ML20055G422
| ML20055G422 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 07/17/1990 |
| From: | Christopher Boyd BABCOCK & WILCOX CO. |
| To: | Haughney C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9007230160 | |
| Download: ML20055G422 (47) | |
Text
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Babcock & Wilcox-nwoussanentasonaroav -
1
- a McDermott company -
P.O. Box 11165 Lynchburg, VA 24506 1165 (804) 522 6000 July 17, 1990 U. S. Nuclear Regulatory Commission Attn Charles J. Haughney, Chief Fuel cycle Safety Branch Division of Industrial & Medical Nuclear Safety Washington, DC 20555-
Reference:
Letter from John P. Eckert to Robert M. Bernero dated May 18, 1990.
Letter from Richard E. Cunningham to John P. Eckert dated June 1, 1990.
Gentlemen:
'Ihe Babcock & Wilcox Company, Naval Nuclear Fuel Division Research
' Laboratory (NNFD-RL), is requesting an amendment to our license, SNM-778, to reflect a recent change in our corporate organization as discussed in the referenced letters.
Specifically, Babcock & Wilcox now has c new parent company, Babcock & Wilcox Investment Company (BWICO).
D&W is a wholly-owned subsidiary of BWICO and BWICO is a wholly-owned subsidiary of McDermott, Inc.
At this time for convenience, we are also making minor editorial changes throughout the ' license.
A description of these changes is attached.
along with the actual proposed page changes to the specification = and-demonstration sections of our license.
Changes are marked on the text pages by a vertical line in the right hand margin.
NNFD-RL believes these changes have no impact on our current organization and are adminis-trative in nature.
This recpest does not affect or modify any operations which are currently approved nr affect the health and safety of any personnel on or off site nor have any adverse effect on the environment. Therefore, granting this request should not require an environmental impact statement as speci-fled in 10 CFR 51.22(c)(ll).
Attached is a check for $150 to cover the initial application fee.
If you should have any further questions, please contact me at (804) 522-5753.
Very truly yours, BABCOCK & WILCOX NNFD Research Laboratory
[h72hk h 24 Charlie C. Boyd, Jr.
PDC Licensing & Compliance Officer C
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p Attachments w
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f REVISIONS BY P/4E AND PARAGRAPH 1
Page 1-l'.
l Paragraph 1.1 McDermott International, Inc. has been changed to Babcock & Wilcox Investment Co.
-Republic of Panama has been changed to. State of Delaware.
]
1 Principle has been changed to principal
-Page 1-8 he cross hatching has been removed from the Temporary Storage racility located at the top right hand corner of the figure.
x-Page 2 Paragraph 2.2.4 j
,l m
The' Licensing & Compliance officer is the " Chairman" of the Safety Audit Subcom-mittee vice the coordinator.
j Page 2-8 Paragraph 2.7.2.1
- Health and Safety changed to Health Physics.
'Page 2-12 Paragraph 2.10.5 Industrial safety audit and inspection records are kept for 2 years vice indefi-nitely..
-Page 3-1 Paragraph 3.1.1.6 Area Supervisor changed to Employee's Supervisor.
Page 3-6 Paragraph 3.2.3.4.1 The word gamma was added before criticality alarm system.
New paragraphs 3.2.3.4.2 and 3.2.3.5.3 were added to address the Model NM-6, neutron. criticality alarm monitors, and the Tennelec LB-5100, alpha / beta propor-tional counting system respectively.
Both are recent addit,'.ons to our health physics program.
1
Pages 3-7 to 3-15 hepaginated due to the text overflow from the preceding page.
[Page4-1
-Paragraph 4.1.2
.he_ Manager Facilities is now the Manager, Industrial Engineering.
'Page 4-2 Paragraph 4.1.6
. he' Industrial Safety officer has been added to the AOP approval process.
W e word verifies has been changed to verify.
Page 4-10
?
LRC changed to !@iFD-RL.
Page 5-2 Paragraph 5.1.4.4 he word logthythmic has been changed to logarithmic.
Page 7-1
- he title of Table -1, Acceptable Surface contamination Levels, has been added in jparagraphs 7.1.2, 7.1.3, and 7.1.4.
Page 7J 2e title of Table 1, Acceptable Surface Contamination Levels, has been added in paragraphs 7.1.6 and 7.2.2.3.
Regulatory Guide 1.86,: dated June 1974, was deleted fram paragraph 7.2.2.3.
l Page 9-1 3ection 9.2 on financial qualifications now located on page 9-2 vice 9-3.
Page 9' l L
Paragraph 9.1.1 and 9.1.3 McDermott International, Inc. has been changed to Babcock & Wilcox Investment Co.
H
> Paragraph 9.1.4 J. E. Cunningham has been changed to Robert E. Howson.
2 l
l Page 9-2 Robert E. Howson as President & Chief Operating Officer (which was listed twice)
- has been deleted.
Robert E. Howson is now the chairman of the Board & Chief Executive Officer as indicated in the change on page 9-1, paragraph 9.1.4.
Paragraph 9.1.6 he last sentence has ' been deleted and replaced with:
In July of 1990, the Babcock & Wilcox Investment company (BWICO), incorporated under the laws of the State of Delaware, became the parent company for Babcock & Wilcox.
B&W is a wholly-owned subsidiary of BWIco and BWICO is a wholly-ownea subsidiary of McDermott, Inc.
Paragraph 9.2.1 he end of the sentence, is demonstrated in the latest has been replaced with,... will be sulxnitted by July 27, 1990 in accordance with 10 CFR 70.25.
