ML20212E727
| ML20212E727 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 02/04/1987 |
| From: | Watters J BABCOCK & WILCOX CO. |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 27867, NUDOCS 8703040447 | |
| Download: ML20212E727 (100) | |
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- Utility Power Generation Division AS babcock & WilCOX Commercial Nuclear Fuel Plant
.i-;b i *ahb a Mc rmott company P. o. Box 800 -
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Lynchburg, Virginia 24505 b
(804) 5224000
- pocyDED.
usMRc February 4, 1987
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United. States Nuclear Regulatory Commission
( U.S. NUCLEAR REGUIMCRY -f Attn:
Mr. W. T. Crow, Acting Chief N'NCN
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g Uranium Fuel Licensing Branch Hau satim p
q Division of Fuel Cycle and Material Safety Washington, D. C.
20555 M
References:
(1)
SNM-1168, Docket 70-1201 (2)
Letter from J. P. Watters to W. T. Crow, dated 2-10-86 (3)
Letter from N. Ketzlach to J. P. Watters, dated 5-16-86 (4)
Letter from J. P. Wal[ters c2o W. T.
Crow, dated 8-19-86 Ac p
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Gentlemen:
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Th The Babcock & Wilcox Company, Comm6rcia[ Nucl' ear Fuel Plant requests amendment of SNM-ll68 to accommodatetrecent organizational changes at the CNFP.
We have made prior subMttals (References 2 and
- 4) -to accommodate previous organizational andDperational changes that are still pending NRC approval.
Rather than complicate matters by amending amendment requests, we ask that the previous amendment requests (References 2 and 4) be withdrawn from NRC review and be replaced by the submittal included as Attachment II to this letter.
We hope that this will be satisfactory for your purposes and help you in reviewing our request.
There are some NRC concerns regarding the method used for assigning page date and revision numbers on our amendment requests.
We would like to establish the following policy concerning this problem.
Each page contains a date, revision level, and superceded revision information.
When a submittal for an amendment is made, the date and next revision level will be entered and the superceded revision information upgraded.
If more than one submittal is made during the amendment approval process, the submittal date will be updated but the revision level and superceded information will remain the same as indicated on the 1st submittal.
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United. States Nuclear Regulatory Commission Page 2' 1 February 4,.1987 revision levels will occur for each NRC approval amendment and the cmultiple submittals can be traced.by the date. Please let us know'if Lyou have-any suggestions or comments concerning this concept of license page-identification and status.
Also, we have' moved the "***" revision. indicators to the left hand side of each page..This should correct.the xeroxing problems that have. occurred in the past.
We hope this meets with your approval.
Attachment I to thisl letter gives detail on the specific items
. requested in this-amendment submittal.
Attachment II contains.the revised license pages (all dated 2-04-87) needed to' incorporate those items addressed in Attachment-I.
.The listed revised pages replace the existing approved pages of SNM-1168 as follows:
SECTION I - Pages 3, 5, 7, 9, Appendix A - Pages 3, 4, 5, 7, 8, 9,'and'10.
SECTION III - Pages:44, 110, 112, 115, 119, 120, 124, 129,.131, 190.
.SECTION IV - Pages 1, 3, 4, 5, 6,.7, 10, 11, 12, 14, 21, ;22, 23, 24, 25, 26, 27, 28, 29, 30, 31, 33, 34, 35, 36, 39, 40, 43, Appendix 1, Page 10.
SECTION V - Pages 3, 6,
7,.8, 11 through 16, 18 through 21, 23,
, 28, 31, 42, 43, 49 through 59,-67 through~75.
Enclosed is a check for $150 to cover the initial administrative licensing fee.
If there are any questions, please call me at (804) -522-6202.
Sincerely, BABCOCK & WILCOX COMPANY COMMERCIAL NUCLEAR FUEL PLANT 3 9. Come J. P. Watters License & Control Administrator JPW:cmr t
Attachments
1 ATTACHMENT I CNFP Organization-The. main portion'of this amendment request is to accommodate change's t
in the organizational alignment at the CNFP.
The presently approved organization is as follows in Chart 1.
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CHART 1 R. A. Alto NUCLEAR FUEL & SPECIALTY MANUFACTURING j
MANAGER i
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MATERIALS & FACILITIES FUEL SPECIALTY QUALITY.
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D. W. Reff EANUTACTURING MANUFACTURING ASSURANCE PA. OPERATIONS l
Manager L. T. Lee C. Al Moore
- MANAGER W. L. Coleman Manager Manager J. Ficor Manager d
.l CONTROL FACILITIES l PRODUCTION l l
CONTROL r
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ADl REGULATORY CO ROL J. T. Ford e
Manager 1
Licensine Health Physicist i
Nuclear Matis.
Control
__ Health-Safety Foreman Health-Safety Monitors f
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This chart is more detailed than that shown on Page 9 of Section I of 3
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SNM-ll68 but illustrates exactly where the Nuclear Materials Control,
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Health-Safety, and Licensing functions were positioned in 3
relationship to other CNFP plant groups.
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The new CNFP organization is structured as shown in Chart 2.
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In comparing Chart 1 to Chart 2 one can obviously determine that the i
names of some of the groups and their managers are different than before.
The important observations to note are that the basic Health-Safety and Licensing organization has the same structure as before and that there is a more appropriate distribution of responsibility than before.
Originally, the Materials & Facilities Manager (D. W.
Zeff) had responsibility for Facilities Control, Production Control, Regulatory Control, Nuclear Materials Control, Licensing, and Health-Safety.
Since that time, D. W.
Zeff, J. T. Ford, L. T. Lee and J.
Ficor have either retired or taken other positions within the company which created gaps in our organizational structure.
As a result, the responsibilities of the Materials and Facilities Manager and Regulatory Control Manager were split mostly between the Production and Materials Control Manager (Mr. B. W. Pugh) and the Quality and Safety Manager (Mr. W. T. Engelke) with the Facilities control responsibilities becoming a separate staff function with C. W. Speight as Manager.
In addition, we have installed Mr.
D. V. Ferree as the Manufacturing Manager and Mr. R. W. Penoza as Field Operations Manager.
Mr. J. T. Ford is now the Fuel Manufacturing Manager and reports to Mr. D. V. Ferree.
He no longer occupies a key role in a safety function, therefore his resume was deleted from Section I.
Resumes for Messrs. Engelke, Pugh and Ferree are included in Section I and replace those resumes for Messrs. J. T.
Ford, D. W.
Zeff, and L. T. Lee respectively.
As illustrated in Chart 2, the Health-Safety Section and Licensing Section reports directly to the Manager of Quality and Safety, Mr. W. T.
Engelke.
This structure consolidates the control (i.e.,
Quality and Health-Safety) functions and provides a broader resource base to assure adequate attention to personnel and public safety and compliance with regulations.
Mr. Engelke has held.a variety of management positions at the CNFP over the past 10 years and has bee'n a member and active participant of the CNFP Safety Review Board since 1977. He has shown a keen recognition of the importance of implementing and maintaining effective control programs to assure the health and safety of employees and the need for compliance with NRO requirements.
Functionally, the Manager of Quality and Safety has full authority to act in the, capacity of the currently licensed function of Re.gulatory Control Manager in the areas of Health-Safety, Nuclear Safety, and Licensing, including procedure approval ~
authority.
Additionally, Mr. Engelke will be the Safety Review Board Chairman which is appropriate due to his managerial role over the Health-Safety and Licensing functions.
.Mr. Engelke's. resume in Section I confirms the appropriateness of his selection as the Manager of Quality and Safety.
Other functional changes within the Health-Safety Section include the
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change from Health-Safety Foreman to Health-Safety Leader.
The Health-Safety Leader supervises the Health-Safety Monitors and acts l
as a backup or overcheck for the Health Physicist if necessary.
The j
minimum qualifications for the Health-Safety Leader have been upgraded to be equal to the Health Physicist if he is to be the backup to the Health Physicist.
Mr. G. B. Lindsey is the new Health-Safety Leader and his resume is included in Section I of SNM-ll68.
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His qualifications show that he meets the minimum qualifications of
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the Health Physicist.
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r Mr. K. E. Shy is still the CNFP Health Physicist as shown in Section I, Page 9.
Mr. Shy's resume (Section I, Appendix A, Pages 7 and 8) has been updated to reflect recent training and is included with this submittal.
The wording of Paragraph 5.3.1 (Section V, Page 8) was restructured to clarify exactly what are the minimum requirements for the Health Physicist.
Specifically these are:
1 - A Bachelor's Degree in Science or Engineering or equivalent 2 - Minimum of 5 years experience (Health Physics / Nuclear Safety) 3 - Formal training in the Health Physics / Nuclear Safety areas Note that the requirement for formal Health Physics training has been added and the work experience requirement has been upgraded from 3 years to 5 years.
Paragraph 5.3 was modified to indicate that the Health Physicist or his qualified designee shall be responsible to provide management with the assurance of the effectiveness of the safety program.
Originally, this read that the Health-Safety Section has the responsibility.
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END CAP REMOVAL STATION i
i The CNFP performed a downloading operation for the fuel assemblies originally scheduled to be delivered to one of our customers.
This operation involved disassembly of each fuel bundle, and removal of one end cap and unloading of the scrap pellets into standard.
i, containers under local ventilation control.'The entire operation except for the actual removal of pellets from rods is performed in an uncontrolled area.
Airborne contamination limits for this area are presently defined by the table on Page 42 of Section V of SNM-ll68.
This table utilizes contamination controls based on percentages of 10 CFR 20 Appendix B, Table 2 (Environmental MPC limits).
The table on Page 42 indicates an exception for the end weld area such that no action is required as long as the quarterly average of the air effluent samples stay under 50% of environmental MPC.
This exception was approved by letter from R. G. Page to D. W. Zeff dated 7-1-80.
Our application for this exception demonstrated that engineering efforts to keep the air effluent under 10% of
~
l environmental MPC at the end weld station was not achievable.
It was a1so demonstrated that. contamination levels seen at the end weld area did not exceed uncontrolled area limits.
)
l The CNFP faced the same situation at the end cap removal station ior the Midland download operation.
Air effluents for this operation have been on the order of 25% of environmental MPC.
We have exhausted all engineering efforts to keep the area under the 10% MPC criteria.
Based on our engineering efforts we have concluded that the most effective air-capture technique was selected for the end cap removal area.
We have performed extensive contamination surveys in the download area since this area has been in operation with the results distributed as shown in Tables 1 and 2 below.
TABLE 1 SMEAR SURVEY (REMOVABLE)( }
2 CNFP CLEAN AREA LIMIT 200 DPM/100 cm r
RANGE (DPM/100 cm )
- OF SURVEYS i
l 0 to 50 1108 51 to 100 164
~
101 -
200 59 (2)
> 200 1
TOTAL 1332
TABLE 2 (FIXED & REMOVABLE)(2)
TOTAL SURVEY (500 DPM/50 cm CNFP CLEAN AREA LIMIT RANGE (DPM/50 cm )
- OF SURVEYS 0 - 100 1207 i
200 51 r
300 31 1
400 41-500 0(3) 600 1 I4I 700 l
L TOTAL 1332 I
Data from 8-14-85 through 10-lg-85 Localizedarea'(281DPM/lg0cm) counted 45 DPM/100 cm after decon I } Localized area - counted 200 DPM/50 cm after decon j
(4) Localized area l' counted 400 DPM/50 cm after 2
decon Tables 1 and 2 clearly illustrate that there has not been a J
contamination problem in the download area.
Only 3 results out of 2664 yielded values that resulted in any decon activity and those instances were limited to the immediate work tables.
Floor contamination levels were all below clean area levels; therefore there is not a real potential for contamination spread.
We are therefore requesting that the end cap removal station be permitted-air effluent values of 50% of environmental MPC based on g-the engineering effo'rt and on the actual contamination levels seen in the download area.
This revises the table on Page 42 of Section V to allow this 50% limit for the end cap removal station as well as the previously approved end cap weld operation.
Other minor editorial i
revisions were also made to the table.
The footnotes previously 4
identified by 1 or 2 asterisks are now included directly in the i
table.
This was done for clarity and to make the table easier to read.
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a ECHO-330 The last major part of this amendment request is concerned with
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changes needed for the failed fuel rod detection system in addition
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-to the organizational. changes.
The.following,is a listing of the Lchanges_ proposed and the justification for the change.
Page 67, Section 10.2.4 f
Originally, Section.10.2.4 indicated that notification and approval J
was required prior to entry to the RCZ.
We are requesting that this be changed to "The identity of authorized personnel allowed access to gy the RCZ and information regarding activity as either maintenance or ll storage in the RCZ shall be communicated.in advance to Health-The intent is to control access to the RCZ. area su) as to f
. Saf e ty'r"e.ad contaminatidn to other plant areas and to prevent not.sp i
unauthorized personnel.from entering the RCZ.
Additionally, a statement was added that requires visitors to the RCZ be accompanied.
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iby authorized personnel.
Control of RCZ access in this fashion will-
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maintain the personnel.and plant safety required for the ECHO-330
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operations.
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Page 68, Section.10.2.5 l
4 f-This change is requested simply out of practicality and will in effect enhance the radiation.and contamination safety surrounding the ECHO-330 equipment.-
As written in the present license, we have to 3
1 perform receipt surveys before the equipment is taken to' the RCZ area p
which yields,a higher potential for contamination spread outside of the RCZ and to the environment because the equipment is exposed to the environment during the surveys.
If the surveys are performed j
after the ECHO-330 equipment.is placed in the RCZ and before'any s
handling or maintenance operations, any potential contamination or i
radiation hazard would therefore be limited to the RCZ area which is j-equipped to handle the potential Health-Safety concerns.
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Page 68, Section 10.2.6 s
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.This change-is requested out of practicality and enhances the Health-1 Safety program for the ECHO-330.
We requested that "or transported S
to a facility that can receive such contamination" be deleted because if the ECHO-330 equipment contamination exceeds the limits, there W.
would be a greater potential for contamination spread due to the 1
-increased handling from repackaging and transport to an authorized fr facility.
The CNFP has the capability to properly perform the F
decontamination of the equipment if necessary, therefore the transport option is not needed.
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Page 68, Section 10.2.8 This change is requested to provide a more realistic means to identify potential contamination spreads in the RCZ.
As'writte'n, i
Section 10.2.8 states that the surveys shall be performed daily on the contaminated equipment which will not identify a potential 4
contamination spread within the RCZ.. A survey of the RCZ area will>
however show if a contamination spread has occurred from the contaminated ECHO-330 equipment within the RCZ which will enhance the Health and' Safety of the personnel working within the RCZ.
Page 68, Section 10.2.9
.Section 10.2.9 was modified to indicate that the weekly surveys are performed on the RCZ rather than the contaminated equipment containers.
The same justification for Section 10.2.8 concerning surveys on the RCZ as opposed to su,rveys on the contaminated equipment applies to Section 10.2.9.
If the contain'ers are stored in the RCZ, they will be included in the weekly surveys.
Page 69, Section 10.2.12 l
This section was revised to reference the appropriate part of Section l
V of SNM-ll68 concerning employee training.
This change eliminates i
redundancy but does not degrade the effectiveness or content of the i
radiation work training or retraining.
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.Page 70, Section 10.2.13 n
As with Section 10.2.13, this section was revised to eliminate redundancy only.
.The instrumentation calibration program has not
,been degraded.
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Page 71, Section 10.2.15 i
J Changed " Boundary air samples around the RCZ" to " Gaseous effluents
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to unrestricted areas shall be controlled to the limits specified in 10 CFR 20" to clarify what effluents are being controlled.
l Also, the next sentence was revised to indicate that " air samples j
shall be collected daily when the facilities are in an operational status".
The change is requested for practicality purposes.
.If j
there are no operations in the RCZ, then there is not a real
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potential for gaseous effluents.
The storage contamination surveys as indicated in Section 10.2.9 would detect any contamination spread in the RCZ.
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. Clarified the" bioassay program in regard to work restrictions for high' bioassay measurements.
It'is appropriate only to restrict.the worker from a controlled area rather than from radiation work,in general.
Page 73, Section 10.2.17 This section was deleted because'it is inappropriate for the CNFP Health-Safety _ program.
It is known that each reactor site has its own radiological controls and is responsible for its proper implementation.. The CNFP cannot execute control over how the reactor sites execute their Health-Safety program.
Page 74 and 75, Item 1 (Both Pages)
-The removable contamination limits on these pages was clarified to indicate the method used to detsrmine-the removable contamination quantity. 2Also, Item 1 on Page 74 was revised to indicate that 2,200 DPM/100 cm is the limit for removable contamination'on protective clothing available for use.
The asterisks designations were changed to numbers for clarity on both pages.
Other Changes Pages 3 and 7.of Section I were updated to reflect changes in mailing _
addresses and to be consistent with prior amendments.
Page 5, Section-I and Page 3, Section V_were revised to increase the
- i ;
possession limit on by-product material from 1 curies to.5 curies.
This change is needed to accommodate the potential for expansion in our ECHO-330 operations.
This change gives us a degree of flexibility in the ECHO-330 operational limits and will not degrade our health-safety controls on the ECHO-330 operations.
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ATTACHMENT II (Revised Pages)
I
BABC00( & WIL(DX C&PANY, C0ftERCIAL NIX 1 EAR REL PIMF f
USNRC LICENSE SNft-1168 DOCKET A 3201 SECTICN I - GENERAL INFORMATION r
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The Commercial Nuclear Fuel Plant has been established for the purpose l
of fabyicating fuel assemblies for commercial utility reactor cores.
- 1) Name of Applicant-i Babcock & Wilcox Company Commercial Nuclear Fuel Plant l
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- 2) State of Incorporation f
Babcock & Wilcox is a segment of McDermott, Incorporated, b,
and is organized and exists under the laws of the State of Delaware.'
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- 3) Addresses of Principal Of'fices Babcock & Wilcox Op'erating Unit, McDermott Incorporated i.
1010 Common Street!
P. O. Box 60035 New Orleans, Louisiana 70160 Babcock & Wilcox Commercial Nuclear Fuel Plant P. O. Box 11646 Lynchburg, Virginia 24506-1646 e
1 tr 5
DATE 2-04 87 REVISION NO.
