clothing .5 mR/hr. at 1 cm 5,000 DPM/100 cm -2. Equipment. Maintenance 2 and Storage 50 mR/hr. at I ft. 500,000 cpm /100 cm
- 3. Floors, Walls, and 2
other Surfaces ~1.0 mR/hr. at 1.ft. 5,000 DPM/100 cm
- Alpha. contamination will be controlled as indicated in Part.8.4.5 of Section V.
Y DATE REVISION NO. PAGE 5-07-85 O 7, CURRENT REVISION: SUPERSEDES:~ PAGE USNRC APPROVAL REFERENCE DATE REVISION
BABC0CK a WILC0X C0WMi COMRCIAL NUCLEAR REL FtM USNRC LICENSE SNft-ll68 DOCKET 70-1201 = 'V CONDITIONS T TABLE 2: UNRESTRICTED AREA RELEASE LIMITS
- Beta-Gamm$
Item External Radiation Removable Contamination
- 1. Skin, Hair, and Personal Clothing Min. Detectable Level Min. Detectable Level 2
- 2. Equipment
'0.2 mR/hr. at 1 cm 1,000 DPM/100 cm
- 3. Floors, Walls, and 2
Other Surfaces 0.2 mR/hr. at 1 cm 1,000 DPM/100 cm
- Alpha contaminaticn will be con. trolled as indicated in Part 8.4.5 of Section V.
D-U/-bd 0 75 DATE REVISION NO, PAGE j CURRENT REVISION: '~ SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE REVISION
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