Page 9-3 Paragraph 9.4 within about two miles of the he sentence, "We property bounda and topography'We site location with respect site are shown in Figure 9-2" was e nged to read to a five mile radius is shown in Figure 9-2" which is what the figure actually represents.
Page 9-4 Repaginated due to the text overflow from the preceding page.
Page 9-5 Paragraph 9.7.1 Facility Supervisor changed to Licensing & Compliance Officer in five places.
Health and Safety changed to Health Physics in two places.
Industrial Safety Officer added to the AOP review and approval process.
Criticality added to the title of Nuclear Safety Officer.
Paragraph 9.7.2 Facility Supervisor changed to Licensing & Cor@liance officer in two places.
Health and Safety changed to Health Physicc in two places.
" Consult with the License Administrator" eliminated since the License Administrator-and the Facility Supervisor were combined to form the Licensing & Compliance officer.
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I Page 9-6 Paragraph 9.7.3-racility Supervisor changed to Licensing & Compliance officer in two places.
Page 9-9
%e cross hatching has been removed from the Tenporary Storage racility. located at
-the top right hand corner of the figure.
1 Page 10-2 Paragraph 10.2.5.3 1
Gramatical change from plural to singular throughout, h
Paragraph 10.3.2.1 y
%e decommissioning of Building A was completed.
i/
Page 10-10
)
he cross hatching has been removed from the Temporary Storage racility located at l
the top right hand corner of the figure.
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/Page 11-3 Paragraph 11.1.8 The'rire & Rescue Team is now called-the Emergency Response Team.
L l-Page-11-17 he Licensing & Compliance officer changed to the Industrial Safety officer in two I
- places.
Page 12-30
-Health and Safety changed to Health Physics.
Page 13 Paragraph-13.4.5' he word plant has been changed to plan.
[
Page 13-6 1
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%e cross hatching has been removed from the Temporary Storage Facility located at
.the top right hand corner of the figure.
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'l l
I 4
L 1
l jf,
.]
i.
'r Page 14-2:
1 Paragraph 14'2
~
he words "at the" have'been deleted.
i Page 14 Supervisor approval changed to approval by the Licensing & Compliance officer.
Supervisor changed to Area Supervisor.
Page 14 : Paragraph 14.7 Manager,l Facilities has been changed to Manager, Industrial Engineering.
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LIST OF REVISED RAGES Remove Add Page-Rev.
Date Page Rev.
Date 1-1
-4 4/87 1-11 13-7/90 1-8 8
11/87 1-8 13 7/90=
2-2 11 5/89 2-2 13 7/90 2-8 11 5/89 2-8 13-7/90 2-12 11 5/89 2-12 13 7/90 3-1 11 5/89 3-1 13 7/90 3-6i 4
4/87 3-6 13 7/90 7 11 5/89 3-7 13 7/90 3-8 4.
4/87 3-8 13 7/90 3-9 11 5/89 3-9 13 7/90 3-10 11.
5/89 3-10 13 7/90 3-11 11 5/89 3-11 13.
7/90 3-12 11 5/89 3-12 13 7/90 3-13 11 5/89 3-13 13 7/90 3-14 11-5/89 3-14 13 7/90-3-15 5-5/87 3-15' 13 7/90 4-1 11 5/89 4-1 13 7/90 4-2 11 5/89-4-2 13 7/90 4-10 9
3/88 4-10 13 7/90 5-2 4
4/87 5 13 7/90 7-1 5
5/87 7-1 13 7/90 7 -5 5/87 7-2 13 7/90 9-i-4 4/87 9-i 13 7/90
,9 4 4/87 9-1 13 7/90 9-2 4
4/B7 9-2 13 7/90 9-3 11 6/88 9-3 13 7/90 9-4 4
4/87 9-4 13 7/90 9 0 10/85 9-5 13 7/90 9-6 0
10/85 9-6 13 7/90 9-9 8
11/87 9-9 13 7/90 10-2 0
10/85 10-2 13
-7/90-10-10 8
11/87 10 13 7/90, 11-?
12 9/B9 11-3 13 7/90 11-17 12 9/89 11-17 13 7/90 12-30 8
11/87 12-30 13 7/90 13-5 10 3/89 13-5 13 7/90 13-6 10 3/89 13-6 13 7/90 14-2 4
4/87 14-2 13 7/90 14-12 8
11/87 14-12 13 7/90 14-18 9
3/88 14-18 13 7/90 l
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PART I LICENSE CONDITIONS 1
i 1.0 STANDARD CONDITIONS AND SPECI AL AUTHORIZ ATIONS 1.1 NAME Name - Babcock & Wilcox Investment Company l
Babcock & Wilcox Naval Nuclear Fuel Division
+
NNFD Research Laboratory Babcock & Wilcox, Investment Company is incorporated under the laws of the State of Delaware.
Principal Office - 1010 Common Street, New Orleans, Louisiana.
1 1.2 LOCATION Address - Babcock & Wilcox NNFD Research Laboratory P. O. Box 11165 Lynchburg, Virginia 24506-1165 The NNFD Research Laboratory-(site) is' located in Campbell County, Virginia, near the James. River, approximately four miles _ F.ast of the city of Lynchburg. Figure 1-1 shows the location of the site with respect to the Commonwealth of Virginia.
Figure 1-2 shows the location of the site with respect to a five mile radius. Figure 1-3 shows the location of buildings and facility locations where licensed materials are handled and stored.