1 PAGE 3
CLERENT REVISION:
li-SUPERSENS: PAGE 3
USNRC APPROVAL REFERENCE 81 DATE REVISION
q R(
BABGXX & WILODX CGPANY, COMBCIAL NUCLEAR REL PIM q
USNRC LICENSE SNM-ll68 DOCAET E1201 I - GENERAL INFORMATION SECTICN i
Name f
Low (4.05%) enriched uranium oxide Uranium as low enriched UF6 Uranium as natural UF6 Depleted or natural uranium oxide By-product material SNM as Pu and Cf sealed sources Amount This application requests authorization for:
235 i
- 25,000 Kg 0 in powder or pellet form 235 5,000 Kg U as enriched UF r storage only l
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- 3,000,000 lbs. uranium as natural. UF for storage only 6
- 20,000 Kg depleted or natural uranium oxide as powder or pellets 235
- Up to 100 grams U in any form j
Specifications
- Up to 51 ci by-product riaterial as sealed sources
- By-product material in contamination quantities on returned, unirradiated fuel assemblies
- Up to 6' grams encapsulated plutonium
- Up to 3.0 mg Californium - 252 as sealed sources
- Up to 0.5 curies of by-product material as contamination 1
on equipment or as waste 10 CFR 70.22 (a)(6)
Technical qualifications, training, and experience are L'
shown in Appendix A of this section.
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(a)(7)
Description of equipmer.t and facil;;ies to protect j
health and ' property is provided in Section III and IV.
Procedures to provide for protection of health and property due to accidental criticality are provided 2-04-87 I
5 DATE REVISION NO.
PAGE CURRENT REVISION:
5 SUPERSEES: PAGE USNRC APPROVAL REFEREN 1-29-82 DATE REVISICN
f BAB000( & WIL(DX QNANY., QMOCIAL NUDIAR REL PIM USNRC LICENSE-SNPt-ll68 DOCKET 70-3201 q
7 I - GENERAL INFORMATION FIGURE 1 SECT!W
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LENRC APPROVAL REFERENCE I
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, *The Safety Review Board Chairman is the Manager of Quality and Safety.
x 33 The permanent membership of the Board shall consist of representatives l
of CNFP operational and technical m.anagement.
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BABQXX & WILCDX CDPM/, QMERCIAL MlX1 EAR REL PLAVT f
USNRC LICENSE SNM-ll68 DOCKET E-1201 SECTIO 4 I - GENERAL INFORMATION l
l NAME:
Bob W. Pugh TITLE:
Hanager, Production & Materials Control CITIZEN OF UNITED STATES EDUCATION:
1963 Phillips Business College - Data Processing EXPERIENCE:
1969-1970 Production Sponsor Jr., Babcock & Wilcox Company, Commercial Nuclear Fuel Plant, Lynchburg, i
Responsible for requisiting and monitoring Contract Materials.
1970-1975:
Production Sponsor, Babcock & Wilcox Company, Lynchburg, Virginia. Responsible for Materials j
Control Function.
1976-1983' Supervisor, Materials Control,I Babcock & Wilcox Company, Lynchburg, Virginia.
Resporisible for f:laterials Control, Stores, and Shipping and i
Receiving Functions.
l 1983-1985 Manager, Special Projects, Babcock & Wilcox Company, Lynchburg, Virginia. Responsible for
- all special project activities.-
1985-Present Manager, Production & Materials Control, Babcock &
Wilcox, Lynchburg, Virginia.
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Appendix A DATE Z-04-87 REVISIQ1 NO.
2 PAGE 3 4
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CURRENT REVISION:
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SUPERSEDES: PAGE Appendix A, Page 3 DATE 5-04-84 pyygsgg; 1
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BABGXX & WILCOX MPAW, CORERCIAL NUCLEAR REL PLAff l
USNRC LICENSE SNftll68 DOCKET 70-1201 I - GENERAL INFORMATION SECTIG4 NAME:
Donald '/. Ferree I,
TITLE:
Manager, Manufacturing i
CITIZEN OF UNITED STATES EDUCATION:
1967 Ohio State University - B.S. Physics 1972 University of Tennessee - M.S. Physics
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EXPERIENCE:
1967-1972 Associate Physicist, Union Carbide Corp.,
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Nuclear Division, Y-12 Plant.
Responsible for R&D in NDE methods of UT, RT, and other radiation techniques.
f 1972-1974 Senior Research Engineer, B&W, LRC.
Respon-sible for R&D in NDE methods of UT and ET.
1974-1979 NDE Manager, QC Manager, QA Manager, B&W, Mt. Vernon Works. Responsible for produc-i 1
tion NDE, dimensional inspection and all QA.
1979-1981 QC Manager, Pullman Std., Bessimer, Alabama, and Butler, Pennsylvania.
Responsible for
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all QC/QA in rail freight car plants.
1981-1982 Supervisory Engineer, B&W, NPD-SPIS.
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Responsible for NDE at nuclear sites.
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I 1982-1983 Nuclear QA Manager, B&W, UPGD.
Responsible I
for all nuclear QA for division.
I 1984-1985 Manager of Special Projects, B&W, CNFP.
Responsible for ASME Code QA Manuals and ECH0-330 development.
1985-Present Manager of Manufacturing, B&W, CNFP.
Responsible for all fuel and spe.cialty j) manufacturing and manufacturing engineer-ing at the CNFP.
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Professional Organization - ASME I
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nppenu 4 n DATE 2-04-87 REVISIQ1 NO, 2
PAGE 4 CURRENT REVISION:
q SUPERSEDES: PAGE Appendix A, Page 4 USNRC APPROVAL REFERENCE 1
5-04-84 p,gygg gg4 L
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BABGXX & WIL(DX C0FPAif(, CGTOCIAL NUCLEAR REL PLM USNRC LICENSE SNM-ll68 DOCKER bl201 y
SECTim I - GENERAL INFORMATION
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NAME:
Gerald B. Lindsey a
TITLE:
Health-Safety Leader CITIZEN OF THE IfNITED STATES EDUCATION:
1975 Graduate of Virginia Polytechnic Institute and State N
University, Blacksburg, Virginia - B.S. in Biology-CVCC Emergency Medical Technician,110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> (coordinated through Blue Ridge Emergency Medical Service)
EXPERIENCE:
1969-1976 Lynchburg General Hospital Emergency Room. Duties include vital signs, emergency aid, patient care.
m 1976-1983 Babcock & Wilcox Company, Commercial Nuclear Fuel Plant.
Employed as a QA lab technician - 5 years; Health-Safety Monitor - 2 years.
1983-1985 Babcock & Wilcox Company, Lynchburg Research Center. Employed'as a H.P. Surveyor for the Building C Decommissioning Project.
Oct. 1985-Babcock & Wilcox Company, Commercial Nuclear Fuel April 1986 Plant. Employed as a Senior Health-Safety Monitor.
April 1986 -
Present Babcock & Wilcox Company, Commercial Nuclear Fuel p'
Plant.
Employed as Health-Safety Leader.
Duties
. include standard review and ? implementation, safety training program, plant safety audits, procedure writing, accident investigations, a
l i
4 1
i i
Aooendix A DATE 2-04-87 RE" 910N NO.
2 PAGE 6'
l CURRENT REVISION:
SUPERSEDES: PAGE Appendix A, Page 5 USNRC APPROVAL REFERENCE
/
BAB000( & WIL(DX CTPANY, COMOCIAL NUCLEAR REL PLM USNRC LICENSE SNM-ll68 DOCKET k.1201 SECTIm I - GENERAL INFORMATION NAME:
Kenneth E. Shy TITLE:
Health' Physicist CITIZEN OF UNITED STATES EDUCATION:
High School - GED U.S. Navy Basic Hospital Corps School - U.S. Navy - 640 Hrs.
1 Advanced Hospital Corps School - U.S. Navy - 800 Hrs.
Field Medical School - U.S. Navy - 320 Hrs.
Operating Room Technician School - U.S. Navy - 960 Hrs.
Supervisory Development Program - 20 Hrs.
Basic Radiological Health - 60 Hrs.
Occupational Radiation Protection - 60 Hrs.
Supervisor Industrial Safety Training - 20 Hrs.
-Industrial Audiometric Testing & Hearing Protec-tion - 20 Hrs.
Industrial Safety Engineering (ICS)
Mathematical Calculations - Four (4) Credit Hrs.
Radioactiva Waste Packaging, Transportation & Disposal Seminar Internal Dose Assessment Seminar l
- Hazardous Radioactive Materials Transportation
?
Seminar Quality Improvement & Cost Reduction f
EXPERIENCE:
1949-1969 United States Navy.
Duties included record maintenance, patient care. ooera-ting room technician and five (5) years j
duty independent of a medical officer being i
responsible for the health and safety of j
approximately 300 men.
Retired in 1969 holding the rank of 1st Class Hospital
)
Corpsman.
O 1969-Present Bubcock & Wilcox Company, Commercial Nuclear Fuel Plant.
1969-1971 Perform routine repetitive Health-Safety a
tasks as directed.
Duties included first-aid care for 150 employces.
Appenuix A l
DATE 2-04 REVISION NO.
PAGE 7
2
?
i CURRENT REVISION:
SUPERSEDES: PAGE Appendix A, Page 7 US E M PR R E N 5-04-84
)
,DATE REVISION
BABQXX & WILCDX C0FPM/, C@tBCIAL NUCLEAR REL PLATT USNRC LICENSE SNft-ll68 DOCKET 70-1201 SECTIO 4 I
GENERAL INFORMATION
. EXPERIENCE:
1971-1973 Senior Health-Safety Technician.
Functional responsibility for maintenance of nuclear fuel fabrication plant health -
physics and industrial safety programs.
Duties include conduct of sampling programs, analytical measurements, exposure control administration, audiometric and visual screening, maintenance of plant fire protection apparatus and other plant safety equipment.
1973-1984' Health-Safety Foreman.
Responsible for maintenance of nuclear fuel fabrica-tion plant health physics and industrial safety programs.
Duties include standards review and! implementation, safety training programs, plant safety audits, procedure writing, accident investigations, and evaluation of analytical measurements of the plant environment.
1984-Present HealthPhykicistforB&WCNFP.
Responsible for coordinating the technical aspects of radiation control and environmental pro-te~ction, radioactive materials transporta-r tion and emergency planning.
i Appendia A DATE 2-04-87 REVISIO4 NO.
2 PAGE 8
CURREffT REVISION:
SUPERSEDES: PAGE Appendix A, Page 8 USNRC APPROVAL REFERENCE DATE 5-04-84 1
ggygggg;
B20XK & WILCDX C&PRU, C01ERCIAL NUCLEAR FLEL PLAH USNRC LICENSE SNtt-ll68 DOCKET 70-2201 SECTION I-GENERAL INFORMATION NAME:
Wilfred T. Engelke TITLE:
Manager, Quality and Safety CITIZEN OF UNITED STATES EDUCATION:
1959 University of Maryland - BSME EXPERIENCE:
1959-1960 Engineer, Reaction Motors Division, Denville, New Jersey, in design and test of solid and liquid rocket engines.
1960-1962 Engineer, Chrysler Missile Division, Huntsville, Alabama, involved in design and fabrication in heat transfer instrumentation for the saturn missile.
i 4
1962-1974 Research Engineer, Southern Research Institute, j
Birmingham, Alabama, performing heat transfer research and thermal characterization of materials.,
i Promoted to Head of Applied Thermal Section.
i 1974-1977 Engineering and Plant Manager, Tech Air Carporation, p
Atlanta, Georgia.
Involved in the development, i
design, installation, and operation of a pyrolysis l waste neutralization process, supervised operational crew in development work and around the clock opera-tion of the unit.
1977-1985 Manager, Manufacturing Engineering, Babcock & Wilcox, Lynchburg, Virginia, managed the Manufacturing Engineering Section.
Responsible for process engi.
neering, technical documentation issuance, qualifi-cation and development of manufacturing operations in the fabrication of nuclear fuel elements. Also managed Information Services Section, responsible for the computer data processing and information systems. Also served as a member of the Safety Review Board.
1985-
~
Present Manager, Quality and Safety, Babcock & !!ilcox, Lynchburg, Virginia. Manage Quality Assurance and Health and Safety Departments.
Responsible 1
for functions of inspection, data evaluation, radiation and industrial safety. Continued to serve as a member of the Safety Review Board.
w F
Appendix A l
DATE 2-04-87 REVISION NO. 2 PAGE 9 CURREffT REVISIQ1:
j.
SUPERSEDES: PAGE Appendix A, Page 9 USilRC APPROVAL REFEREi4CE j
5-04-84 1
DATE REVISIQi
B200CK & WIL(DX C0FPAN, CORERCIAL NUCLEAR REL PIM USNRC LICENSE SNM-ll68 DOCKET 70-]201 SECTIO 4 I - GENERAL INFORiiATION GENERAL:
Exp rience at B&W since 1977 has been in the management and direction of a variety'of manufacturing and quality processes, operations, and procedures. This has required a basic under-standing of nuclear criticality and radiation safety since the safety program at the CNFP impacts the entire plant operations. This has qualified him to manage the health safety organization at the CNFP which has within it a Health Physicist and a Health-Safety Leader that can provide indepth technical assessment as needed.
2 Appendix A DATE 2-04-87 REVISIQ4 NO.
2 PAGE 10 CURT 3fT REVISIO4:
SUPERSEDES: PAGE Appendix A, Page 10 USNRC APPROVAL REFEREHCE 5-04-84 1
DATE _
REVISIQ1
BABQXX & WILG)X QH'ANY, C0fERCIAL NlX1 EAR REL PUNT USNRC U NSE SNPt-1168 DOCKET E 201 SECTI(N 7.4 Pelletizing 7.4.2.'l UO Powder Receipt (continued)
~
2 f-(A$t.
e-M 3
I l
3 l
4 5
6 l __
Contents of reder containen 3 i/cc L:3 t
2 tarIch.xnt v/o 4.0 do 40 do do do it/U.
0.6 0.6 0.6 2.24 7.24 7.24 Interspersed roderatf or. (:)
0 7,.
100
' 0,, *.
7 100 Itff
.222 JL.004
.C7G A 0.012 0.535 1 0.010 0.5 s 0.011 1.018 1 0.011 0.925 1 0.C t
The above results indicate that, except in the case where all available space in all the powder containers is filled with moderator and 7% interspersed moderation is present l
(Case 5), K-effectives are acceptable. The situation -
calculated in Case 5 is not credible due to powder pa,ck-aging techniques and moderation controls established for the pelletizing area.
The limitation on the number of vertical containers in the sampling area is assured by physical sampling and conveying equipment limitations as well as by operator work area requirements.
I Powder containers are visually inspected upon receipt.
Containers exhibiting damage that could have resulted l
in violation of internal packaging are set aside on the loading dock for Hearth-5afety inspei: tion. Upon
~
~
Health-Safety determination that the container his no~t ~
been breached so as to allow internal moderation the con-DATE
~ 2-04-87 REVISION NO.
2 PAGE 44 1
ClRRENT REVISION:
l
~
44 SUPERSEDES: PAGE USNRC APPROVAL REFERENCE 5-04-84 I
DATE REVISION 1
i BAB0XX & WILO)X C&PANY, COMERCIAL NUCLEAR REL PlMT USNRC LICENSE SPM-ll68 DOCKET D E l III NUCLEAR SAFETY ANALYSIS SECTIGi 7.4 Pelletizing 7.4.4.4 Transfers Between Moderation Controlled Units (cont'd) ports, etc. Additionally, blind flanges, screw type caps, or other equally effective measures are utilized r
{
to provide secondary protection of penetrations I
into the blender and transport container at all L
times when such penetrations are not in use.
i When empty, process equipment normally operated under moderation control limitations is maintained in a closed and sealed condition and is inspected prior to returning.to use.
V Gloveboxes or other effective enclosures are utilized v
as necessary to preclude external moderation of SNM h
where the unit itself does not provide the necessary h
protection (slug press) or where, such as in blender I
i loading, the use of positive. connections is not feasible. Where practicable, such e1 closures shall t
l
.be of metal. When visibility or other operating requirements dictate their use, plastics or other hood: materials are of fire resistant construction i
]
(.chlorinatedPVCorequivalent).
t 7.4.4.5 Admininistrative Controls and Procedures i
Approved Health-Safety and iiFohess procedures
~
j j
DATE 2-04-87 ~
REVISION NO.
2 PAGE 110 CLRRENT REVISION:
t SUPERSEDES: PAGE 110 j'
LENRC APPROVAL REFERENCE 5-04-84 1
1 DATE REVISim d
)
BABC00( a WIUDX UPPM, ONERCIAL NUCLEAR REL PLM USNRC LICENSE SNPt-1168 DOCKET D E l III NUCLEAR SAFETY ANALYSIS SECTION t
7.4 Pelletizing i
l 7.4.4.6 Moderation control Measurements (continued)
[
OPERATOR QUALIFICATION Personnel responsible for measuring moisture content of UO will be trained in equipment operation and 2
result interpretation.
Such training will include practical use of the instrumentation and satisfactory analysis of unknown samples. Operation of moisture analysis units will be limited to authorized personnel. Authorized operators will be determined by the area supervisor.
PROCEDURES AND CHECK LISTS _
Specific procedures covering the use of nnisture
, analysis equipment, approved by Health-Safety, will be maintained at the work station. Additionally, the actual process is conducted in accord with a i
i
" check-list" indicating the operational sequence,
. development of analytical data, and the operator performing the analysis.
Points where " standard samples" are analyzed and the action to be taken in the event of an unsatisfacto.ry standard result are indicated.
2-04-87 112 DATE REVISION NO.
2 PAGE CURRENT REVISION:
SUPERSEDES: PAse 112 USNRC APPROVAL REFERENCE l
DATE 5 04-84 I
REVISION
1 l
BABOXX & WILWX C&PANY, C(MERCIAL NUCLEAR REL PIM USNRC LICENSE SN?t-ll68 DOCKER 70.1201 III NUCLEAR SAFETY ANALYSIS SECTIO 4 7.4 Pelletizing 7.4.4.7 Administrative Controls (continued) 1.
those in the process which require dual signature:
- Initial moisture analysis of as-received powder
- Prior to addition of powder lubricant to blender or transport container
- Prior to addition of re-cycle material to a moderation controlled unit, if the ma-terial has been exposed to an uncontrolled environment.
Adherence to the above procedure will be audited by Health-Safety at least monthly.
2.
The addition of powder lubricants to the blender or transport container has been shown to be safe under credible accident conditions.
However, in order to further preclude the potential for double batching of lubricant, or of adding lubricant to a system where the existing H/V is such that the additional moderator would cause the system to exceed the 0.45 H/V license specification, administrative controls are established for the receipt, storage, and DATE 2-04-87~
2 REVIS!Q1 %
PAGE 115 CURRENT REVISION:
SUPERSEDES: PAGE 115 WNRC APPROVAL REFERENCE 1
DATE 5-04-84 REVIS!Q1
i j
(
BABOXX & WILG)X C&PANY, 00M9CIAL NUCLEAR REL PIM b
USNRC LICENSE Snit-ll68 DOCKER 70.1201 III NUCLEAR SAFETY ANALYSIS SECTIO 1 N
0 7.4 Pelletizing
- 3
.7.4.4.8 General Area Moderation Control Criteria (continued)
In the event it becomes necessary to utilize " wet" decontamination techniques on a moderation controlled uni ts, Health-Safety shall inspect and certify that visible moisture is not present before the unit is returned to service.
FIRE FIGHTING Specific procedures relative to fire fighting will be instituted and will include, as a minimum, the following considerations:
A.
Fire fighting capability will be based on the use of CO, "Halon" or other non-hydrogeneous 2
agents.
B.
The CNFP Fire Brigade will be informed of area restrictions and will receive training in the techniques to be utilized.
C.
All fire fighting efforts will be conducted under the direction of qualified members of the plant management.
D.
Accumulation of flammables will be' limited to the greatest practical extent.
2-04-87 DATE REVISION No.
2 PAGE 119 CURRENr REVISIQ4:
SUPERSEDES: PAGE ll9 G RC M R R E N 1
{
DATE _ 5-04-84 REVISIQ1
MB000( & WIUDX C&PM, CutEEIAL NUCLEAR REL P!M USNRC UCENSE SNPt-3168 DOCKET & l201 SECTION III NUCLEAR SAFETY ANALYSIS 7.4 Pelletizing 7.4.4.8 General Area Moderation. Control (continued) 9 FIRE FIGHTING i
E.
The area contains no source of generalized mo-deration such as sprinkler systems, or steam lines.
[
Flammable wastes will be stored only in metal containers approved by Health-Safety.
WATER LINES Figure 1 shows the placement of water lines in the pelletizing area relative to moderation-controlled and.other major equipment positions. Water lines ~
are, except where necessary to service equipment, located against (e.g.,
- 1' foot) the outer bu.ilding walls approximately 20 feet above the floor and are secured.in place by'means of steel brackets.
l For purposes of industrial safety, and to limit the i
potential for accidental damage, the water lines
'necessary for furnace and grinder operation are po-i sitioned above head height until the unit to be serviced is reached.
t i
i The typical baffling technique for service lines positioned along the plant walls is represented 1
~2-04-87.
j MTE REVISION NO.
2 PAGE 120 l
CLERENT REVISION:
f]
SUPERSEDES: PAGE 120 USNRC APPROVAL REFERENCE I
MTE 5-04-84 REVISION i
BABOXX & WIL(DX CGPANY, OMERCIAL NVQfAR REL PUNT l
USNRC UCENSE SNPt-ll68 DOCKET E 1201 III NUCLEAR SAFETY ANALYSIS L
SECTICN L
7.4 Pelletizing 7.4.4.8 Unit Area Moderation Control (continued)
WATER LINES directly over moderation controlled units or arrays, the overhead shielding essentially serves as a tech-nique for providing "second order" protection. The shielding is not required to protect the array from accidental moderation due to pipe rupture since that contingency has been provided for through baffling ;
and double containment.
PERIODIC EVALUATION OF MODERATION CONTROL EQUIPMENT The routine calibration and standards analysis pro-gram for moderation control instrumentation has been described previously. While safety within an operational area is the responsibility of the area supervisor. Health-Safety conducts ' routine system audits to verify that all activities are conducted safely and in accord with Iicense conditions.
Additional nuclear safety and health physics audits are conducted by qualified B&W personnel, from outside the CNFP, at least quarterly.
r At least monthly, a detailed inspection will be con-ducted by Health-Safety, DATE z-u4-u/
REVISION NO.
2 PAGE 124 CtERENT REVISION:
SUPERSEDES: PAGE 124 WNRC APPROVAL REFERENCE I
DATE 5-04-84 REVISION
BAB000( a WILIDX QNANY, UNERCIAL NUCLEAR REL PLAff USNRC LICENSE SNW1168 DOCKET E 1201 III NUCLEAR SAFETY ANALYSIS SECTION 7.4 Pelletizing
~
The following measures are applied to minimize 7.4.5.1 FIRE.
de fire potential and to assure localized containment in the event a fire does occur.
1.
Hoods, gloveboxes, and other containment devices are constructed of fire resistant materials ("Self-extinguishing " Plexiglas" conforming to ASTMD 635,i' or equivalent) with metal supporting members.
2.
Pre-filters and HEPA units are the fire resistant metal case type. Additionally, supporting units and manifolds are of flame resistant construction.
Breaching of the ventilation system is not credible due to the limited flammable material available.
3.
Accumulations of flammable wastes and scrap are removed from the area promptly when containers are filled. Only covered fire-safe containers approved by Health-Safety are utilized for the accumulation of flammable wastes in the pelletizing area.
I 4.
Limited quantities of flammable solvents may be required for operation.
These materials are DATE 2-04-87 REVISION NO.
2 PAGE 129 t
CURRENT REVISION:
SUPERSEDES: PAGE 129 USNRC APPROVAL REFERENCE
't 1
DATE 5-04-84 REVISION
L BABC00( & WIL(DX Caf#f(, 00ftERCIAL NUClEAP. REL PLM tlSNRC LICENSE SNM-ll68 DOCKET &l201 III NUCLEAR SAFETY ANALYSIS SECTIO 4 7.4 Pelletizing 7.4.5.1 FIRE.
6.
While Brigade members are cognizant of the radiological and nuclear safety limitations that may be imposed, any major fire fighting activity would be conducted under the direction of responsi-ble plant management (e.g., except 1st aid measures).
Brigade members receive semi-annual training by representatives of Health-Safety as appropriate to the subject matter.
7.
Formal weekly inspections are conducted by Heal th-Safety to monitor the effectiveness of, and ad-herence to, the fire prevention program.
8.
Response arrangements have been made with the Con-cord Volunteer Fire Department. The Lynchburg Fire Department and the Concord Volunteer Fire Department have toured the CNFP facilities and have been made aware of special hazards that may be encountered.
Retraining is conducted on an annual basis.
Based on the above considerations, as well as the limited potential for fire within the process itself, it is felt that fires represent only a limited accident potential.
The most likely hazard will consist of DATE 2-04-87 REVISION NO.
2 PAGE 131 CURRENT REVISION:
SUPERSEDES: PAGE 131 WNRC APPROVAL REFERENCE I
DATE 5-04-84 REVISION
n BABC00( a WILWX GWANY, COM9CIAL NUCifAR REL PLM USNRC LICENSE SNM-ll68 DOCKER A1201 III NUCLEAR SAFETY ANALYSIS SECTICH 7.14 Waste Storage 7.14.2 Nuclear Safety Parameters The safety of both 850 grams of U-235, and the 4.0" slab has been demonstrated elsewhere.
7.15 Self-Explanatory.
7.16 Transport 7.16.1 Such trans' port occurs only during the course of manufacturing activities, at.which times abnormal levels of moderation are not present, interaction with other materials need not be considered.
P 7.17 UF Storage 3
7.17.1 Storage Parame:ers - Source and Special Nuclear Material The UF, as received for storage only, will be in solid form 6
and stored in cylinders that are approved for shipment.
The cylinders will be stored outside, in an area designated for UF storage within the CNFP security fence. The cylinders will 6
be stored on timbers designed to cradle and give support, in an area prepared and maintained under weed control, and located 2
a minimum of 100 ft. from the paved driveway which circles the CNFP.
The cylinders will be equipped with valve protectors, and will be routinely monitored by, Health-Safety personnel to detect leakage and to assure the continued adequacy of storage conditions.
Outside storage of enriched UF cylinders has been 6
previously determined to have no adverse environmental impact (Reference 1).
Reference 1: BAW-1412, Annex 1; UF to U0 Conversion Facility.
6 2
DATE
'2-04-87 REVISION No.
2 PAGE 190 CLRRENT REVISION:
{.
SUPERSEDES: PAGE 190 USNRC APPROVAL REFERENCE I
5-04-84 l
DATE REVIS!m
i BABC00( a WIUDX COPANY, COMERCIAL NUCLEAR REL PUE USNRC UCENSE SNPt-ll68 DOCKER E 1201 IV HEALTH PHYSICS SECTICN
- 1. '
INTRODUCTION This section presents the health physics program which is adminstered at the Comercial Nuclear Fuel Plant of the Babcock & Wilcox Company to assure safe operating conditions. The information provided in this section is intended to demonstrate typical methods utilized in the health physics and, to some extent, in the industrial safety programs and, as such, is subject to change in detail, or in the application.of alternate methods.
Progr'am effectiveness will not be reduced as a
~
result of changes instituted by plant management. Technical specifica-tions defining the parameters which the health physics program must
+
meet are contained in Section V.
i l
2.
POLICY Operations involving exposure, or potential exposure, to radioactive materials will be performed in a manner which will assure the radiation safety of employees and t.he general public. This policy is implemented by maintainina -
taff of qualified personnel and appropriate equip-
~
ment, procedures, and records. Operations will be conducted in I
accordance with applicable Federal, State, and Local requirements.
Exposures to radioactive materials, or other hazards, will be maintained as low as reasonably achievable.
Health'-Safety has the autiiority
~
to stop hazardous or potentially hazardous operations until correction or resolution by plant management is obtained.
'~
DATE 2-04-87 REVISICN NO.
2 PAGE 1 ClRRENr REVISION:
SUPERSEDES: PAGE 1
WNRC APPROVAL REFERENCE 5-04-84 1
DATE REVISIm
BABOXX & WILCDX C&PANY, OtERCIAL NUOf# REL PIRT USNRC LtCENSE SNM-ll68 DOCKET h.l3 1 SECTION 3.3 Detailed operating procedures are developed by Health-Safety to assure standardization, accuracy, and effectiveness of activities performed by Heal th-Safety.
Procedures are reviewed periodically and revised as required.
As a minimum, Health-Safety procedures shall be approved in writing by the Manager, Quality and Safety as well as approved by aftected members of plant mariagement.
l 4.
RESPONSIBILITIES The Health-Safety.Section reports directly to the Manager, Quality' and l
. ho reports directly to the Plant hanager of the Commercial l
Safety w
Nuclear Fuel Plant.
4.1 Health-Safety 'Section Health-Safety personnel are responsible for the general surveil-lance of all activities involving radioactive materials, distributing l
and processing personnel monitorino equipment, maintaining in-f dividual exposure records, notifying supervisors of significant exposure levels, and recommending appropriate restrictions.
Other responsibilities are represented by, but not limited to, the following:
i a.
Maintaining appropriate radiological and regulatory control of radioactive material, shipments, and receipts.
b.
Supervising and coordinating the contaminated waste l
disposal program.
j Assisting in personnel and equipment decontamination.
]
c.
3 f,j 2-04-87 2
3 DATE REVISION NO.
PAGE 1
CURRENT REVISION:
SUPERSEDES: PAGE3 USNRC APPROVAL REFERENCE 5-04-84 1
DATE REVISIm 1
BAB000( a WIUDX ONM, COM9CIAL NUOfAR REL PLM 1
I USNRC LICENCE SNM-ll68 DOCKET M-1201 IV HEALTH PHYSICS SECTION f
4.1 d.
Orienting and training CNFP personnel in radiological f
and nuclear safety.
I e'. Furnishing consulting services and advice on radiation j
protection to plant supervision and management.
i f.
Generating or acquiring, maintaining, and appropriately distributing all records and reports required by appli-cable regulations or procedures.
g.
Leak testing on sealed radioactive sources.
i h.
Developing and disseminating procedures related to i
radiation safety and reviewing procedures prepared by other operating sections for regulatory compliance and the adequacy of safety considerations.
4.2 Employees S'ince every unnecessary exposure to radiation violates sound Health Physics practicy, each CNFP employee is responsible for the following:
a.
Following all established Health-Safeti proce~dures.
~
j b.
Seeing that any visitor in his company or custody observes all established Health ~ Safety procedures.
f c.
Reporting any radiation hazard or potential hazard to his super-visor or to a Health-Safety repfes~entative.
d.
Minimizing radiation exposure, and assisting in the evaluation of exposure of himself and others to the 0
4 DATE 2-04 87 REVISI M NO.
2 PAGE ClRRENT REVISION:
].
SUPERSEDES: PAGE 4
USNRC APPROVAL REFERENCE DATE 5-04-84 1
REVISim d
BABC00( & WIL00X COM, CatERCIAL NUCLEAR FLEL PLAVT USNRC LICENSE SNM-ll68 DOCKET 70-1201 IV HEALTH PHYSICS SECTIO 4 4.2 d.
extent possible by:
- Wearing prescribed monitoring and protective equipment.
- Surveying hands, shoes, and body for radioactivity and removing loose contamination to prescribed tolerance levels to comply with approved decontamination procedures.
- Wearing appropriate protective clothing whenever contami-nation of clothing is possible, and not wearing such clothing outside prescribed areas.
- Using recommended safety equipment; using proper techniques and facilities in operations.
- Observing regulations governing eating and smoking in cobtaminatedareas.
- Promptly reporting injuries and suspected or known in-gestion or inhalation incidents to Heal th-Safety.
- Cooperating in all attempts to evaluate exposures.
- Roping off hazardous areas, controlling potential hazards, and reporting contamination to his supervisor.
- Cleaning up contamination for which he is responsible.
- Properly storing and labeling radioactive materials for which he is responsible.
- Being familiar with the evacuation plan and evacuation route.
4.3 Supervisors Each supervisor is responsible for ensuring that the individual DATE 2-04-87' 2
5 REVIS!Q1 NO.
PAGE CURREt(T REVIS101:
5 SUPERSEDES: PAGE NRC APPROVAL REFERENCE 5-04-84 1
DATE REVISIQ1
BABC00( & WILOR COPANY, COMUCIAL NlX1 EAR REL PLAff USNRC UCENSE SNPt-1168 DOCKET 70-1201 IV HEALTH PHYSICS SECTION 4.3 responsibilities listed previously are discharged by persons under his control and is also responsible for the following:
1.
Acting in conjunction with Health-Safety to keep his em-ployees' exposure below 300 mrem in 1 week and keeping the average weekly exposure below 1.25 Rem /13 weeks (See 10 CFR, Part 20).
2.
Furnishing information to Health-Safety on individuals and activities in his area, particularly additions to or deletions from, his' personnel roster.
3.
Contacting Health-Safety whenever major changes in operational procedures, new techniques, or new operations are anticipated.
.5.
OPERATIONAL EVALUATION Radiation safety evaluations will be made for new operations, or those operations undergoing significant revisions or redesign.
These evalua-tions will also consider industrial and nuclear safety as appropriate.
Pre-operational evaluation may consider, but is not limited to, such items as ventilation control, external exposure potential, license compliance, contaminated waste generation and control, and special protective measures that may be required.
Results of the evaluation will be reviewed with cognizant area supervision and any necessary changes will be made prior to approval for operational startup.
In addition, the evaluation results will be documented and maintained on file at the CNFP for at least six months after termination of the operation.
MTE 2-04-87 REVISION NO.
2 PAGE 6
ClRRENT REVISION:
SUPERSEDES: PAGE 6
(ENRC APPROVAL REFERENCE I
MTE 5-04-84 REVISION
MBC00( a WIL(DX QPPM, CafERCIAL NtX1 EAR REL PLN USNRC LICENSE Sl#t-ll68 DOCKET D E l SECTim IV HEALTH PHYSICS 6.
RADIATION SAFETY EQUIPMENT
[
Instrumentation, appropriate to the detection, monitoring, and measure-i ment of industrial and radiological safety hazards potentially encountered j
in a nuclear fuel plant, will be maintained by _ Health-Safety, f
6.1 A list of radiation detection and miscellaneous instrumentation is.
k given below. These instruments are typical of those which are available for use at the CNFP.
Equivalent substitutes, or
]
additions, will be acquired as necessary.
I a.
Alpha survey and monitoring f
-PAC-4G(0-500KCPM2x)
)
-AlarmingHandMonitor(50 CPM 2x) 3 I
b.
Low Range 8/y survey - Eberline E-120 (0 - 50 mR/hr.)
j
- Eberline E-530 (0,- 200 mR/hr.)
1
.1 c.
Intermediate' Range y survey - Eberline " Rad Owl" R0-2A (0-50R/hr.)
d.
High Range y - Victoreen Radector II (0 - 1000 R/hr.)
e.
Laboratory =/8/y Measurement - NMC Proportional system, DSIT/
9 h
PC11T 1
- Ludlum scinta11ation systevi, Model 20-A i
- Multi-channel analysis capabilities, alpha spectrometers, j
etc., are available at other B&W facilities, f.
Miscellaneous 1
- Positive displacement, low flow rate sampling pumps
,3j
- HG-70 and " Glass fiber" filter papers h
- Sound level meter, Pulsar, Model 85 2
DATE 2-04-87 REVISION NO.
PAGE 7 ClRRENT REVISION:
j-SUPERSEDES: PAGE 7
USNRC APPROVAL REFERENCE 3
DATE 5-04-84 I
REVISION 1
d
)
.o BAB000( a WIL(DX COPANY, GifERCIAL NV0 EAR REL PIAU USNRC LICENSE SNftll68 DOCKET 70-1201 IV HEALTH PHYSICS SECTICN 7.1 CNFP procedures require that Health-Safety be notified before maintenance or other non-routine operations are undertaken if significant airborne activity may result.