1.3 LICENSE HlNBER AND PERIOD License Number - SIN-778 License No-SNM 778 Docket No. 70 824 Date July,1990 Amendment No.
10 Revision No.
13 Page 1-1 Babcock &Wilcox a McDermott company 1
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License No SNM 778 Docket No.70-824 Date July,1990 Amendment No.
Revision No.
Page 1-8 10 13 Babcock &Wilcox a McDermott company
4-
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f Y pertain to nuclear activities. He shall be the coordinator of the-D SRC and the Chairman of the Safety Audit Subcommittee and shall l'
represent management on both. 6 shall maintain the. permanent records of the SRC and shall be responsible for assuring. that appropriate action is taken to correct SAS audit findings that are approved by the Manager, SS.
2.2.5 Area Supervisors - Area Supervisors are recommended by their division management and their appointment shall be jointly approved by the Supervisor, Health Physics, and the Licensing & Compliance Officer. They shall functionally report to the Licensing & Com-1 p11ance Of ficer. They shall be responsible for the safety and compliance of operations in their assigned areas. They shall be responsible for maintaining the exposures of personnel assigned to -
their' area below 300 millirem / week; 1250 millirems / quarter..They c
shall have approval authority for Radiation Work Permits that apply to their assigned areas. They shall keep the Licensing & Compliance Officer advised of plans for projects and work to be carried out in
-1 their areas.
2.2.6 Supervisor, Health Physics - The Supervisor, Health Physics is responsible for providing adequate facilities, procedures, and properly trained personnel to implement the Health Physics Program.
1 He is responsible for health physics activities. The Superv_isor, Health Physics reports to the Manager,. Safety and Licensing. The a
Supervisor, Health Physics has the authority to stop any operation that he believes is contrary to accepted safety practices or license
'I requirements. He shall review new Area Operating Procedures, Radi-1 ation Work Permits and changes thereto, for the radiation safety aspects of the procedure, RWP, or change' and he.shall have approval authority for-them.' He shall be responsible for training programs for new employees and Authorized Users of Radioactive Material. He shall be responsible for the shipment of licensed material. The Supervisor, Health Physics shall be a member of the Safety Review Committee but shall not be a member of the' Safety Audit Subcommittee.
He shall have approval authority for Area Supervisors.
2.2.7 Health Physicists - The Health Physicists shall administer activi-ties of the Health Physics Group. They shall report to the Super-'
visor, Health Physics.
2.2.8 Industrial Safety Officer - The Industrial Safety Officer shall administer the industrial safety program.
He shall report to the HNFD Manager, Health and Safety.
License No SNM-778 Docket No.70-824 Date July, 1990 Amendment No.
Revision No.
10 13 Page 2-2 Babcock & Wilcox a McDermott company
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T 2.7 OPERATING PROCEDURES,
.2.7.1 Area'Operatin~g Procedures 2.7.1.1' All operations with licensed material shall be conducted in accordance with Area Operating Procedures or Radiation Work Permits (see 3.1.1).
2.7.1.2 Area Operating. Procedures ( AOP) - Area Operating Procedures shall
-be established for all roi: tine operations in which SNM, source and byproduct materials are stored or handled. AOP's.shall include those nuclear criticality and radiation safety controls and limits that apply to the operation. Each A0P shall'be approved by the Nuclear Criticality Safety Officer or his designated alternate, the Supervisor, Health Physics or his designated alternate, the Licensing & Compliance Officer or his designated alternate, the Industrial Safety Officer' or his designated alternate and the Safety Review Committee.
2.7.1.3 A0P's may be revised with the approval of the Nuclear Criticality Safety Officer or his designated alternate, the Supervisor, Health Physics or his designated alternate, the Industrial Safety Officer or his designated alternate and the Licensing & Compliance Officer or his designated alternate. The revised procedure may be used with these approvals until the next scheduled regular meeting of the Safety Review Committee when the revision must be approved by the:SRC.
2.7.1.4 A0P's shall be available in each operations area where they apply and shall be followed by site personnel.
2.7.1.5 Distribution of new and revised. procedures shall be made in accordance with a document control system which assures tha? "a procedure manuals contain only the mort current revision Ae -
procedures.
2.7.1.6 AOP manuals shall be reviewed annually by the Licensing &-Com-
- pliance Officer to assure that the manuals contain the most current revision of the procedures.
2.7.2 Technical Precedures 2.7.2.1 Technical procedures shall be established, reviewed, approved, and followed for Health Physics or Nuclear Criticality Safety. They l
shall be reviewed and approved by a Health Physicist or the Nuclear Criticality Safety Officer, respectively, or their designated License No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
Revision No.
13 Page 2-8 10 Babcock &Wilcox a McDermott company x_ _
. h 1
2.10.2 Nuclear Criticality Safety Of ficer '
Nuclear criticality-safety 6 months after evaluations and calculations termination of the approved process.
Nuclee.r Criticality Safety Officer 2 years Audit Reports.
2.10.3 Licensing & Compliance Officer Safety Review Committee Minutes
(*)
Safety Audit Subcommittee Audit Reports 2 years Investigation. reports of off-normal occurrences 2 years
- 2.10.4 Emergency Records-Records pertaining to emergency response and preparedness shall be retained in accord ace with Radiclogical Contingency Plan, Section 8.0.
2.10.5 Industrial Safety Of ficer Training. Records
(*)
Industrial Safety Audits 2 yeart.