Data collected by work station or other fixed samples is supported, and modified if necessary, based on lapel sample results.
Lapel sample collection frequency is determined by Heal.th-Safety based on verification requirements and the_ nature of the operation being conducted.
7.2 : Smear surveys to evaluate surface contamination levels are con-ducte' throughout the plant on a regular schedule.
Routine survey d
frequ,ency varies from daily to monthly depending on contamination potential or potential hazard category. Portable instruments used concu'rrently with smear. surveys provide a means of assessing total surface contamination.
In addition, special smear programs are instituted as consi.dered necessary by Health-Safety to provide in-depth coverage of special or unusual activities and to evaluate the effectiveness of decontamination. Material being transferred from a " contaminated" to a " clean" area is routinely monitor.ed i
for surface contamination.
7.3 External (." penetrating") radiation levels throughout the plant l
are monitored using a combination of portable instruments and TLD area dosimeters.
i l
l.
DATE 2-04-87 REVISION NO.
2 PAGE 10 CtRRENT REVISION:
SUPERSEDES: PAsE 10 USNRC APPROVAL REFERENCE 5-04-84 R
DATE REVISION 1
ll
BABC00( & WILG)X QNANY, UNERCIAL NUClfAR REL PLANT USNRC LICENSE SWt-ll68 DOCKET M -1201 SECTIm IV HEALTH PHYSICS 8.'
PERSONNEL DOSIMETRY AND EXPOSURE CONTROL 8.1 Personnel monitoring devices are. selected by Health-Safety on the _
basis of radiation type and sensitivity requirements, and' may include film, TLD, or pocket chambers.
Rapid dosimetric evalua-tion of neutron exposure in the event of accidental criticality is provided by indium foil issued to personnel as part of their standard dosimetric package.
Dosimeters are issued to all plant employees and selected visitors based on the requirements of 10 CFR 20, with routine monthly or quarterly e changes. Use of special dosimeters may be required by Health-Safety, where unusual exposure levels may be encountered, as in source manipulation. An indica-
~
tion of 100 mR/or more on a pocket hamber requires the expeditious evaluation of the employee's TLD or film.. Extremity exposure is monitored using TLD's as determined necessary by the Health Physicist, or Healt'h-Safety Leader. TLD and f,ilm dosimeters are pro-cessed by a vendor with monthly or quarterly printout forwarded to CNFP.
More rapid notification is available by telephone if needed.
Personnel involved in activities where exposure to airborne activity is possible participate in a bio-assay program con-ducted in accord with. Regulatory Guide 8.11 (" Applications of
~
Bioassay for Uranium"). Operatin'g philosophy is that the air sampling program, supported by the smear surveys, provides DATE 2-04-87 2
REVISION NO.
PAGE 11 ClRRENT REVISION:
i-SUPERSEDES: PAGE LENRC APPROVAL REFERENCE 5-04-84 1
i DATE REVISION 1
j BABC00( & WILG)X COPANY, CatERCIAL NUCLEAR REL PIMF USNRC LICENSE SNM-ll68 DOCKET 70-1201 SECTICN 8.1 definitive indications of personnel exposure. Bioassay techniques,
~
including urinalysis and in-vivo counting serve to validate the effectiveness of existing exposure controls. A " Base-Line" bioassay (urine) sample is collected from all new hires and from terminating personnel with an exposure history.
In addition, newly' hired employees whose job assignments involve handling of significant quantities of unclad SNM are scheduled for in-vivo analysis as required.
In-vivo and urinalysis services are provided by a Fecal sampling may be empl'yeed, as considered necessary vendor.
o by the Health Physicist or Health-S.afety Leader to evaluate the magnitude of suspected accidental or elevated exposure.
8.2 Radiation exposure and absorbed dos'e to employees are derived based on dosimetric results and in accord with 10 CFR 20.
Normal operational doses accrued by CNFP employees are limited to the following (10 CFR 20.101)
- Whole Body, trunk and head, active blood forming organs, lens of eyes, and gonads 1.25 Rem / cal. qtr.
- Hands and forearms, feet and ankles 18.75 Rem / cal. qtr.
- Skin of whole body 7.50 Rem / cal, qtr.
However, NRC Form 4 documentation is provided for each permanent employee and in specific cases the Manager, Quality and' Safety, Health Physicist, and the Plant ~ Manager may autnorize ex;
~
posures greater than the above provided 10 CFR 20.101 (b) and 20.102 requirements are satisfied. In these cases, the " maximum permissible exposure" 2
DATE 2-04-87 REVISION NO.
PAGE 12 ClRRENT REVISION:
SUPERSEDES: PAGE 12 (ENRC APPROVAL REFERENCE DATE 5-04-84 I
REVISION
r i
BAB000( & WILEX C&PANY, CatERCIAL NIX 1 EAR REL PIM L
l USNRC LICENSE SNM-ll68 DOCKET M-1201 SECTICN IV HEALTH PHYSICS 8.6 Eating and smoking are prohibited in controlled areas. Smoking i
may be permitted in change rooms if assurance of adequate radiological hygiene practices are maintained. At the discre-tion of the Health Physicist drinking fountains may be located within controlled areas where non-transportable materials are being processed.
Drinking facilities are providd in change areas.
8.7 Exposure histories at CNFP for the period 1977-1980 are shown in Fige*e 1 below.
Data show normal fluctuations from period to period, without significant discernable trends.
FIGURE 1 Maximum MPC H urs/Otr. for an Individual xpres d 1
owable 5 rem /yr.. whole body exposure, except as otherwise noted)
(Expressed as % of maximum allowable 520 MPC Hours /Qtr.)
1977 1978 1979
.1980 Year 1979 1960 P
t and 4.9%
3.7%
4.7%
4.2%
!st Qtr.
17.2%
20.3%
- Internal % of 2nd Qtr.
18.6%
17.6%
maximum 2080 4.9%
3.2%
4.3%
4.4%
MPC hrs./yr.
3rd Qtr.
14.0%
15.8%
Rod Processing Assembly Fabri.
2.6%
l'. 3%
4.25 4.4%
- I'*"
4th Qtr.
17.2%
11.25 nte a
- e. Grid.
0.5%
0.3%
1.1%
1.2%
(
Office 0.1%
<0.1%
0.1%
0.1%
l MTE 2-04-87
REVISI(N NO.
2 PAGE 14
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CLRRENT REVISION:
SUPERSEDES: PAGE 14 WNRC APPROVAL REFERENCE MTE 5-04-84 I
REVISION
BAB000( & WILCDX C&PANY, 00WERCIAL NUQEAR REL PIM USNRC U NSE SNM-ll68 DOCKET E-3201 SECTICN IV HEALTH PHYSICS 9.1 filters (in series) before re-entering the area. Air recirculated to the pelletizing area is representative 1y sampled on a continuous basis to verify filter effectiveness.
Existing procedures require notification of Health-Safety prior to servicing or maintenance on those portions of the fans or HEPA systems that may be contaminated.
Flow sensing elements are installed within ductwork at appropriate i
locations to provide an audible and visual alarm if flow is interrupted.
If flow loss is other than a momentary disrup' tion, I
operations may be terminated until proper ventilation is restored.
l Additionally, pressure sensing devices are routinely monitored to assure that the controlled area remains negative with respect to the remainder of the plant.
- 10. LIQUID EFFLUENT CONTROL Potentially contaminated liquids generated at the CNFP are controlled by means of a dedicated drain and retention tank system. Sanitary wastes, and waste originating in areas where there is no potential for i
radiological or chemical contamination, are routed to a sewage treat-1 ment plant through separate piping.
Liquids originating in the con-trolled area, analytical labs, de-ionizer area and " cleaning room" are part of the retention tank system.
Liquids accumulated in the retention tanks are sampled, radiometrically 2-04-87 21 DATE REVISION No.
2 PAE CLRRENT REVISION:
SUPERSEDES: PAGE 21 WNRC APPROVAL REFERENCE L
DATE 5-04-84 REVISION 1
F
BABOXK & WILG)X GPPANY, CatERCIAL NUCLEAR REL PLM USNRC LICENSE SNW1168 DOCKET D E l SECTI(N 10'.
LIQUID EFFLUENT CONTROL analyzed, and treated as necessary, prior to release. The retention tank system incorporates capacity alarms, and air agitation capability.
Analytical sensitivity is 1% of the applicable 10 CFR 20, Appendix B, Table II limit. The sampling program is under the control of Health-Safety and no releases are made without the. prior approval of that component.
The retention tanks are housed in the Rad Waste Retention Building.
'l.
SOLID WASTE DISPOSAL l
Non-contaminated solid wastes are disposed of through a contract hauler.
Contaminated solid wastes are sent to another licensed facility for processing or to a licensed burial facility.
l Uncontrolled disposal of solid wastes or equipment is authorized when 2
contamination levels do not exceed an average of 2500.dpm/50 cm and a 2
2 maximum of 7500 dpm/50 cm for total alpha; 1000 dpm/100 cm maximum for removable alpha; or an average of 0.2 mradAir. and a maximum of 1 mr/hrt (8/y) a't 1 cm.
Establishment of the above contamination limits to permit disposal in accord with routine industrial practice does not present a hazard to the general public and the limits are generally accepted, within the nuclear iridustry, as not presenting any significant radiolo-gical or nuclear safety hazard. 49CFR173.397(a)citesremovable 2
contamination levels below-2,200 DPM/100 cm as being insignificant when applied to natural or depleted uranium. Although uranium enriched 235 up to 4.05% will be the contaminant of interest, the low 0 content DATE 2-04-87 REVISION NO.
2 PACE 22 CLERENT REVISION:
0 SUPERSEDES: PAGE 22 uSNRC APPRWAL REFERENCE 5-04-84 1
DATE REVISIm
BABCDO( & WILG)X QMYW, QMERCIAL NUCLEAR REL PLAVT USNRC LICENSE SNPt-ll68 DOCKET M-1201 SECTICN IV HEALTH PHYSICS 11.
SOLID WASTE DISPOSAL is not significant in the present case for radiological safety purposes and is treated as natural uranium. Additionally, 49 CFR 173.391(a) notes that the allowable B/y exposure rate is 0.5 mrem / hour for exempt shipments. Solid waste material, when the radioactive component is distributed throughout the non-radioactive matrix, is not considered radioactive when the specific activity does not exceed 0.002 microcuries per gram (49 CFR 173.389).
Routine sampling and monitoring programs are conducted by Heal jh-Safety
~
to assure that material, contaminated in excess of specification limits.
is not released for uncontrolled disposal and to detect and alleviate l
increasing contamination trends.
'11'. 2 Contaminated solid wastes consist primarily of low specific activity material and are disposed of a by a licensed contractor by land burial on an NRC or state licensed site.
LSA wastes are packaged in containers designed to retain loose contamination.
SNM content for each package is estimated using garmia scan or sampling technique.
12.
RESPIRATORY PROTECTION A supply of respirators, equipped with high efficiency filters, is maintained for use in unusual conditions where airborne concentrations l
are such that personnel may receive exposures in excess of acceptable DATE 2-04-87 REVISION NO.
2 PAGE 23 CURRENf REVISION:
23 SUPERSEDES: PAGE USNRC APPROVAL REFERENCE DATE 5-04-84 1
REVISim
BAB000( & WILOR ONANY, C0ftERCIAL NUGEAR REL PIM USNRC LICENSE Snit-ll68 DOCKET 70.1201
)
IV HEALTH PHYSICS SECTIQ4 12.
RESPIRATORY PROTECTION limi ts. All respiratory devices for protection against radioactive materials are approved by the NIOSH or other authorized governmental authority.
Respiratory devices giving effective protection against acid gases, chlorine, ammonia, and other toxic substances as well as L
particulate are available, based on the specific requirements imposed by plant activities. Self-contained breathing units of the "back pack",
pressure demand type, are provided for e'mergency use.
Examples of operations for which respiratory protection may.be
[
determined to be necessary by Health-Safety include certain mainte-nance activities such as filter changes and to provide an additional safety factor during the initial start-up of operations wher.e the extent of airborne contaminatioit cannot be evaluated accurately during the pre-operational check.
Respirators are not used as a routine protective measure or as a substitute for engineered controls.
12.1 All respiratory devices, used for protection against toxic 4
substances, as opposed to those used for " nuisance control" (paint spraying, etc.) are maintained, issued, and use-monitored by Heal th-Safety. Healtn-Satety also determines the type of respirator to be used in a particular situation.
Each individual who is required to wear a respirator, for toxic substance protection, is ' trained by Health-Safety in t roper use i
and fitting including:
DATE 2-04-87 REVIS!Q1 NO.
2 PAGE 24 CURRENT REVIS101:
SUPERSEDES: PAGE 24 LENRC APPROVAL REFERENCE j
DATE 5-04-84 REVIS!Qi I
tl
BAB000( & WILCDX C&P#f/, CDtERCIAL NUCIFR REL PINT G RC LI NSE SNft-ll68 DOCKET 70.1201 SECTICN IV HEALTH PHYSICS 12.1 a.
Advise that the user may leave the area in case of malfunction.
and psychological or significant physical discomfort.
b.
Proper method of fitting and use (wearing) of the respirator.
The initial f.tting of a respirator on an individual will be conducted b; Health-Safety during the t' aining program and r
the fit checked by,sr.;oke or an equivalent method.
Procedures relating to respirator use, training, and maintenance are in effect.
Respirator maintenance is performed by Health-Safety based on manufacturer's recommendations.
Routine inspections are conducted by Health-Safety tio evaluate operability, c, heck for deteriora-tion, and to remove outdated components from stock. Out, dated can-nisters, etc., may be used for training purposes; however, they will be identified so as to prevent use in a situation where protection is required.
Air sample coverage is provided during all activities where the use of respirators is required. Special bioassay evaluations are undertaken if justified in the opinion of the Health Physicist or Health-Safety Leader in order to define the respirator effectiveness, 12.2 Protection factors for respirators currently available at the DATE 2-04-87 REVISIGl NO.
2 PAGE 25 CtRRENT REVISlal!
SUPERSEDES: PAGE 25 lJSNRC APPROVAL REFERENCE 1
DATE 5-04-84 REVISIQ1
.c j
M & WILOR C@P#lY, CGff.KIAL NinEAR RB. PUNT USNRC LICENSE SNPtll68 IDCKET 70-3201 IV HEALTH PHYSICS SECTION 12.2 CNFP, are defined below:
a.
Half-mask facepiece, negative pressure - 10 L
b.' Full face piece, negative pressure 50 c.
Full face powered air purifier - 1000 d.
Self-containad breathing apparatus full face (pressure demand) -
1000
- 13. ANTICONTAMINATION PROGRAM Means for the limitation of personnel contamination in controlled areas and the spread, by personnel, of contamination from controlled areas are defined by ' Health-Safety procedures and plant design criteria.
All persons ent'ering contaminated areas are required to wear pro-tectivefothin_g.
Minimum protective clothing consists of shoe covers l
and lab coats. Additional protection in the form of coveralls, hair covers, etc., is required, where necessary (e.g., pelletizing area).
Anti-contamination clothing is identified to assure that is not worn in " clean" areas without., Health-Safety approval'.
Change room facilities are provided at all entrances to controlled areas, the sole exception being emergency exits, and controlled access points, not used on a routine basis. The change rooms contain facilities for protective and personal clothing storage and decontamination.
" Controlled" showers are available for whole body Fixed al'ha monitors are installed in all change decontamination.
p rooms.
Instructions for the use of these monitors and the decontami-nation procedures to be followed are posted with the instrument.
2-04-87 DATE REVISION NO.
2 PAGE 26 CIRCENT REVISION SUPERSEDES: Pace 2e 5-04-84 I
DATE REVISim
BABOXX & WIUDX CGP#f(, CufERCIAL NUQIAR REL PLM USNRC LI NSE SNM-ll68 DOCKET & l201 IV HEALTH PHYSICS SECTim
- 13. ANTICONTAMINATION PROGRAM In the event an employee cannot reach satisfactorily low contamination 1evels after two attempts he is instructed to contact' Health-Safety for further evaluation. A personnel decontamination kit is maintained in the First Aid Room.
Section V, Part 8.4 specifies action levels for surface alpha contamina-tion on personnel and equipment.
Entrance to the controlled area is demarcated by means of easily visible t
stepoff lines.
Instructions for proper use of the change room facility are posted'by Health-Safety as appropriate. Normal' access to the con-trolledareaislimitedtothechangeroom,landthelayoutofthe change room itself is such that individuals exiting the contaminated area must pass the decontamination and monitoring points.
Tools and other equipment routinely used within the controlled area are conspicuously marked and 'are not normally removed from the area. If removal is necessary, decontamination to the levels specified.in Section V, Part 8.4 is undertaken.
If decontamination attempts are not successful, specific licalth-Safety appr' oval must be obtained prior to removal, and additional controls instituted as necessary. Where tools or equipment have been exposed to high contamination levels such as may be found inside process units, the items will be decontami-nated as soon as practicable, or will be packaged and labeled if prompt cleanup is not feasible. All such equipment will be decontaminated prior 2-04-87 DATE REVISION NO.
2 PAGE 27 CURREt(T REVISION!
SUPERSEDESi PAGE 27 WNRC APPROVAL REFERENCE
BAB000( a WILGA C0F#f/, C0WERCIAL NUCLEAR REL PUM i
I USNRC LICENSE SNPt-ll68 DOCKET E 1201 SECTIG4 IV HEALTH PHYSICS
- 13. ANTIC 0NTAMINATION PROGRAM to removal from the controlled area unless the item is intended for disposal'as radioactive waste and is properly packaged to prevent contamination spread.
- 14. MEDICAL AND FIRST AID PROGRAM Medical examinations of employees are performed as consistent with good industrial practice.
All employees receive,a thorough pre-employment physical including kidney function, hematological evaluation, and chest x-ray.
Examinations upon termination of employment will be made when considered appropriate by plant management.'
Babcock & Wilcox has retained the services of a number of area physicians l
to assure adequate representation of variou's medical specialties as appropriate. The CNFP maintains a fully equipped First Aid Room staffed by. oorsonnel qualified in first aid. Additional plant personnel receive Red Cross (or equivalent) training to assure that first aid capability is always available.
Registered nurse and ambulance services are availabic on site from another B&W facility.
15.
PERSONNEL TRAINING All personnel receive basic training in radiological, industrial, and nuclear safety upon being hired.
This initial training is a coopera-tive effort involving Personnel, Health-Safety, and the employee's supervisor and is designed to satisfy the requirements of 10 CFR 19.12.
IMTE 2-04-u/
REVISION No.
2 PAGE 28 CURRENf REVISION!
SUPERSEDES: PAGE 28 LENRC APPROVAL REFERENCE 5 04-84 l
DATE REVIS!m
(
BAB000( & WIL(DX Cuf##, CORERCIAL NUCLEAR REL PlAff USNRC LICENSE SNM-ll68 DOCKET 70-1201 IV HEALTH PHYSICS SECTION
- 15. PERSONNEL TRAINING Particular emphasis is placed on the nature of the materials handled, plant safety program and rules,10 CFR 19 requirements, and the emergency evacuation system. The training is documented in Health-Safety records. Additional training sessions, of a general or specialized nature, are conducted by Health-Safety as requirec.
Postings are mace as required by 10 CFR 19 and 20 specifications.
Radiation workers are re-trained annually.
15.1 Employees are referred to Health-Safety by the Personnel Department for initial training in safety. At this time, the entire plant safety program is reviewed in some detail with par-ticular emphasis being placed on specific areas according to the employee's job assignment. A brief discussion' o'f, and familiari-zation with, the general principles of health physics and nucicar safety is included.
The employee is informed of his rights and responsibilities under CFR 19, and OSHA. Training sessions are documented and filed as part of the employee's Health-Safety record.
Following the initial indoctrination, the employee receives additional safety training from his imediate supervisor. The employee' immediate supervisor shall complete a new employee training verifica-tion form (App. 3 Exhibit A) prior to allowing the employee to operate independently.
15.2 Continuing training of a gancral nature is provided as necessary b
This training may be formalized
\\
(y Health-Safety and supervision.
i.e., " classes") or informal and conducted as a part of routine DATE 2-04-87 REVISIOl NO.
2 PAGE 29 CURRENf REVISION!
29 SUPERSEDES: PAGE lENRC APPROVAL REFERENCE DATE 5-04-84 REVISIQi 1
n I
BABC00( a WIL(DX C0f##, QMERCIAL NUClfAR REL PLAY USNRC LICENSE Snit-1168 DOCKET 70-1201 IV HEALTH PHYS 10S SECTIO 4 15.2 Health-Safety audits.
Formalized retraining may be utilized to explain operational changes affecting safety, control of special problems such as increased airborne activity, or changes in license specifications.
The responsibility for determining the necessity for retraining or special training rests with Health-Safety based on plant conditions or tne request of supervision.
15.3 Training and retraining in the use of respiratory protection devices is provided by Health-Safety as required.
Points relating to proper use are covered as the unit is issued and fitted by Heal th-Safety.
This approach provides continu1ng review of respiratory protection requirements. Should situations arise where frequent use of a respirator is necessary, frequent Health-Satety surveillance will assure continued proper application.
15.4 Specialized training for special and emergency r'esponse units such as the Fire Brigade, Radiation Monitoring Team and First Aid personnel is coordinated by dealtn-Safety.
Fire origaac training is conducted by representatives of Health-Safety and/or local Fire Departnents and covers the use of equipment and agents available at CNFP including high pressure water, C0, dry chemical, 2
and Met'L-X.
Radiation Monitoring Team members receive periodic training from Heal th-Safety in emergency response techniques
- +
(emergency plan), instrument use and maintenance, health physics and nuclear safety fundamentals, respiratory protection and DATE N/
2 REVISIQ1 NO.
PAGE 30 CWREf4 REVIS104!
SUPERSEDES: PAGE 30 lENRC APPROVAL REFERENCE l
DATE 5-04-84 REVIS!Q1
BABC00( & WILIDX CGPM, CatERCIAL NUCLEAR REL PLM USNRC LICENSE SNPt-ll68 DOCKET M-1201 IV HEALTH PHYSICS SECTim 15.4 contamination control. Annual evacuation drills are utilized as a training period for the emergency teams.
First aid training l
is given by a qualified instructor and is the standard Red Cross program or equivalent.
Efforts are made to recruit individuals who have had previous training such as military damage control or Civil Defense radiation monitoring.
16.
RECORDS AND REPORTS 4
Records and reports pertaining to Health-Safety activities requiring' l
. formal documentation are maintained and stored in accord with Regulatory Guide 8.7, Occupational Radiation Exposure Records Systems. Supporting documentation and material not appropriately part of Regulatory Guide 8.7 is prepared and stored in a manner, and for a period of time, consistent with good industrial practice.
The provisions for records retention and report submittal are governed by 10 CFR 19, 20, 70, and 71 specifications.
All documentation directly relating to Health-Safety activities is pre-pared by, or is under the administrative control of, the Health-Safety Section.
Vendor generated and supplied data (bioassay, TLD) is incor-porated as part of the Heal'th-Safety record system based on contractual assurance of quality, precision, and adequacy of supporting information.
Information generated by other plant or company components is utilized as appropriate in the Health-Safety doc 0 mentation program. This type of material may be characterized as " supportive" and may include selected l
[
DATE 2-04-87 REVISION No.
2 PAGE 31 L
CURRENT REVISION!
SUPERSEDES: PAGE 31 WNRC APPROVAL MFEENCE DATE 5-04-84 REVISION 1
E S WII.GR NM, QMElEIAL NUClfAR REL PIM l
LENRC LI NSE SNPt-ll68 DOCNET D E l l
IV HEALTH PHYSICS l
16.3 reviewed periodically by the Manager, Quality and Safety and in the course of routine audits provided by other B&W com-ponents.
Record retention requirements are in accord with
16.4 Where applicable, all records are maintained using terminology equivalent to 10 CFR 20. Where because of type of sample or the analytical technique employed, other units are more descrip-tive or useful, Health-Safety may maintain records in the units most appropriato. Typically,' unit terminology will be as noted below:
- All air samples - pCl/mi 2
- Removable surface contamination - OPM/100 cm l
2
, Fixed surface contamination'- OPM/50 cm
- Effluent water samples - pCi/ml
- Environmental water sampics - pCi/ml
- Soil / vegetation samplos - pCi/g
- Bioassay samples in-vivo counting 235 U
urinalysis - OPM/t pgUlt l
f: cal - pgU/samplo nasal smears - OPM/samplo
- Exposure records Rem, mrom, MPCh
- Ponotrating radiation surveys - R, mR, mrom
- Source Icak test - 901 235
- Solid wasto disposal - gU, 9 g
DATE 2-04 87 REVISim No. 2 PAGE 33 CLRRENT REVISICNt SUPERSEDES: PAGE 33 USNRC APPROVAL E FE R NCE 5 04-84 I
IMTE ---
REVISim t
F BABOXX & WILIDX (DFM, GNEHCIAL NlEAR REL PUNT USNRC LICENSE SPM-ll68 D00ET M-E l IV HEALTH PHYSICS 17'.
CAUTION SIGNS, LABELS, AND AREA CONTROL A continued exemption is requested from the labeling and posting require-ments of'10 CFR 20.203(e)(1) and 20.203(f)(1) because of the nature of trir operation.
The intent of these section is met by posting plant entrances with signs incorporating the radiation symbol and the following warning:
CAUTION RADI0 ACTIVE MATERIALS ANY AREA OR CONTAINER WITHIN THIS PLANT MAY CONTAIN RADI0 ACTIVE MATERIAL.
This system has been applied effectively at the CNFP for the past ten, years.
17.1 Personnel access to the plant and supporting buildings is con,
trolled through a guard station which is constantly manned. The plant area is surrounded by a'chathlink fence, and all access points, other than the main gato, are locked when not in use.
- f*
Kev control and other security naasures utilized at the CNFP is
- h*
the rosnonsibility of Facilities and Services.
For purposes of plant and personnel protection ard access control, the CNFP "rostricted arca" is considered to consist of all areas within the perimotor fence.
In specific instancos, CNFP management may modify the restricted area as defined above in order to accon-modato unusual or temporary conditions.
17.2 " Controlled areas" within the CNFP are established as necessary to assist in the protection of personnel or in the control of contamination spread.
Critoria specified in 10 CFR 20.202 DATE 2-04-87 REVISICH NO.
2 PAGE 34 CLRRENf REVISIONI SUPERSEDES: PAGE 34 ur,NRC APPROVE MFEENCE DATE 5 04-84 REVISICN I
BAB000( a WILOR CDFANY, 00PfERCIAL NUCLEAR REL PUM LENRC LICENSE SNPtll68 DOCKET E201 SECTIOi IV HEALTH PHYSICS 17.2 and 20.203 are applied to the determination for the necessity of establishing controlled areas.
Portions of the plant falling within one of the above categories are identified and controlled in accord with 10 CFR 20 requirements.
Postings utilized in accord with the abose are placed so as to be visible from all access points. Additionally, Heal th-Sa fety may require the use of barriers, tapes, etc., to further control access or delentate the extent of the involved area, i
Change areas, stepoff lines and appropriate monitoring equipment are used to control the spread of contamination to uncontrolled l
areas.
Doundariet between controlled and uncontrolled areas are clearly identified and special requirements for access to the area are posted.
A radiation work permit program (RWP) may be instituted by' Health-Safety at any time in order to assure adequato protection, con.
trol, and health physics coverage of personnel working under high, or potentially high, radiation exposure conditions.
Due to the routino nature of plant operations, tho imposition of RWp controls is infrequent and generally relates to special mainto-nance or process development programs.
Safotyrules(industrial, radiological,andnuclear)arepro-minently posted throughout the plant.
Thoso postings are main-MTE 2-04-07 2
REVISION NO.
PACE 35 CLRENT REVIS1(W!
SUPERSEDESI PAGE 35 g gg g 37g s.04-84 I
REYlSION
f l
f BAIK00( a WluDX CDf9W, C0fDCIAL NUClfAR REL PLM USNRC LI NSE SPM-lMS DOCKET M 1 SECTim IV HEALTH PHYSICS
~
17.2 tained by_ Health-Safety based on license requirements and specific plant operating criteria.
18.
EMERGENCY RESPONSE AND CONTROL PROGRAMS 18.1 Criticality Monitoring System A criticality monitoring system based on a series of GM detector; units and a central control panel located in the Health-Safety Offico is installed at the CNFP. GM detector spacing meets, 1
or exceeds, the specifications of 10 CFR 70.
Integral with the detector system is an immediate evacuation alarm system composed of a modulated frequency' generator and speakers or horns positioned throughoutthepignt. Alarm sound levels in all areas requiring immediate evacuation are distinctively audible above niaximum ambient noise levels. Selection of the alarm system was based on noise levels, frequencies, and modulation characteristics under plant operating conditions. The system currently in use has bee'n demonstrated in the course of drills to result in immediate personnel responso.
Sound characteristics of tho evacuation alarm are totally distinct from other audible alarms or signals inuseattheplant(firestron,timoballs),
j At the present timo the monitoring system consists of six mastor dotector units covoring the plant in a manner consistent with therequirementsin10CFR70.24(a)(1)or(a)(2).
Thoso detectors aro located at appropriato distancos Whora necessary to allow for i
2 04 W DATE REVISim No.
2 PAGE 36 CURRE M REVISI M I SUPERSEDESI PAGE 36 LANRC APPROVAL MFEENCE IMTE 5 04 M gygsgm 1
I p
[
BABGXX & WIL(DX CDPM, UNEEIAL NtX1 EAR REL PUE LENRC LICENSE SNPtll68 DOCKET M 1 IV HEALTH PHYSICS SECT!W
- 19. BY-PRODUCT MATERIAL AND SEALED SOURCES 19.1 Encapsulated by-product material and neutron sources may be possessed at CNTP for use in instrument calibration, monitor training, and product evaluation devices such as scanners. Signi-ficant quantities of material are required in order to provide i
exposure or neutron flux rates of sufficient intensity to calibrate "high range" survey instruments and to penetrate high density materialsforgaugingpurpfses.
CNFP llealth-Safety personnel haveadequatetrainingand,experienceinhealthphysicsand) source handling to insuro utilization of such sources (reference SNM-1168,Section V, minimum qualifications).
l The following controls are in effect to insure adequate radiological safety:
a.
Authorized users of sources intended for training and instru-ment calibration are limited to qualified icalth-Safety and plant instrument technicians.
In cases whern other personnel may be involved in uso of those sources, as in training exorcisos, the operation is directly supervised by a qualified representathe of Iloalth Safety l
b.
Sources intended for use in manufacturing / quality control devices will be operated only by personnel designated by plant supervision and instructed in safo operating proco-duros by lloalth Safety personnel.
1 MTE 2 04 117 REVISION No.
2 PAGE 39 CURENf REVISION SUPENSEDESI PACE 39 USNRC APPROVAL. MFE M NCE i
mig s 04 n4 REYlSION I
s. -
BABQXX & WILCDX C0WANY, C0m3CIAL NUCLEAR REL PIM l
LENRC LICENSE SNM-ll68 DOCKET E 1201
_ SECTIO 4 IV HEALTH PHYSICS 19 c.
When not in use, sources will be stored in approved, labeled h.1 and locked shields in a designated area. Source container
'shleiding shall be sufficient to minimize the exposure rate to personnel working in the vicinity of the container to less than 2 mrem /hr.
In general, storage requirements will be guided by the conditions outlined in " Safe Handling of Radio-isotopes" (IAEA Safety Series, No.1 Section 4,1962) and NBS Handbook 73(1960).
5 d.
Adequate portable survey instrumentation is presently ayallable on site.
c.
All employees of CNFP routinely wear personnel monitoring devices.
In addition, self-reading dosimeters, neutron dosimeters, and extremity dosimetry are required as deemed necessary by Health-Safety.
Routine use of remote handling devices minimizes extremity exposure. Wherever practicable, automated handling and process equipment is utilized.
f.
Leak tests are conducted on all sources ininediately upon receipt and at least semi-annually thereaf ter and are performed in accord with the guides outlined in NBS Handbook 73(1960 Section 7.6, " Radioactive Source Leakage & Contami-nation") or by an equally effective method.
In the event that a leaking source is discovered it shall bo packaged so as to prevent further contamination spread and arrangements IMit 2 04-81 pgygggg;no, 2
PAG 40 CUMt(f f(VISIult SU'EldCDCSI PAGE 40 U;flRC APPROVAL FCfEREllCE IMTE __ f"04-84 Rtyistal 1
BAIKDO( a WILC0X CGPM, stERCIN. NUCLEAR RB. PIM USNRC LI NSE SNPt-ll68 DOCNET & l201 SECT!W IV HEALTH PHYSICS 20.1 d.
Sampling media available at selected site, e.
Chemical and physical characteristics of potential con-taminants(insolubleuraniumoxides,etc.).
f.
Potential impact from neighboring nuclear facilities.
The sample results are maintained on file by Health-Safety.
Figure 4 shows results of the environmental sampling program for the period 1977-1980. flormal data fluctuations are noted with no discernable trends identified.
t l
I o I MTE 2-04-07' E VIS 44 NO.
2 PAGE 43 i
C W E NT E Vis104:
p GUPERSEDEs PAoE 43 USNRC MA'. ERENCE MTE 5 04-84 I
}
REVISION
BABOXX & WluDX QHW, GNERCIAL NUCLEAR REL PUNT 1
USNRC LIGNSE SNPt-ll68 DOCKET M 1
[
SECT!W IV HEALTH PHYSICS APPENDIX 1 PAGE 10 t
l NEUTRON EMITTING SEALED SOURCES i
I It is believed that neutron activation of scanned rods will result in 7
an insignificant increase in the penetrating radiation levels normally encountered with unexposed fuel rods. During the initial phase of scanning, however, a confirming measurement program will be undertaken. Sources are i
l leak tested upon receipt at CNFP and at least every six months thereafter (unlessthesourceisinstorage). Leak tests will be conducted by Health-Safety using remote handling techniques and will be compatible with NBS Handbook 73 Section 7,6, or by an equally effective method. Measurement i
techniques are capable of detecting 0.005 microcurie on the test sample.
When practicable, leak tests will be conducted without removing the source from its shielding uni. Neutron survey instrumentation is available on-site.
Personnel dosimetric devices,.such as film and self-reading chambers, appro-priate for evaluating neutron exposure are utilized as determined to be necessary by Health-Safety.
Operating personnel are trained in safe practicos and health physics requirements prior ta operating the scanner.
Documentation of such training is maintained in the Health-Safety Office.
In-plant operating procedures require that Health-Safety be notitled prior to undertaking any maintenance or other activities that may involve access to, or modification of the source shield.
In addition, all source handling is under the supervision of qualified Health-Safety personnel. Written procedures provide guidance for normal use of the sources and define the controls to be applied in the event of lenknoo or other non routino condition.
REVIS! W No.
2 PAE k f
IATE 2-04-87
__CLERENT REVISimi gypcgstgg PAcg Appendix 1. Page 10
BABC0CK a WILC0X C0WAW, CafERCIAL NUClfA REL PlM USNRC LICENSE SNft-ll68 DOCKET 70-1201 DUMS SECTION 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 0 enrichment of 4.05% 235 Chemical form to be uranium oxide.
[
U 235 I
3.2 5,000 kilograms of 0 enriched as UF6(max.5.00% enrichment) for storage only.
3.3 20,000 kil,ograms of uranium as depleted our source material in powder or. pellet form and composed of uranilum oxides.
l i
3.4 3,000,000'1bs. uranium as natural UF f r s'torage only.
6 3.5 2,000,000 lbs. of naturally enriched uranium in powder or pellet fonn and composed of uranium oxides for stofage only.