Industrial Safety Inspections
-2 years License No SNM 778 Docket No.70-824 Date July, 1990=
Amendment No.
10 Revision No.
13 Page 2-12
=
Babcock &Wilcox a McDermott compeny
1' 3.0 RADIATION PROTECTION 3.1 SPECIAL ADMINISTRATIVE REQUIREMENTS 3.1.1 Radiation Work Permits (RWP) 3.1.1.1 RWP's shall be issued whenever the activity is not covered by an Area Operating Procedure and workers are likely to be exposed to levels of radiation or concentrations of radioactive material in excess of those specified in 10 CFR 20.101 & 20.103.
3.1.1.2 RWP's shall be approved by the Area Supervisor, Supervisor, Health Physics, Industrial Safety Officer, and the Licensing & Compliance Officer.
In the absence of any of the above persons, a designated and qualified alternate may approve RWP's.
3.1.1. 3 The RWP shall specify the radiological protection requirements for the operation and specify levels of worker exposure above which a doeumented ALARA evaluation shall be performed. RWP's that re-quire a documented ALARA evaluation n:ust, in addition to 3.1.1.2, be approved by the Manager, SS.
3.1.1.4 kWP's shall be approved at a meeting of all the signators of the form.
3.1.1.5 The RWP form shall provide space for entering the estimated exposures to the whole body, extremities, and for the job. These are used to identify the areas of exposure concern and do not constitute an exposure 90 41 or limit.
3.1.1.6 The RWP form shall provi@ spece for the employee's supervisor to 1
sign or initial, attesting that the workers have been instructed in the requirements of the RWP.
3.1.1.7 The term of a RWP shall not exceed 30-days, except that Standing RWP's shall have a term not to exceed 6-months.
3.1.2 ALARA Policy The management of the site is committed to a policy of maintaining exposures as low as is reasonably achievable.
3.1.2.1 Site workers shall be introduced to this policy during their initial training and shall be reinforced during the annual re-training of Authorized Users.
Ucense No SNM 778 Docket No.70-824 Date July,1990 Amendment No.
10 Revision No.
13 Page 3-1 Babcock &Wilcox a McDermott company
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3.2.3.4.1 Nuclear Measurements Corp. (NMC) Model GA-2TO and GA-2A - These monitors are designed as gansna criticality alarm systems. De-I tection is by a Nal (T1) detector operated in the constant current mode. Response is logarithmic and non-saturating.
Emergency power is provided. The nomine1 alarm setpoint is 20 mR/hr. Failure alarm function is provided. Criticality monitors shall be calibrated semiannually.
3.2.3.4.2 Nuclear Measurements Corp. (NMC) Model NM These monitors are designed as neutron criticality alarm systems. The NM-6 is com-r prised of a r. 9 tron sensitive detector recessed in a paraffin-filled moderator operating into an electronic system comprised
=
of a rate-meter with low and high voltage supplies and electronic alarm circuits. The detector uses a scintillation phosphor with Boron-10 as the energy conversion principle. The nominal alarm set point is 10 mrem /hr. Emergency power and failure alarm function is provided. The neutron criticality monitors shall be calibrated semiannually.
s 3.2.3.5 Counting Equipment 3.2.3.5.1 Sharp Low Beta - Air samples and effluent samples may be counted on this instrument. This instrument utilizes a 4,5-inch and a 2.5-inch very thin end window proportional detector. Back-grounds and counter response are tested weekly and the instru-ment is calibrated annually.
3.2.3.5.2 Beckman Wide Beta - Air samples and effluent samples may be counted on this instrument.
It utilizes two 2.5-ir.ch very thin end window proportional detectors. Backgrounds and counter response are tested weekly and %e system is calibrated annually. The manual detector 1s used inf requently and it is tested when used.
_r 3.2.3.5.3 Tennelec LB-5100 - Air samples (breathing zone and area) and smear samples may be counted on this instrument. The LB-5100 is an automatic alpha / beta proportional counting system with a user definable reporting format. System background is checked weekly.
Performance checks with alpha and beta standards are run daily or with each batch of samples whichever is less frequent. The LB-5100 is calibrated annually.
-3.2.4 Internal and External Exposure 3.2.4.1 Ventiletion Ucense No SNM 778 Docket No.70-824 Date July,1990 Amendment No.
10 Revision No.
13 Page 3-6 Babcock &\\Wilcox a McDermott company
k 3.2.4.1.1 lhe minimum air velocity across the opening of fume hoods tnat are used to handle licensed material shall be at least 100 fpm.
Hood face velocities shall be measured monthly. Those hoods that do not meet the minimum requirement shall be placed out of service.
3.2.4.1.2 The maximum differential pressura across HEPA filters shall be limited to 4-inches of water, except the hot cell filters which shall be limited to 5-inches of water. HEPA filters shall oe changed to prevent exceeding these limits. The di'ferential pressure across HEPA filters shall be checked weekty.
3.2.4.1.3 The minimum differential pressure across the hot cell face shall be 0.25-inches of water. The differercial pressure across the hot cell face shall be checked weekly. An additional hot cell fan will be automatically or manually started when the i
differential pressure reaches 0.-25-intnes of water.
3.2.4.2 Air Sampling and Analysis i
3.2.4.2.1 Continuous air sampling shall be performed in all areas where, in the judgment of the Supervisor, Health Physics there exists the potential for exposing personnel to concentrations of I
airborne radioactive materials in excess of 10% of the appli-i cable MPC.
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3.2.4.2.2 Air sampling filters shall be changed daily in areas where I
si le evaluations indicate concentrations of airborne radio-l accive materials in excess of 10% of the applicable MPC, 3.2.4.2.3 Air sampling filters shall be changed weekly in areas where sample evaluations indicate concentrations of airborne radio-i active materials less than or equal to 10% of the applicaDie MPC.
3.2.4.2.4 Preliminary evaluation of air sample filters shall be performed within the next working day following their removal. Final evaluation of air sampling filters shall be performed within 7 i
working days following their removal.
1 3.2.4.2.5 An investigation by a Health Physicist shall be performed into the cause of unexpected air sampling results that indi: ate air-borne activity at levels between 10% and 25% of the applicable MPC. The Health Physicist shall assign responsibility for completion of any actions that may be indicted by the investi-gation.
l License No SNM 778 Docket No. 70 824 Date July,1990 Ammedmont No.
10 Revision No.
13 Page 3.- 7 Babcock &Wilcox a McDermott company
3.2.4.2.6 An investigation by the Supervisor, Health Physics shall be performed into the cause of unexpected air sampling results that indicate airborne activity at levels exceeding 25% of the appli-cable MPC. The Supervisor, Health Physics shall be responsible for specifying corrective actions and assuring that the specified actions are taken.
3.2.4.2.7 If fixed air samplers are used to determine concentrations of airborne radioactivity ir, the worker's breathing zone, the representativeness of the samplers shall De determined at least once every 12-months.
3.2.4.3 bioassay, 3.2.4.3.1 Uranium Bioassay Program
- 1. The uranium bioassay program sampling fr equency shall comply with Regulatory Guide 8.11 June, 1974, except as specified in section 1.8 of this application.
- 2. All workers who routinely work in uranium handling areas shall be subj2ct to the uranium bioassay program. The follow-ing are the action criteria for the routine uranium bioassay program:
Action Analysis i.evel Action to be Taken
- a. Urinalysis
< 9 ug/l None
- b. Urinalysis 9-16 ug/l
- 1. Determine if a'ea surveys support the analysis results.
- 2. If #1 is positive, investi-gate and correct as needed.
- 3. Make sure individual is in-vivo counted during the next time that the body counting service is at the b8W site.
- c. Urinalysis
> 16 ug/l
- 1. Restrict the worker from further exposure. Resample the individual within 5 working days.
License No SNM 778 Docket No. 70 824 Date July,1990 Amendment No.
10 R* vision N,.
13 Page 3-8 Babcock &Wilcox a McDerrr:ott company
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- 2. Determine if area surveys support the analysis I
results.
- 3. If #2 is positive, investigate the cause and correct as needed.
- 4. If exposure is confirmed by
- 2, investigate to determine how exposure was incurred l
and correct it.
If the ex-i posure exceeds 50% of the i
maximum permissible annual 1
dose, the worker shall be restricted from further i
exposure until the Super-visor, Health Physics authorizes the lifting of i
the restriction.
i
- d. In vivo
< 30 ug None j
U-235 j
- e. In vivo 30-120 ug
- 1. Determine if area surveys U-235 support the analysis results.
- 2. If #1 is positive, investi-gate and correct as needed.-
- f. In vivo
> 120 ug
- 1. Resample the individual U-235 within 10 working days, i
- 2. Determine if 6rea surveys support the analysis results.
- 3. If #2 is positive, investi-gate the cause and correct as needed.
- 4. If exposure is confirmed by i.
- 1, investigate to determine how exposure was incurred and correct it.
If the ex-i Lloonee No SNM 778 Docket No.70-824 Date July,1990 L
l Amendment No, 10 Revision No.
13 Page 3-9 Babcock &Wilcox a McDermott company
posure exceeds 120 ug, the worker shall be restricted from further exposure until the Supervisor, Health Physics authorizes the l
lifting of this restriction.
i 3.2.4.3.2 Plutonium Bioassay Program
- 1. All workers d o routinely work in Plutonium handling areas shall be subject to the Plutonium bioassay program. The minimum frequency for urine sampling shall be six months. The minimum frequency for in vivo counting shall be annual. Ad-ditional bioassays shall be performed when, in the judgment of the Supervisor, Health Physics conditions during a job and/or other data (air. semples, floor smears or clothing con-tamination) indicate an internal exposure may have occurred.
i
- 2. The following are the action criteria for the routine Plu-tonium bioassay program:
Action Analysis
_ Level Action to be Taken 6
- a. Urinalysis
< 0.2 dpm/L None
- b. Urinalysis
> 0.2 dpm/L
- 1. Resample the individual within 5 working days.
- 2. The Supervisor, Health Physics shall consider the need for worker restriction to prevent further exposure until the diagnostic evalu-ation is complete. Only the Supervisor, Health Physics may lift any work restriction i
once it is imposed.
- 3. Determine if area surveys support the analysis results.
- 4. If #3 is positive, investi-gate the cause and correct.
License No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
10 Revision No.
13 Page 3-10 Babcock &Wilcox a McDermott company
- 5. If the exposure is confirmed by #1 investigate to de-termine how exposure was incurred and correct it.
If the exposure exceeds 50% of the maximum permissible annual dose, the worker shall be restricted from further exposure until the i
Supervisor, Health Physics authorizes the lifting of this restriction.
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- c. In vivo
< 1.6E-8 Ci None Pu-239
- d. In vivo
> 1.6E-8 Ci
- 1. Restrict the worker from Fu-239 further exposure.
l
- 2. Resample the individual within 10 working days.