3.6 Up to 51 curies of encapsulated by-product material contained in one or more sealed sources. Atomic numbers 3 to 83 inclusive.
3.7 By-product material in contamination quantities on returned, 1
unirradiated' fuel components.
3.8 Up to 6.0 grams of encapsulated plutonium contained in one or i
?
more sealed sources.
3.9 Up to 3.0 milligrams of cali'fornium-252 contained in one or more sealed sources.
235 3.10 Up to 100 grams 0 without limit on chemical, physical, or isotopic composition, for analytical purposes, f
3.11 Up to 0.5 curies of By product material as contamination on/within equipment, and/or as waste.
2' OI DATE REVIS10ilNO, 2
PAGE CURRENT REVIS10fl!
SUPERSEDES PAGE 3
USNRC APPROVAL REFERENCE 2
DATE 5 28 85 pgygggggg L
l.
S.
I j
j BAB000( & WilmX QN, QMIAL NUQEAR RB. PLMT USNRC LICENSE SNPt-1168 DOCKET M - 3 1 SECTim V CONDITIONS I
I 5.0 Administretive l
The following feature of administration provide control to assure nuclear and radiation safety.
5.1 Management shall be responsible to assure the safety of the operation and compliance with license conditions. Control shall be established by designation of responsibilities to qualified individuals, review and approval of Health-Safety procedures designed'to 1
assure continuing safety and compliance, review of progFam effectiveil I
ness and assuring correction of non-conforming conditions.
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'5. 2 Operaf. tonal Area Supirvision
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Operational area supervision inthat supervision directly responsibli for the control of materials, personnel, equipment, and activities in specific areas.
Those responsibilities include assuring that...
approved control procedures developed with Health-Safety i
shall be available in writing to operators and other concerned personnel and shall be adhered to.
I 5.2.1 Minimum qualifications of operational area supervisiun i
shall include:
1 1
(a) A high school education or equivalent and a
{
minimum of 6 months experience in the nucicar 1
industry.
Experience shall include the practical I
DATE 2-04-87 REVISION NO,'
2 PAGE 6
ClRRENf REVISION!
8EN8%83 WNRC APPROVAL REFERENCE
' 1 DATE REVISION L
Ji
[
c.
BAB000( a WILOR (DPANY, QMDCIAL NUCLEAR REL PLM LENRC LICENSE SfM-ll68 DOCKET M-El V CONDITIONS SECTim 5.0 Administrative (continued) 5.2.1 (a) application of criticality control techniques i
and a familiarity with the applicable specific limitations imposed on CNFP operations.
(b) Sufficient experience of industrial supervisory nature for recognition of the responsibilities
{
of the position and achievement of the required control.
i 5.3 The Health-Safety Section'shall De responsiule to in-terpret the license conditions, provide monitoring facilities, develop safe operation guidelines, maintain training programs, and review and approve operating procedures to assure safe opera-
,I tion and license compliance.
These respansibilities include nuclear safety and radiation safety with the approval authority limited to authorized specific or general license conditions.
The Health Physicist or his qualified designee shall be respons1 Die
- 4*
to provide management with assurance of the effectiveness of the safet.
program by maintaining an audit program that includes periodic inspection of controls and operations, reports to management, follow-up of non-conforming conditions and necessary documentation.
(See Audits Part 6,6,Section V),
i DATE 2-04-87 REVISION W.
2 PE 7
CLBRENT REVI5ICN SUPERSEDES: PAoE 7
m mg arEm 5 04-84 l
DATE REVISIM
BABC00( & WILCDX CTPAi#, CORBCIAL NUCLEAR REL PLAY USNRC UCENSE SNPt-ll68 DOCKET F1201 V
CONDITIONS SECTICN l
5.0 ' Administrative (continued) 5.3 The Health-Safety section shall not be directly responsible for the performance of manufacturing operations.
5.3.1 The Health-Safety'Section shall include a person who l
shall. act as the plant Health Physicist. This person shall have a Bachelor's Degree in Science or Engineer-ing or equivalent.
A minimum of 5 years experience is required along with sufficient formal training that provides an understand-ing of the health physics and nuclear safety hazards involved at the CNFP.
This person must have the ability to evaluate the poten-tial for exceeding authorized control limits. The backup for the plant Health Physicist shall have the same mini-mum qualifications..__
~5.3.2 The Health-Safety Leader shall have 'a nigh school education or equivalent, and a minimum of one year experience in responsible positions or three years experience in radiation safety which would develop an understanding of nuclear and radiation safety. The Health-Safety Leader can be the backup to the Health Physicist if $e meets the minimum qualifications for the Health Physicist.
5.3.3 The manager to whom-the section reports shall have a. bachelor's degree, or equivalent, and a minimum of five years experience in responsible positions which would develop an understanding of nuclear and radiation safety. Such experience shall be of a nature which demonstrates to the Plant Manager sufficient judgement and capability to establish and maintain an effective nuclear criticality and radiation safety program for the activities authorized by license.
5.4 Independent Auditors shall be responsible to ascertain the over-all performance of the plant functions in providing adequate con-trols, surveillance, and followup to assure safety and license compliance. This shall be accomplished by periodic inspection of the facilities and records resulting in a written report to the Plant Manager.
5.4.1 Oualifications of the independent auditors shall include DATE 2-04-87 REVISION No.
1 PAGE 8
CURRENT REVISION:
SUPERSEDESI PAGE O
WNRC APPROVAL REFEREllCE 0
DATE 12 6-82 REVIS!Ctl
BABC0CK a WILC0X C0f1PA1Y, C0fPERCIAL NUCLEAR REL PLM USNRC LICENSE SNft-ll68' DOCKER 70-1201 SECTION V CONDITIONS 6.0 General Specifications - Implementation of the technical specifications will be accomplished through application of the following general specifications.
6.1 Control Program Specifications and design criteria for purchased or locally fabricated equipment where nuclear and radiological safety considerations are involved shall be approved by. a knowledgeable representative of Health-Safety. Before being released l
for production operation, new equipment shall be tested to assure that safety specifications are satisfied. Safe geometry equipment shall be measured by a knowledgea}ble person to ascertain that it is of proper dimensions before it is put into service. Where operational safety is based wholly or in part on the use of electrical or. mechanical interlocks, the proper functioning of interlocks shall be verified upon installation and on an annual basis thereafter. Routine plant inspections place added emphasis on new operations. No equipment is used after being removed from service until an equipment checkout for continued effoctiveness of safety related para-I moters is performed.
Radiation instruments, shall be calibrated at the frequency indicated in Section V, Part 8.3.4.
Calibration shall be performed by Health-Safety personnel or other f4KC licensco fa r.il i ti as.
DATE 2-04-87 REVIS10fl flo.
3 PAGE 11 CURREllT REVIS10fl!
SUPERSEDESI PAGE 11 USilRC APPROVAL REFEREilCE DATE 2-0_4-85 REVISI0t; 2
I l
BABC00( & WILG)X CW#ff, UNERCIM. NUCLEAR REL PIM USNRC LICENSE SNft-ll68 DOCKET 70-1201 V CONDITIONS SECTION 6.0 General Specifications (continued) 6.1 Ventilation, containment, and air cleaning equipment shall be
~
routinely inspected by Health-Safety personnel to assure continued _._
effectiveness and c,ompliance with. license specifications.
~
These inspections shall be recorded and a periodic review shall be per formed by the Health-Safety Leader. Any unusual circuiitstances shall be broughs 'to'the attenti6n~~of the Health Physicist
~
~
and/or the Xinager, Quality _and Sa.fety.
~
The Healtil-Safety' Leader or_oualified designee _as appointed by Manager, Quality and Safety shall be responsib1e for the c_ontrol of the air sampling and contamination survey pr.ogram, and evaluates ~
daily sample results. Quarterly air sample program records shall be I
reviewed by the Health Physicist and/or the Manaaor, Ouality and Safety.
l Instances of inadequate control of contamination or air effluent levels, and of equipment operation not in accordance 1
with established nuclear and ' radiation safety and license parameters
]
shal'1 be reviewed by either the Health Physicist, and/or the Manager, Quality a,nd Safety who may order the operation suspended if timely compliance cannot be assured. Disciplinary action can be recommended' if warranted.
6.1.1 Safety Review Board A Safety Review Board shall be established to review the following as a minimum on a quarterly basis:
IMTE-2-04-87 3
I REVISION NO.
PAGE CtRRENT REVISION:
k SUPERSEDES: PAGE 12 USNRC APPROVAL REFERENCE 2-04-85 DATE REVISICN
BABC0(X & WILCDX C&PAif(, C&fBCIAL NUOfAR REL PIM USNRC LICENSE Snit-3168 DOCKET E -1201 SECTION V CONDITIONS 6.0 General Specifications (continued) 6.1.1 Safety Review Board
'new or revised facilities
' analysis of equipment and processes. involving radioactive materials
'the continuing effectiveness of established controls and safeguards
' maintenance of ALARA criteria (review of quarterly air sample averages, review of surface contamination surveys)
' safety-related audit findings
'other items (such as abnormal occurrences) that Safety Review Board members wish to discuss i
The Safety Review Board Chairman or his qualified designee shall be directly responsible to the Plant Manager for the prc perhonductoftheSafetyReviewBoard.ThePlantManagershal be kept informed in writing of Safety Review Board action.
The Board shall be chaired by the Manager, Quality.and Safety,-.tand the permanent membership of the Board shall consist of representativesof CNFP operational and technical mana'gement, specified by procedure, which is approved by Plant Management personnel. Technical representatives of consulting organizations shal.1 be included as necessary (LRC, NuclearCriticaiitySafetyGroup).
~
Board meetings may be convened at the discretion of the Safety Review Board Chairman or his qualified designee, but shall be held at least quarterly. The Safety Review Board Chairman or his qualified designee shall decide whether or not the necessary disciplines are present' during a board meeting to evaluate the item (s) under consideration. There shall be a minimum of 4 Safety Review Board members present during a board meeting.
i
~2-04-87 ~
13 DATE REVISION NO.
3 PAGE CtRRENT REVISION:
SUPERSEDES: PAGE 13 m yeam u m 2-04-85 2
DATE REVISICri.
- un ~ _.;
p BABGXX & WILCDX CTPN#, CGfERCIAL NUCIEAR REL PLMT 1
USNRC LICENSE SNPt-ll68 DOCKET E 1201 V CONDITIONS SECTION i
6.0 General Specifications (continued)
)l 6.1'.1 Safety Review Board The Safety Review Board Chairman or his qualified designee reviews all requests for changes in process and equipment which involve radioactive material.and determines if Board review is necessary.
In the case of minor change where existing safety practice remains the same, the Safety Review Board Chairman or his qualified designee may determine that Board review is not necessary. Safety Review Board members shall be kept appraised of actions taken.by the Safety Review Board Chairnian or his qualified designee on such minor changes.
Where other than minor changes are involved, the Safety Review Board review and approval process shall be con-ductedinaccordwithPart.7.1.4oftdissection.
Records of Safety Review Board proceedings, including
^
supporting calculations and approvals, s' hall be retained
~
for at least six months after the completion or termina-tion of the subject activity.
6.1.2 Records Plant alterations or additions, abnormal occurrences, events associated with radioactive releases, criticalit'y analyses, audits, inspections, instrument calibration, Al. ARA findings, employee training.and retraining, personnel exposures, routine radiation surveys, and environmental surveys shall be maintained on file for a minimum of 2 years or as other-wise required by federal regulation or other license con-dition, for review by B&W management and regulatory agencies.
i j
6.2 Personnel Training Initial indoctrination of employees into nuclear and radiological safety shall be the responsibility of Health'-Safety and shall
~~
DATE 2-04-87 REVISION NO.
2 PAGE 14 j
CtRRENT REVISION:
l.
SUPERSEDES: PAGE 14 USNRC APPROVAL REFERENCE 5-04-84 1
l DATE REVISIQi _
~
BABC00( & WILCDX CQPMY, CalERCIAL NUCLEAR REL PLAIT USNRC LICENSE SNM-ll68 DOCKET 70-1201 l
SECTIQ1 V CONDITIONS 6.'0 General Specifications (continued) 6.2 Personnel Training conform with 10 CFR 19.
Initial indoctrinal..cn training shall, as a minimum, include the following topics:
' license conditions
' federal regulations loperatingprocedures radiation safety lnuclearsafety emergency procedure The extent and depth of the training, relative to the detailed aspects of the health physics and nuclear safety programs, is dependent on the employee's job assignment and potential exposur6 to radioactive materials as determined by Health-Safety.
The initial indoctrination training shall be reinforced (as appro-priate to the individual's job assignment) by the employee's imme-diate supervisor or his designee with respect to individual unit safety requirements, location of emergency exits, contamination control techniques, specific local controls, and operating proce-dures, prior to the employee being released to operate independently.
The employee's immediate supervisor shall complete a new employee training verification form prior to allowing tne employee to operate
+
independently.
I I
A continuing safety training program shall be conducted by Health-Saf~ety to the extent necessary to assure the maintenance of acceptable safety practices.
Such training may be conducted on an individual or group basis. The content of retraining programs may be varied by Health-Safety but will include radiolo-I gical and nuclear safety as a minimum.
Emphasis is placed on new or revised safety criteria or areas in need of reinforcement. A formal retraining of radiation workers shall be conducted at least annually.
Documentation of formal training and retraining shall be maintained by Health-Safety.
DATE
~ 2-64'-57 REVISIO4 NO.
2.
PAGE 15 CURRENT REVISION:
}.
SUPERSEDES: PAGE 15 USNRC APPROVAL REFERENCE j
I DATE 5-04-84 pgt3;g;
v
[
[
BABC00( & WILOR CTPANY, UNERCIAL NUQfAR REL PUWF i
USNRC LI NSESNM-ll68 DOCKET h ]2D1 SECTION
~
l 6.0 General Specifications (continued) 6.2 The Manager, Quality an'd Safety shall be responsib'le to assure ~
~
~
~ ~
j that _ personnel assigned _to_ Health-Safety _are_pr_operly I
trained. The extent and depth of the training is based on' the specific job assignment involved. Health-Safety monitoring personnel shall receive a combination of formal and "on-the-job" training such that they can successfully demonstrate their proficiency in basic nuclear and radiation physics monitoring and control techniques and regulatory requirements before being allowed to function with-out direct oversight.
.t l
Members of the CNFP emergency monitoring team shall be trained by Health-Safety in the proper technique of accident control.
l 6.3 Postings
]
Nuclear safety postings approved by Health-Safety shall be maintained specifying nuclear safety parameters that are subject
]
to procedural controls.
3
- l Area postings may be used for those parts of the process where li nuclear safety is maintained by means of " area-wide" require-ments.
Operations for which specific (dedicated) controls are q
lq applicable shall be individually posted.
v
['
Local safety rules approved by Heilth;Sifetf providing personnel l
and supervision with specific directions essential to assuring l
u
~'04-87 REVISION NO.
2 PAGE 16 2-'
~
1, DATE I:
CLERENT REVISION:
SUPERSEDES: PAGE 16 USNRC APPROVAL REFERENCE
]
DATE 5-04-84 REVISION 1
4 BABC00( a WILG)X C&P#ff, CutERCIAL NUClfAR REL PLM USNRC LI NSE SNPt-ll68 DOCKET D E l V CONDITIONS SECTIm 6.0 General Specifications (continued) 6.5 consideration involves SNM or radioactive materials, specific 3
written approval by the Manager, Quality and Safety or his designee shall be required prior to implementation of the procedure. Applicable procedures shall be available in the work area and adherence to procedure shall be required of all personnel.
~
Procedures for operations where nuclear and radiological safety are involved shall include specific reference to applicable safety re-qu'irements. Procedure and format shall be such that operations are cl'early detailid'and specific directions are provided for operaticn under both normal and abnormal conditions Deviation from written l
procedures for the handling of SNM shall be approved by the Managor, Quality and Safety, or his qualified designee.
Procedural control o'f activities at the CNFP are catacorized as follows:
- Procedures developed by Health-Safety specifying the method by which safety related functions are to be accom-plished. Such procedures may be for internal Health-Safety use or may be intended for general distribution to affected indivi-duals within other components. As a minimum, Health-Safety Proce-
~
P dures shall be approved in writing by the Manager, Quality and as well'as appr' ved bf affected members of plant
~
o Sifety
' manageinetit. ~
~ ~ '
~~~- ~ ~ ~ - ~ ~ ~ ~ ~
~ ~ ~ ~
~
~ ~ ~
T DATE
~ 604-87 REVISION NO.
3 PAGE 18 CLERENT REVISION:
l j{
SUPERSEDES: PAGE USNRC APPROVAL REFERENCE l'
DATE 2-04-85 REVISIm 2
li
BAB00CK & WIL(DX C&PANY, CutERCIAL NUClfAR REL PLAE USNRC UCENSE SNPt-ll68 DOCKET M.1201 V CONDITIONS SECTICN 6.0 General Specifications (continued)
Nuclear Materials Control procedures provide techniques for the 6.5 accountability and measurement of SNM. As a minimum, sucn pro-cedures shall be approved in writing by the Manager,. Quality l
and Safety and the Manager, Production & Materials Control.
i.
- Procedures from other plant groups where nuclear or radio-l logical safety,11 cense conditions, or regulatory require-ments are involved require prior approval by the Manager, Quality and Safety as well as approval by affected members of plant management.
l Revised procedures shall be' subject to approval in the same manner as new procedures. Health-Safety
' procedures shall be reviewed at least annually for technical correctness and applicability.
l l
Procedure distribution and control shall be the responsibility of j
plant supervision.
6.6 Audits An internal audit program shall be maintained to provide assurance that. plant activities are I
conducted safely and in accord with license specifications.
3 e ***
The Manager, Quality a'nd Safety ihill be responsTDTe~to j;
assure that the audit program is conducted effectively.
3 IMTE 2-04-87 REVISION NO.
PAGE 19 9
]
CLERENT REVISION:
1-SUPERSEDES: PAGE 19 LENRC APPROVAL REFERENCE f
IRTE 2-04-85 2
REVISION a
BABOXX & WILG)X COPANY, QNERCIAL NUCLEAR REL PIAT USNRC U NSE SNPt-ll68 DOCKET k.1201 SECTI(N V
CONDITIONS 6.0 General Specifications (continued) 6.6 Health-Safety _ personnel shall conduct, at least weekly, a formal audit of plant status relative to nuclear and radiolo-gical safety, except during plant shutdown of a week or longer.