- 3. Determine if area surveys support the analysis results.
- 4. If #3 is positive, investi-gate the cause and correct as needed.
- 6. If exposure is confirmed by
- 2, the Supervisor, Health Physics shall determine the organ dose.
If the confirmed exposure exceeds 50% of the maximum per-missible annual dose, the l
worker shall be restricted from further_ exposures untii the Supervisor, Health Physics authorizes the lifting of this restriction.
- 6. The restriction in #1 may be lif ted by the Supervisor, Health Physics if the License No SNM 778 Docket No. 70 824 Date July,1990 Amendment No.
10 Revision No.
13 Page 3-11 Babcock &Wilcox a McDermott company
results of the analysis per-formed under #2 fails to confirm the analysis.
3.2.4.3.3 Fission Product Bioassay Program l
- 1. The fission product bioassay program sampling frequency shall comply with Regulatory Guide 8.26, September,1980.
- 2. Additional bioassays shall be performed when in the opinion of the Supervisor, Health Physics, conditions during the job were such that significant internal exposure may have occurred. The following are action criteria for additional bioassays.
Action i
Analysis Level Action to be Taken in vivo
>10% MP0B Remeasure subject to determine effective half life of the contami-nant and plot decay curves.
Follow-up program will continue until the contamination present is
<5% MP0B or the effective half life has been determined.
Estimation >10% MP0B Submit in vitro sample for analysis from nasal within 5 v^rking days, smears or air sample in vitro
>5% MP0B Resample excreta to confirm presence of contamination and to establish rate of elimination.
Perform isotopic analysis if >10%
of MP0B is a possibility, in vitro
>10% MP0B in vivo measurement to be made as I
soon as practicable.
- 3. The Supervisor, Health Physics shall be responsible for evaluations to determine the location and amount of depo-sition; to provide data necessary for estimating internal dose rates, retention functions, and dose commitments; and to License No SNM 778 Docket No.70-824 Date July,1990 Amendment No.
10 Revision No.
13 p.,,
3-12 Babcock &Wilcox a McDermott company
L determine if work restrictions or referrals for therapeutic treatmeist are required for any case where a result indicating a greater than 10%/MP0B deposition of a radionuclide is verified.
3.2.4.4 Protective Clothing 3.2.4.4.1 The use of protective clothing shall be specified in Area Operating Procedures and Radiation Work Permits.
3.2.4.4.2 Protective clothing may also be specified by the Health Physics Group.
In the event of conflicts between the Area Operating Procedure Radiation Work Permit, and the Health Physics Group, the decision of the latter shall prevail.
3.2.4.5 Respiratory Protection 3.2.4.5.1 The Respiratory Protection Program shall be conducted in ac-cordance with 10 CFR 20.103, and shall be a responsibility of the Health Physics Group.
3.2.4.5.2 The Respiratory Protection Program shall be implemented through written and approved procedures.
3.2.4.6 Surface Contamination Monitoring 3.2.4.6.1 The Health Physics Group shall perform smear surveys in the below listed areas at the indicated minimum frequencies:
1 L
Action Level Area Frequency (dpm/100cm2)
)
i
<.........................--ALPHA.--.--------.----.---.--.>
1 Unirradiated, unencapsulated Weekly 5000 l-fuel handling areas Building B Counting Lab.
Monthly 200 Hot Cell Oper. Area Monthly 200 L
Scanning Electron Monthly 200 Y
Microscopy Lab.
i l
Exit portals from Biweekly 200 controlled areas 1
l License No SNM 778 Docket No. 70 824 Date July,1990 Amendment No.
10 Revision No.
13 page 3-13 Babcock &Wilcox a McDermott company
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<-----------------------BETA + GAMMt.---------------------->
Building B Counting Lab.
Monthly 2000 Scanning Electron Monthly 2000 Microscopy Lab.
Hot Cell Operations Area Bimonthly 2000 Cask Handling Area Bimonthly 22000 Radiochemistry Lab.
Bimonthly 22000 Exit portals from Biweekly 2000 controlled areas 3.2.4.6.2 Large area smears are used to survey many square meters of surface area. To determine if these smears indicate that an action level has been exceeded, the assumed area covered shall not exceed 1-square meter.
3.2.4.6.3 Daily surveys shall be performed in snack bars and vending machine areas located within the restricted area and in the cafeteria. Weekly surveys shall be performed in snack bars and vending machine areas in the unrestricted areas on site.
If contamination is detected in any of these areas, corrective action shall be taken at once.
3.2.4.7 Decontamination 3.2.4.7.1 The Health Physics Group shall determine and direct the actioa to be taken to protect personnel and reduce the levels of contamination below those specified in Section 3.2.4.6.
3.2.4.7.2 Decontamination to reduce icvels of contamination shall begin
. ithin 24-hours of the disctvering survey.
If the survey is w
made just prior to the beginning of a holiday or weekend, the contamination shall be marked and-labeled, and decontamination shall commence during the first regular workday af ter the survey.
3.2.4.7.3 Fixed contamination that, in the opinion of the Supervisor, Health Physics does not substantially contribute to a worker's exposure, shall be posted and its location and radiation level recorded and its removal shall be scheduled as soon as practicable.
License No SNM 778 Docket No. 70 824 Date July,1990 3-14 Amendment No.