At the discretion of Health-Safety, the audit may consist of an indepth evaluation of a specific area or may be of a generalized nature providing an over-view of total plant activities. Audit results shall be documented, reported to plant management and supervision as appropriate, and will be maintained on file by Health-Safety for at least 2 years.
~
~~
Health-Safety audits shal1 b'e conducted by personnel technically qualified in operational nuclear and radiological safety and in the application of license specifications.
Health-Safety persor)nel shall, as part of their routine duties, conduct informal daily audits of plant activities.
Independent auditors shall conduct inspections as follows
- nuclear safety
- quarterly
- health physics
- quarterly All formal (quarterly) nuclear safety and health physics audits shall be conducted in accordance with written instructions or
),
procedures.
The audit program shall include physical inspections and records reviews for the industrial, nuclear, and radiological safety elements of plant activities inclu' ding:
- Effectiveness of procedural controls impacting on operational safety parameters.
DATE 2-O'4-87 REVISION NO.
3 PAGE 20 CLRRENT REVISION:
SUPERSEDES: PAsE 20 USNRC APPROVAL REFEREN &
2 DATE 2-04-85 REVISION L
f.
1 l....
l MBOXX & WIUDX QWANY, QMEEIAL NUQEAR REL PLM j
USNRC UCENSE SNM-ll68 DOCKET M-1201 i
y-SECTim V
CONDITIONS 6.0 ' General Specifications (continued) 6.6
- Audit of operating records, where such re' cords provide a means i
of verifying procedural compliance with safety specifications.
- Periodic review and evaluation of contamination survey data.
An annual ALARA report shall be submitted to the Safety Review Board on employee exposures and effluent release data.
A copy of the report shall be sent to the Plant Manager.
Independent auditors' reports shall be submitted to the Plant Manager.
The' Manager, Quality and Safety shall review the audit reports as tney are submitted. The audit report shall include any audit findings or recommendations. Actions taken as a result of. audit findings shall be documented.
1 Safety-related audit findings are reviewed by the Safety Review Board.
6.7 Reporting Unusual events requiring reporting under 10 CFR shall be investi-gated, with results reported to plant management and NRC.
Events not otherwise requiring a report may be reported to NRC based on potential public or media involvement, etc., in order to keep NRC appraised of the situation.
l DATE 2-04-87 2
REVISION NO.
PAGE 21 l~
CLRRENT REVISION:
[
SUPERSEDES: PAGE 21 USNRC APPROVAL REFERENCE i
DATE 5~-04 "4 I
REVISIm
2
(
.e
. e BAIKDO( & WIL(DX CTPANY, CTPERCIAL NUCifAR REL PIM i
USNRC LICENSE SNPt-ll68 DOCKET M-E l l
V CONDITIONS t
l SECTIG4 I
I 7.0 Nuclear Safety - Technical Specifications (continued) l s.
j 7.1.2 e.
The solid angle criteria applied in accord with TID-7016 (Rev. 2) for accumulations having k-eff l'
j
< 0.8.
j 7.1.2.1 The Safety Review Board Chairman or his qualified designee, with the concurrence of the LRC Nuclear Criticality Safety Group, shall determine which arrays are more reactive than those used as a basis for a, b, and c or are best' represented as slabs for nuclear interaction purposes.
In these cases, the interaction acceptance cri-teriashall be evaluated on an individual basis by the LRC Nuclear Criticality Safety Group or itshall be the equivalent of eight inches (20.3 cm) of water or as defined in 7.1.2(d) or (e).
7.1.3 Isotopic enrichment of SNMshall be verified by shipper's documents with added assurance by Quality and li Safety overchecks.
7.1.4 Modification of product or process involving SNM may be made without license amendment provided such changes are controlled as described in this section and where the license conditions specified in this part are not vinlatoi.
DATE 2-04-87 REVISION NO. 2 PAGE 23 l
CtRRENT REVISION:
SUPERSEDES: PAsE 23 LENRC APPROVAL REFERENCE 1
DATE 2-04-85 REVISIG1
i l
BABOXX & WILGR C&PANY, C&tERCIAL NUCLEAR REL PLAY USNRC LI NSE SNM-ll68 DOCKET 70-1201 V CONDITIONS SECTIO 4 7.0 Nuclear Safety - Technical Specifications (continued) 7.2 discussed in Section III and may be considered typical of material
)
j pr'ocessed.
7.2.1 Fuel Pellets Composition: Uranium 0xide Size:
.300" to.600" diameter inclusive 235 Enrichment: Maximum 4.05%
U NOTE: An increase from 4.00 to 4.05 w/o does not significantly affect nuclear saf?ty calculations based on 4 w/o material.
7.3 Fuel Pellet Receiving and Temporary. Storage i
A single shipment of pellets may be stored in the shipping containers in an array no more reactive'than as received pending. transfer to
~
planned storage facilities. Nuclear interaction between the shipment and other SNM will be as specified in 7.1.2.
7.3.1 The containers shall be examined for transit damage, and He'alth-Safety notified if damage is fourid.
Health-Safety
~
shall examine the damaged containers for evidence of water entrainment and other conditions that might constitute a hazard.
Damaged containers shall be opened one at a time and as the material is removed, itshall be imediately 1
placed into storage within safe geometry slabs or 850 grams U235 accumulations in accord with appropriate license con-ditions for storage.
DATE Z-W-@
REVISIQ1 NO.
2 PAGE 28 CtRRENT REVISION:
SUPERSEDES: PAGE 28 LENRC APPROVAL REFERENCE DATE 5-04-84 REVISIQ1 1
B20XX & WIL(DX COW #ff, COERCIAL NUCifAR REL PIM USNRC LICENSE SNM.ll68 DOCKET 70.1201 SECTIQi 'l CONDITIONS _
7.0 Nuclear Safety - Technical Specifications (continued) 7.5.2 Only a single slab thickness will be permitted on any one shelf.
7.5.3 The vault is separated from other SNM storage and pro-cessing areas by eight inch thick concrete walls, i
7.5.4 Storage and handling of materials in the vault shall be 1
controlled based on criter,ia specified by Health-Safety per-4 sonnel. Enrichment determination and selection of proper slab thickness shall be'made utilizing appropriate records or test data.
f:
7.6 Fuel Pellet Handling and Storage l
Fuel pellet handling (following release from the pellet handling area) may involve such operations as fuel rod loading, and storage of packaged but unciad fuel pellets in areas other than the vault.
Fuel pellets shall be handled in accumulations limited to thickness by enrichment as follows:
l 235U Enrichment Maximum Thickness (5)
(in. )
ij
< 2.5 5.4
> 2.5 < 3.0 4.8 l
> 3.0 < 3.5 4.4 2
> 3.5 < 4.05 4.0 t
DATE 2-04-87 REVISIQ1 NO.
2 PAGE 31 CLERENT REVIS!Q4:
)-
SUPERSEDES: PAGE 51 LENRC APPROVAL REFERENCE i
DATE 2-04-85 I
REVISIQ1 4
BABGXX a WILG)X C&PANY, CGtBCIAL NUCifAR REL PlAff USNRC UCENSE SNM-1168 DOCKET E1201-V CONDITIONS SECTION l
8.'O Technical Specifications - Radiation Safety (continued) 8.1.1
-c.
The following program'shall be instituted to assure that airborne releases to uncontrolled areas are maintained
.as low as, reasonably achievable.
l
=--
' Quarterly Average - % of 10 CFR 20 g
Appendix 8. Table 2-a LIMIT ACTION
_ _10% of MPC
- None required.
j I
11 - 20%
- Conduct investigation of
{
system and correct if possible, i
(No Action required for end
?
weld operation or end cap 5 removalarea).
21 - 75%
- Visually inspect system. Issoon as practical, conduct efficiency I
test. Detertpine and correct cause.
l (This action performed: for the end weld operation area or end cap j
removalareaat>50%MPC).
l
> 751
- Conduct irmnedtate investiga. tion ta i
determine and correct problem in 1
ventilation system. Maintain addi-I tional Health-safety surveillance j
.i of system to monitor contamination levels until problem is corrected.
> 100%
- If all engineering efforts are un-successful in lowering the %MPC to acceptable levels then the operation 4
j shall be shutdown or moved to the 4
controlled, area.
Health-Safety shall maintain records of investiga-tions and actions resulting therefrom.
a i
d.
its daughters) pha radioactivity (excluding radon and If the gross al l
in planned gaseous effluents discharges exceeds 10 uCi/ cal. qtr., a written report shall
'j be submitted to NMSS and the Regional Office of the Com-mission within 30 days, identifying the cause for exceed-ing the limit, and corrective actions to reduce release
)
rates.
If the parameters important to a dose assessment change such that the parameters no longer represent boundary q
conditions, report shall be submitted within 30 days
,j which describes the changes in parameters and includes an estimate of the resultant change in dose commitment.
(Ref: Order to Hodify License, Jan. 28,1980).
DATE
-~2-04-07
~~
REVISION'NO.
3 PAGE d2 '
CURRENT REVISION:
SUPERSEDES: PAGE 42 USNRC APPROVAL REFERENCE 2
DATF
.2-04-85 ggygsgm
BABC00( & WIL(DX CGPANY, UNEEIAL NUCLEAR REL PIAff USNRC LICENSE SNPt-ll68 DOCKET 70-21 SECTION V CONDITIONS 8.0 Technical Specifications - Radiation Safety (continued) 8.1.2 Po.tentially contaminated liquid effluents shall be controlled through a retention tank system with.
dilution and mixing capabilities and shall be evaluated for compliance with 10 CFR 20, Appendix B limits prior to release to unrestricted areas. The following actions, at the contamination levels indicated, shall be undertaken in order to maintain contaminated liquid effluent re-leases as low as practicable:
LIQUID EFFLUENTS
% 10 CFR 20 l
App. B. "MPC" Action
< 20%
No action required.
21 - 75%
Individual releases authorized by Manager, Quality and Safety or his alternate.
> 75%
' Discharge prohibited. Effluent routed for further treatment or disposal.
llealth-Safety shall maintain records of investiaations and actions resulting therefrom.
a.
Retention tanks shallbe inspected monthly for sludge accumulation.
8.1.3 The following parameters are established for determining if waste or excess materials and equipment may be disposed of in routine industrial fashion.
Item (d)
MTE 2104-87' 3
43 REVISION NO.
PAGE CLRRENT REVISION:
SUPERSEDES: PAGE 64 MTE 2-04-85 REVISION 2
i
BABOXX & WIL(DX C&PANY, CutERCIAL NUQfAR REL Pl#ff USNRC LICENSE SNM-ll68 DOCKET 70-3201 V CONDITIONS SECTION 8.0 Technical Specifications - Radiation Safety (continued) 8.2.2 Pressure differential shall be monitored'by manometers or equivalent devices. Minimum face velocities for hoods and similar enclosures shall be 100 LFM whenever hood work in-volving dispersible licensed material is being performed.
Air velocity surveys shall be conducted using heated thermocouple anemometers or equivalent. Higher velocities may be required, based on flealth-Safety survey data.
1.
Glovebox negat.ive pressures shall be monitored weekly, except during plant shutdown of a week.or longer.
- 2. Face velocities shall be measured weekly, except during plant shutdown of a week or longer.
" Elephant' trunk" drops shall be used as required for i
maintenance or non-routine activities requiring ex-haust ventilation and where other, more permanent types of containment are not practicable.
Except as noted above, elephant trunks shall not be q
used as a routine control measure without the specific I
approval of Healt'h-Safety. Minimum velocity j
at the point of entrance to " elephant trunk" drops i
1 in the pelletizing area shall be 1300 LFM, i
]
i l
EATE 2-04-8/
REVISIQ1 NO.
3 PAGE 49
- l CURRENT REV1SION:
SUPERSEDES: PAGE 70 LENRC APPROVAL REFEREilCE 2
h DATE 2-04-85 ggyi3ga;
BABC00( a WILG)X COMNY, 00PPERCIAL NUDIAR REL PIM
~
~
LENRC L! CENSE SNIFll68 DOCKET M.1201
~
SECTim V CONDITinN9 8.0 Technical Specifications - Radiation Safety (continued) 8.2.2 andshall be measured weekly when the area is in operation.
8.2.3 Air Sampling In order to verify the adequacy of the ventilation and containment systems, air sampling technique (s) shall be employed. Air samplers shall be positioned at work stations based on evaluation of smoke tests, special air samples, and operator working position. Based on operational status and/or.
exposure potential, air samples shall be; collected after each shift..The air samples shall be analyzed to evaluate airborne levels and assign worker exposures.
General' area air samples'shall be collected and analyzed as stated in the preceding paragraph.
t Upon initiation of new operations, non-repetitive opera-tions, or operations modified such that previous airborne contamination levels may be effected, ' Health-Safety sha'11 verify that satisfactory control is being maintained by means l
of the air sanpling techniques stated above. The scope and duration of such special programs shall be determined
~
by Health-Safety based on good health physics pr'actice.
p DATE
'2-04-87 REVIS! W NO.
3 PAGE 50 CLRRENT REVISION:
p.
SUPERSEDES: PAGE 71 USNRC APPROVAL REFEREN h
DATE 2-04-85 REVISim 2
i
BAB000( a WILIDX CDP #f(, CutERCIAL NUCEAR REL PLM USNRC Li NSE SP#tll68 DOCKET E 1201 SECTim V CONDITIONS 8.0 Technical Specifications - Radiation Safety 8.2.3 The following action points shall apply.to the routine work station air sampling program:
PERSONNEL EXPOSURE Quarterly % MPC-Average Action
___25 %
No action required.
> 25%, < 50%
Report to Manager, Quality and __
SafeL y or designee.
t.
Evaluate op,eration and containment.
Increase ai,r sample frequency if indicated.,
> 50%, < 75%
Report to Manager, Quality and Safety. Take steps necessary
~
to lower airborne activity to acceptable range.
i
> 75%
Notify Manager, Quality and Safety.
f, Terminate operation if > 100
~
MPC, Modify or install air capture devices. Increase air sample freauenc:
If any one sample. measures 100% MPC, the location and occurrence shall be.investicated.
Health-Safety shall' mainUin records 'of lnvestigations
~
~
and corrective actions taken.
The action levels do not apply to non-routine operations con-ducted with the cognizance' of Health-Safity, and iri~ accord."'
~
with specific contamination control measures (for example, certain maintenance activities).
4 MTE Z-04-6/
REVISION NO.
PAGE 51 CLRRENT REVISION:
SUPERSEDES: Pace 72 WNRC NE REFERENCE 3
i MTE 2-04-85 REVISim 1
yx=.= _,-, - -.~.
BAB000( & WILCDX C0W##, C0ftERCIAL NUCLEAR REL PLAK W NRC LtCENSE SNM-ll68 DOCKET E1201 V CONDITIONS SECTIO 4 8.0 Technical Specifications - Radiation Safety (continued) 8.2.4 Respirators may be used in unusual conditions where air-borne concentrations of radioactive material may.cause personnel to receive exposures in excess of permissible levels. Typical unusual conditions may be certain maintenance operations, startup periods, short-term operations, etc. Procedures for maintenance of the respirators and training of personnel using respirators shall be under the cognizance of Health-Safety.
Respira-tors shall not be applied as a routine control measure in situations where engineered or procedural controls l
are feasible. SCBA is available at the plant.
Respiratory protection equipment shall be governed by 10CFR20.103(c).
8.3 Instrumentation 8.3.1 Portable instrumentation used to evaluate general area activity shall be capable of detecting contamination levels at or below license limits or action levels.
P 3
DATE 2-04-87 REVISIQ1 No.
PAT 52 i
CLERENT REVISION:
StJPERSEDES: PAGE 73 WNRC MRR EME I
2-04-85 2
l MTE REVIS!Qi
J BABOXX a WillDX CDPM, UNERCIAL NtEEAR REL PLM i
USNRC LICENSE SNPt-ll68 DOCKET E 1201 SECrim V CONDITIONS 8.d Technical Specifications - Radiation Safety (continued) 8.3.2 Analytical capability for evaluation of effluent samples shall be such that instrument sensitivity and sample preparation techniques allow:
a.
1% of the appropriate MPC for liquid effluents b.
10.0% of the appropriate MPC for airborne effluents.
8.3.3 A criticality monitoring system shall De maintained in com-pliance with the appropriate sections of 10 CFR 70. Response time for the system shaji be in accord with Regulatory Guide 8.5, " Criticality and Other Interior Evacuation Signals" dated March, 1981. The criticality alarm system shall be function-tested at least quarterly, anf detector units calibrated annually. Nucitar accident dosimeters incorpo-rating neutron activation foils shall be positioned in the plant at locations selected by Health-Safety to provide exposure estimating capability in the event of a nuclear l
incident.
8.3.4 All instrumentation shall be calibrated upon initial installation, following major maintenance, and at other times as deemed necessary.
In any case,
- j i)
MTE 2-04-87 REVISION NO.
3 PAGE 53 ClRRENT REVISION:
SUPERSEDES. PAGE 74 m mg mm MTE _ 2'-04-85 REVISION 2
BAB000( a WILQ)X ON#ff, CatERCIAL NilGEAR REL PLM l
LENRC UCENSE SNM-1168 DOCKET Al.1201 SECT!m V CONDITIONS 8.0 Technical Specifications - Radiation Safety (continued)
[
8.3.4 calibration shall be performed at least semi-annually. Labora-I tory counting instruments shall be calibration-checked daily when in use. Calibration records shall be maintained for a minimum of two years.
8.3.5 Field check sourcesshall be available for assuring functional response of instrumentation prior to use.
l l
8.4 Personnel Monitoring and Contamination Control 8.4.1 Personnel monitoring equipment - film badges, thermo-luminescent dosimeters, detectors, ctc., -shall be used by persons having ac' cess to restricted or radi-ation areas, as deemed necessary by Health-Safety, and in accord with 10 CFR 20.
The dosimeters shall be processed routinely 'to determine radiation dose. Heal th-Safety shall review and maintain the dose records and prepare such reports as are required by regulations.
Neutron dosimetersshall be used by operators and other persons as deemed necessary by Health-Safety w' hen a potential for measurable neutron exposure exists.
8.4.2 An indium foil stripshall be worn by plant personnel to provide for identification of persons receiving high exposures in the event of an accidental criticality.
8.4.3 Persons who work routinely in areas where there is a potential for bodily intake of radioactive materials r
DATE
'2-04-87' I
REVISION No.
PAGE 54 CLRRENT REVISION:
SUPERSEDES: PAaE 75 m mg am DATE 2-04-85
.2 REVISim 1
l BAB000( a WIUDX C&P4f(, GNERCl#. NUClfA REL PIM USNRC LICENSE StM-1168 DOCNET M-1201 SECTIO 4 V CONDITIONS 8.0 Technical Specifications - Radiation Safety (continued) 8.4.3 shall be subject to determination of the extent of in-take and retention by analysis of excreta or body counting.
The bioassay program shall be ccnducted in accord with Regulatory Guide 8.11 " Application of Bioassay for Uranium". Periodic " blank" or " spike" samples shall be included in the bioassay program.
8.4.4 Personnel Contamination
" Change room" facilities shall be provided for the control of contamination spread from areas where sig-nificant quantities of unclad SNM are handled.
Normal exit from controlled areas shall be through change room facilities.
The change room shall include personnel decontamination and monitoring capability.
External contamination of personnel entering controlled areas shall be limited by means of protective clothing.
The degree and type of protection required is determined by Pealth-Safety, depending on the contamination potential f
in the area under consideration.
Required protection may range from a minimum of lab coats and shoe covers over street clothes to coveralls, haircaps, gloves.,
and special shoe for areas of higher contamination potential.
The use of anti-contamination clothing DATE 2-04-87 REVISION NO.
3 PAGE 55 CLRRENT REVISION!
SUPERSEDES: PAGE 76 L5NRC APPROVAL. HEFERENCE 2-04-85 2
MTE REVIS!m
l BABQXX a Wil.00X (DPANY, 00MUCIAL NUQfAR REL PLM USNRC LICENSE SPM-ll68 DOCKET M-E l V CONDITIONS SECTI(N f
8.0 Technical Specifications - Radiation Safety (continued) 8.4.4 within the plant is limited to the controlled area, q
except as specifically authorized and monitored by lieal th-Safety..
Radiation monitors, incorporating audible and/or visual alarms, shall be located at routine exit points from controlled areas.
The monitor alarm point shall be set as low as practicable taking into account the necessity for reducing spurious alarms induced by background fluctuations. Health-Safe.ty shall be noti-fled when initial decontamination attempts fail to reduce skin contamination below the monitor alarm point. Health-Safety shall assist during further decontamination, as necessary, to' levels as low as reasonably achievable, consistent with good
~
health physics practice before releasing the employee.
4 8.4.5 Surface Contamination Control The following criteria shall be applied to monitoring and control of surface contamination.
The levels shown represent contamination levels which, when ex-ceeded, shall cause prompt clean-up activities of the affected area to be initiated.
DATE 2-04-87 REVISION NO.
3 PAGE 56 CLRRENT REVISION:
SUPERSEDES: Pace 77 m m g REFEREncs DATE 2-04-05 REVISION 2
BAIKDO( a WILCDX CCNANY, UNERCIAL NUClfAR REL PUE USNRC LICENSE SNM-1168 DOCKET M-El SECTIOi V CONDITIONS 8.b Technical Specifications - Radiation Safety (continued) 1 8.4.5 kia Action tevel survey Frequency a
50,000DPM/50[2 1.
Controlled pellet Removable:
5,000 OPM/100 Weekly 2
/
processing / rod Total loading. change room 4
(hot area) 2 2.
Change Room Removable:
500 DPM/100 cm Daily *
(Intermediate)
Total 2.000 DPM/ 50 cm 2
3.
Clean (Remainder of Removable:
200 OPM/100 cm Monthly plant and office Total
.500 DPM/ 50 cm area)
- When pellet processing operations are being conducted.
In no case shall there be more than one week between surveys.
k The levels established for Item "1" above are defined for the general area including floors and other exposed surfaces.
The contamination levels in hoods and on
)
equipment that directly contacts SNM cannot be effectively specified.
Control shall be maintained through
]
frequent cleanup and limitation of powder accumulation.
Tools and equipment removed from controlled areas for uncontrolled use elsewhere in the plant shall not exceed that specified for clean areas unless specified by Heal th-Safety'.~In siich cases Health-Sifiti mij~ impose ~~ ~
~
f limitations on use or require other controls to preclude con-taminai; ion spread.
1 DATE 2-04-87 REVISION NO.
3 PAGE 57 CURRENT REVISION:
SUPERSEDES: PAGE 78 mogg,
DATE 2-04-85 2
REVIS!0N
.f
L BABC00( & WIL(DX C&P#h', C@tERCIAL NUCLEAR REL PLM USNRC LICENSE Snit-ll68 DOCKET E 1201 V CONDITIONS SECTICN 8.0 Technical Specifications - Radiation Safety (continued) 8.4.6 Health-Safety may approve the performance of non-routine l
or temporary operations in the manufacturing area outside the controlled area when the operation may result in contamination I
provided the following controls are established and documented:
- The area involved is identified and access controlled.
- Necessary area and personnel contamination control and monitoring programs are implemented including use of an,ti-contamination clothing if needed and air sampling as required.
- During the course of the operation, decontamination shall be initiated when general contamination levels in excess of 1000 DPM/100 cm2 (removable) or 2,500 DPM/50 cm2 (total) are noted. Following cympletion of the operation, decontamination to clean area levels specified in Paragraph 8.4.5 shall be accomplished.
8.4.7 Operations which are not covered by an operating procedure and are judged by cognizant supervision as being likely to exceed the concentration limits specified in Table I of Appendix B to 10 CFR Part 20, shall be covered by a Radiation WorkPermit(RUP),
The RWP shall be issued by the Health-Safety group.
It shall specify the safety requirements, protective clothing and equipment, and monitoring requirements necessary to assure the operation is conducted in a safe manner.
8.5 Receiving Inspection 8.5.1 SNM receipts shall be inspected for damage, and surveys conducted to ascertain if the level of contamination is acceptable for CNFP handling and storage.
Results in excess of contamination limits specified by the Department of Transportation shall be reported to Health-Safety for 3
PAGE 58 DATE 2-04-H/
REVISICH No.
CURREfR REVISICN:
t SUPERSEDES: PAGE 79 USNRC APPROVAL REFERENCE 2-04-85 2
DATE ggygggcg;
.o BAB000( a WIUDX CDP #ff, CutERCIAL NUCLEAR REL PIM USNRC LI NSE SPM-1168 DOCKET E.1201 SECTICN V CONDITIONS 1
8.0 Technical Specifications - Radiation Safety (continued) j 8.5.1 notification of the shipper and evaluation of the need 6
for decontamination.
8.6 Non-Exempt Sealed Source Control 8.6.1 Use of non-exempt sources for training and instrument calibration shall be limited to, or under the direct control of, qualified Health-Safety personnel.
Sourcesutilizedasafunctionalcomponenthfdevices 8.6.2 designated for manufacturing and quality control purposes shall be operated only by approved personnel who have been instructed in safe practice by Health-Satety.
Health-Safety shall provide appropriate monitoring support during maintendnce o'r other operations that may entail increased exposure levels.
A register of approved operators,shall be maintained in the Health-Safety Office.
8.6.3 Maximum whole body exposure rates in any constantly occupied area in the vicinity of operating manufacturing or quality control units utilizing by-product material sources shall be less than 2 mrem /hr.
8.6.4 In addition to dosimetric devices routinely worn by all CNFP employees, appropriate self-reading dosimeters shall be utilized by personnel involved in source MTE
" 2-04-87 REVIS! W NO.
3 PAGE 59 CURRENT REVISION:
SUPERSEDES: PAGE s9 USNRC APPROVE REFERENCE ETE 2-04-85 REVIS!m 2
BAB00CK & WILC0X COWANYI C0ffERCIAL NUClfAR REL PLM USNRC LICENSE ~SMt-ll68 DOCKET D-1201 SECT. ION,
.V CONDITIONS 10.
Failed Fuel Rod Detection System 10.1 Description of Activities A Radiation Control Zone (RCZ) will be established for activities with the ECH0-330 when it is out of the storage configuration.
Typical activities performed on the ECH0-330 equipment in the RCZ include decontamination, repair, testing, and packaging.
The ECH0-330 will be appropriately packaged and labeled to prevent contamination spread when in the storage configuration.
10.2 Radiation Control Zone (RCZ)
The following conditions apply to the establishment and maintenance 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 shall be performed within the RCZ.
i 10.2.3 The action levels used for radiological control within the RCZ are given in Table 1 of this part.
10.2.4 The identity of authorized personnel allowed access to the RCZ and information regarding activity as either maintenance or storage in the RCZ shall be communicated in advance to Health-Safety.
Visitors or other personnel desiring access to the RCZ must be accompanied by authorized personnel.
DATE 2-04-87 REVISION No.
1 PAGE 67 CURRENT REVISION:
SUPERSEDES: PAGE 67 USNRC APPROVAL REFERENCE IMTE 5-07-85 REVISION 0
F BABC0CK & WILC0X Caf##l MEIAL M E N USNRC LICENSE SMt-ll68 DOCKET 70-1201 SE G M.
.V CONDITIONS
- 10.
Failed Fuel Rod Detection System 10.2.5 Upon return to the CNFP, radiological surveys shall be
~ ~ ~
performed prior to any initial maintenance or handling of the ECH0-330 equipment.
10.2.6 Contaminated equipment that exceeds the Radiation Control Zone limits in Table 1 shall be decontaminated.
I i
10.2.7 Radiological surveys shall be dQcumented and maintained by l
Health-Safety 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-l ment, radiological surveys of the RCZ shall be performed at lea'st daily ' or more frequent 1y'if considered necessary by Health-Safety.
[
10.2.9 During periods' of long term storage, weekly sbrveys of i
the RCZ for external radiation and renovable contamination i
shall be performed,'except during CNFP plant shutdown of a week or longer, but not to exceed 3 weeks.
I f 'the contaminated equipment containers are s'tored in the RCZ, then they will be included in these weekly surveys.
l 1
l DATE 2-04-87 REVISION NO, 1
PAGE 60 ctFPBIT REVISION:
SUPERSEDES: PAoE sa s-07-85 0
fut
_ cggggg_
BABC0CK a WILC0X C0WA's CGNKIAL NUDIAR FLEL PLM USNRC LICB4SE SNft-ll68 DOCKET 70.1201 SECTJON..V CONDITIONS 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 of this part.
10.2.12 Radiation workers shall receive initial indoctrination o
[
training before they are allowed to work in the RCZ. This training, as well as the, annual retraining, is as described
! ?,
in Paragraph 6.2 of Section V of SNM-1168.
j' 4
l
/
4 DATE 2-04-87 REVISION No.
1 PAGE 69 CURRENT REVISICtl
'[
5bRSEDES: PAiE 69 USNRC APPROVAL REFERENCE DATE 5-07-85 REVISION 0
.y s v..
- =
~
u
.BABC0CK & WILC0X mf.Wj CQMIAl_ Nin. EAR FEL PIRE m
USNRC LICENSE SNM-ll68
' DOCKET, 70-1201 SECUON.
V.
CONDITIONS.-
10.
Failed Fuel Rod D'etection System 10.2.13 Instrumentation shall be calibrated as' indicated in i
Section 8.3.4.
10.2.14 Respirators may be used in unusual conditions where air-borne concentrations of radioactive material may cause personnel to receive exposures in excess of permissible r
levels. Typical unusual conditions may be certain maintenance operations, short-term operations, etc. Pro-cedures for maintenance of the respirators and training l
of personnel using respirators shall be under the 4
cognizance of Health-Safety.
4 4
4 a
k L
i
-y i
x if*w i
i
.(';
2-04-87 DATE-REVISION NO.
1
'PAGE-
-70 l
t I; O CURRENT REVISION:
**C
~
[ ' '+
SUPERSEDES: PAGE 70 USNRC APPROVAL REFERENCE i
DATE 5-07-85 REVISION 0
i
L...
3 4-WWCK WL.QWMW) CMCAL. NUCLEAR RR RM i
L USNRC LICENSE Snit-ll68 DOCKET 70-1201 E
SECTION...V.
CONDITIONS 10.
Failed Fuel Rod Detection System
-10.2.14 The Respiratory Protection Program shall be conducted in 3-accord with 10 CFR 20.103.
t 1:
10.2.15 Personnel and/or fixed air samplers shall be used to deter-t mine exposure to airborne radioactivity during maintenance-operations. Health-Safety shall specify frequency of per-sonnel sampling based on operational experience and Health Physics judgeme'nt to keep exposures within 10 CFR 20.103(a) t limits. Gaseous effluents to unrestricted areas shall be controlled to the limits specified in 10 CFR 20. Air l
samples shall bp collected daily when the facilities are in an operational status. HEPA filtered containment facili-ties such as disposable tents or enclosures, shall be f
used in accord with good Health Physics practice as required by Hea'lth-Safety to control airborne radioac-tivity. HEPA filters shall be changed when the differential pressure exceeds 4" of water. Differential pressure shall b'e recorded weekly when containment facilities are in use.
e 2-04-87 DATE
. REVISION NO.
1
~PAGE 71
~
CURRENT REVISION:
SUPERSEDES: PAGE 71 USNRC APPROVAL REFERENCE DATE 5-07-85 REVISION 0
1-BABC0CK 2 WILCOX C0WA's C0ffERCIAL NUCIBR FLEL PIM USNRCLICENSESNM-ll68 DOCKET 70.1201
(
SECTION.. Y CONDITIONS.
5 10.
Failed Fuel Rod Detection System 10.2.16 Personnel working directly in the RCZ shall be included in j
the bioassay program of at least one in vivo measurement n
4 per year, if they work in an area which is designated as an d
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 j
were such tha't significant internal exposure mhy have occurred. Such conditions include but are not limited to:
1.
Nasal sr. ear results indicating facial captamination in excess of 10,000 DPM.
2.
An internal exposure in excess of 40 MPC. Hr. in any seven consecutive days.
3.
Any accidental internal exposure, whether real or suspected.
Immediate followup bioassay (excreta) measurements shall be performed if any of the 3 conditions noted above exist. If i-the followup measurements confirm the presence of greater than 10% of the maximum permissible organ burden, the worker will be restricted from work in a controlled area until the maximum permissible organ burden is under 10%.
l~
DATE 2-04-87
~ REVISION NO.
1 PAGE' 72 o
l CURRENT REVISION:
SUPERSEDES: PAGE 72 USNRC APPROVAL REFERENCE DATE 5-07-85 REVISION 0
a
l as BABC0CK a VILC0X C0ifNK CORERCIAL NtJCLEAR FlJEL PLAIT USNRC LICENSE SNft-ll68 DOCKET 70-1201 l
SECT. ION.. V CONblTIONS l
10.
Failed Fuel Rod Detection System l
10.2.16 Prior to liealth-Safety approval of an individual to work I
in the RCZ, the individual's occupational radiation exposure history (both internal and external) shall be reviewed.
t 10.2.17 The reactor inspection equipment contain only contamination quantities of by-product material and there-fore does not require special. handling with regar.d to nuclear criticality safety.
10.2.18 Contaminated wastes that cannot be disposed of un' der the current conditions in Section V will be transferred to a i
licensed facility for subsequent disposition.
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f
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2-04-87 DATE-REVISION NO.
~ ~l PAGE 73 4
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CURRENT REVISION:
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SUPERSEDES: PAGE 73 USNRC APPROVAL REFERENCE DATE 5-07-85 REVISION 0
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p BABC0CK 8 WILCOX COW #C COWERCIAL NUCLEAR REL RM USNRC LICB4SE St#t-1168 DOCKET 70-1201 SECT. ION V
CONDITIONS-1)
TABLE 1: -RADIATION CONTROL ZONE (RCZ) LIMIT Beta-Gamma Total (Fixed & Removable)
Item External Radiation Removable Contamination
(}
- 1. Protective Clothing 2
Available for Use
.5 mR/hr. at 1 cm 2,200 DPM/100 cm
- 2. Equipment Maintenance 2
and Storage 50 mR/hr. at 1 ft.
500,000 DPM/100 cm i
j
- 3. Floors, Walls, and 2
other Surfaces 1.0 mR/hr. at 1 ft.
5,000 DPM/100 cm f
(1)Alpha contamination will be controlled as indicated in
{
Part 8.4.5 of Section V.
(2)As measured by direct survey.
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DATE 2-04-87 r
' REVISION NO.
~1
'PAGE~
74
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CURRENT REVISION:
ll SUPERSEDES: PAGE 74 USNRC APPROVAL REFERENCE 5-07-85 0
MTE REVISION t
(.
-x BABC0CK & WILCOX C0WNC C0fTERCIAL NUCLEAR REL RM USNRC LICENSE StM-ll68 LDOCKET F.1201 SECTION. V. CON DITIONS.
l TABLE 2:
UNRESTRICTEDAREARELEASEI.IMITS(1) i e
i Beta-Gamma Item External Radiation Removable Contamination
- 1. Skin, Hair, and (2)
L Personal Clothing Min. Detectable Level Min. Detectable Level 2
- 2. Equipment 0.2 mR/hr. at I cm 1,000 DPM/100 cm
- 3. Figors, Walls, and 2
Other Surfaces 0.2 mR/hr. at I cm 1,000 DPM/100 cm II}AlphacontaminationwillbecontrolledasIndicatedinPart8.4.5 f'
of Section V.
(2)As measured by direct survey.
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2-04-87 DATE REVISION NO.
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q CURRcNT REVISION:
SUPERSEDES: PAGE 78; USNRC APPROVAL REFERENCE 5-07-85 0
DATE REVISIM