10 Revision No.
13 Pay Babcock &Wilcox a McDermott company
3.2.4.7.4 Fixed contamination that, in the opinion of the Supervisor, Health Physics may substantially contribute to workers' exposure shall be posted and removed as soon as practicable.
3.2.4.8 Emergency Evacuation 3.2.4.8.1 Refer to Radiological Contingency Plan, required by Order dated February 11, 1981, as amended.
3.2.4.9 Personnel Monitoring 3.2.4.9.1 Site Workers (Restricted Area) shall be issued a film badge, a thermoluminescent dosimeter (TLD), and either a self-reading dosimeter (SRD) or an indirect-reading dosimeter (IRD).
3.2.4.9.2 Site Workers (Controlled Areas) shall be issued a film badge, a TLD, and either a SRD or an IRD.
3.2.4.9.3 Visitors shall be issued a TLD.
3.2.4.9.4 Non-Site Workers (Restricted Area) shall be issued a film badge, a TLD, and either a SRD or an IRD.
3.2.4.9.5 Non-Site Workers (Controlled Areas) shall be issued a film badge, a TLD, and either a SRD or and IRD.
3.2.4.9.6 Film badges and TLD's that are issued pursuant to 10 CFR 20.202 shall be processed and evaluated monthly.
3.2.4.9.7 Whole body dose equivalents to workers shall be limited to 300 mrem / week and 1.25 Rem / quarter by the appropriate Area Supervisor.
J i
License No SNM 778 Docket No.70-824 Date July,199D Amendment No.
10 Revision No.
13 Page 3-15 Babcock &Wilcox a McDermott company
4.0 NUCLEAR CRITICALIT) SAFETY l
4.1 SPECIAL ADMINISTRATIVE REQUIREMENTS 4.1.1 Double Contingency Policy - The Doubic Contingency Policy as de-fined in the American National Standard ANSI /ANS-8.1-1983 shall be followed in establishing the basis for nuclear criticality safety of all operations.
4.1.2 Structural Integrity - Where structurai integrity is necessary to provide assurance for nuclear criticality safety, the design and construction of those structures will be evaluated with due regard to load capacity and foreseeable abnormal loads, accidents, and deterioration. The Manager, Industrial Engineering shall be l
responsible for determining the structural integrity of equipment when it is necessary to provide assurance of nuclear criticality safety.
4.1.3 Nuclear Criticality Safety Evaluation - All modifications or additions or both to any operation, system or equipment must be approved by the Licensing & Compliance Officer.
It is the responsi-bility of the Licensing & Compliance Officer, in consultation with the Nuclear Criticality Safety Officer, to determine whether or not a nuclear criticality safety evaluation is required for the proposed modi 71 cation or addition. The Nuclear Criticality Safety Of ficer or a person designated by him shall provide any required evaluations, including calculational support.
Nuclear criticality safety evaluations shall be reviewed by a second individual, either the Nuclear Criticality Safety Officer or by a person with the same minimum qualifications required for the Nuclear Criticality Safety Officer.
4.1.4 Posting - Each unit shall be posted with the limit. of SNi4 per-mitted in the unit. The Licensing & Compliance Officer shall be 7
responsible for approving the posting of nuclear criticality safety limits.
4.1. F.
Labeling - Each container containing greater than 0.5 grams of SNM shall be labeled to show the amount of element, the percent enrichment, when applicable, and the amount of fissile isotope.
This condition does not apply to irradiated SNM.,
4.1.6 Compliance.- Compliance with the nuclear criticality safety require-ments shall be in accordance with written area operating procedures, reviewed and approved by the Licensing & Compliance Officer, the Lloonee N o SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
10 Revision No.
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Supervisor, Health Physics, the Indt.strial Saf ety Of ficer, the l
Huclear. Criticality Safety Officer, and the SRC. Area operating procedures shall include all the controls and limits significant to the nuclear criticality safety of the operation. In addition, the if helear Criticality Safety Officer shall perform a quarte:1y audit 5
for compliance with nuclear criticality safety requirements and verify that process conditions have not been altered that may I
affect nuclear criticality safety. The results of the audit shall be documented and submitted to the Manager, SS.
TECHNICAL PE0VIREMENTS 4.2 4.2.1 Huclear Isolation - When nuclear isolation is required (the i
potential neutronic interaction between units is negligible) the Unit or units isolated shall be separated from all other SHM by one
[
of the following or equivalent conditions:
1.
Twelve inches of water.
3 2.
Twelve inches of concrete with density of at least 140 lb/f t when the unit (s) being nuclearly isolated are one of the units permitted by this license, (i.e., a mass limit specified in Section 4.2.2.2 or an authorized PWR or BWR fuel assembly or portion thereof, pursuant to Section 4.2.2.7.1) provided that ea the unit or units cannot be representable as a slab which interacts with other SNM primarily through its major face.
3.
The edge-to-edge separation of 12-feet, or the greatest distance across an orthographic projection of either accumulation on e plane perpendicular to a line joining their centers, whichever is larger.
L 4.2.2 Building B
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4.2.2.1 General - Building B shall be limited to 40 units, excluding the hot cells, underwater storage, and the examination of power reactor g
fuel assemblies. Each unit shall be separated from adjacent units by at least 8-inches edge-to-edge and 24-inches center-to-center, h
4.2.2.2 Unit Limits - Each unit shall be limited to one of the following:
4.2.2.2.1 Mass limits for mixtures of plutonium and U-235
- h i
Lkanse No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
10 Revision No.
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t b
4 Scrap, including rod segments, shall be disposed of according to present NNFD-RL procedures and limits.
l 4.2.3 Outside Storage 4.2.3.1 General - Outside storage consists of underground storage, ship-ments, and.the fenced storage area located adjacent to Building J.
4.2.3.2 Underground Storage - Radioactive materials stored in underground storage tubes shall be limited to one SNM unit per tube, with values as specified in section 4.2.2.2 of this Part. Tubes shall be spaced 20-inches center-to-center and are 5-inches in diameter, and totally immersed in concrete.
4.2.3.3 Shipments - Each shipment of fissile material being stored out~
side must conform with all license requirements for the type of shipping container. Additionally, each shipment must be i
nuclearly isolated from all other SNM.
4.2.4 Dry Waste 4.2.4.1 Dry waste is waste that is free of liquids but not necessarily free of hydrogenous material. Dry waste shall be accumulated in steel drums or steel containers with a minimum size of 30 gallons (114 liters) and a maximum of 45 grams of SNM per container. These con-tainers may be located throughout the laboratories as required to collect contaminated laboratory waste. Filled containers are trans-ferred to either the radioactive waste storage building or to the temporary storage facility. Containers of unirradiated SNM shall be gamma scanned before transfer to verify that the 45 grams SNM per container limit is not exceeded.
Drums containing irradiated SNM are not gamma scanned. The amount of SNM per container is based on a mass balance difference.
The amount of waste generated within any hot cell or unit handling irradiated fuel is equal to the difference between the mass of SNM transferred into the unit, less the mass of SNM transferred out. Dry waste in containers with less than 0.5 grams of unirradiated SNM per container may be stored in the fenced, locked and paved outside storage area adjacent to Building J.
License No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
10 Revision No.
13 Page 4-10 Babcock &Wilcox a McDnmott company
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'5 1 3 6 Waste tanks that indicate concentrations of activity greater than those specified in section 5.1.3.2 shall be appropriately diluted prior to release.
5.1.3.7 The NNFD must approve the release of liquid waste to their waste treatment facility prior to the release.
5.1.3.8 The 10,000 sq. ft. Storm Drain Collection Pond shall be grab sampled quarterly. The sample shall be analyzed for gross alpha and gross beta.
5.1.4 Gaseous Effluent - Discharge air from process areas is released to the general environment through the 50-meter high stack. The discharge rate of the stack is approximately 20,000 cubic feet per minute. The annual discharge volume is 1.1E10 cubic feet. Planned discharges to the air shall be in compliance with 40 CFR 61. The annual exposure resulting from these planned discharges shall not exceed 25 millirem whole body and 75 millirem t'o any organ.
5.1.4.1 Action levels - The action levels for releases from the stack are specified in section 3.2.2.5 of this Part 1.
1 5.1.4.2 Analyses - The fixed filter of the stack particulate monitor shall be counted on the Low Beta or Wide Beta counting system, after an appropriate decay period. The results shall be recorded and maintained on file.
5.1.4.3 Sampling - The stack shall be sampled isokinetically on a continu-ous basis.
5.1.4.4 Monitoring - The stack sample shall be passed through a monitoring system that consists of the following:
1.
Particulate Monitor - The stack particulate monitor consists of an alpha and beta channel, with a dual channel ratio de-tector. This monitor uses a fixed filter and a nominal sampling flow rate of 2 - 3 cubic {eet per minute. The de-tector is a thin window (1.0 mg/cm ) gas flow proportional detector. Alpha and Beta-gamma radiations are monitored through two single channel ana'lyzers and log rate meters. The ratio between these two channels is also displayed as a loga-rithmic ratio. This system effectively compensates for the presence of Radon and Thoron daughters and increases the sen-sitivity of the system. Alpha and Beta-gamma sensitivities License No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
10 Revision No.
13 5-2 Pap i
Babcock &Wilcox a McDermott company i
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7.0 DECOMMISSIONING PLAN j
The site is committed to decommissioning the facilities which have i
been uted for the use and storage of licensed material at the end of their useful life. At the time of this application for renewal of License No. SNM-778, two programs arr - V way to decommission Buildings A and C.
It is presently e ':w id that these two facili-l ties will be decontaminated and ready w release for unrestricted use i
by March, 1987.
7.1 PLANNING CONSIDERATIONS I
7.1.1 The history of the facility shall be determined to facilitate the identification of services, equipme.9, and areas that should be included in the survey plan.
3 7.1.2 The decontamination of facilities and equipment must meet the levels of contamination specified in Table 1, " Acceptable Surf ace Contamination Levels" in " Guidelines for Decontamination of Facili-ties and Equipment Prior to Release for Unrestricted Use or Termi-nation of Licenses for Byproduct, Source, or Special Nuclear Material," dated May, 1987, as amended.
in addition, a reasonable effort will be made to further reduce contamination levels to those which are as low as reasonably achievable.
7.1.3 No covering will be applied to remaining surfaces until it has been determined that contamination levels are below those of Table 1, l
" Acceptable Surf ace Contamination Levels" in " Guidelines for Decon-l tamination of Facilities and Equipment Prior to Release for Varestricted Use or Termination of Licenses for Byproduct Source, or Special Nuclear Material," dated May,1987. as amended, and until it has been determined that a reasonaLie effort has been made to further reduce contamination below those specified above.
7.1.4 The radioactive contamination of interior surfaces of pipes, duct-work, and other conduits will be determined by taking measurements at all traps and other appropriate access points, provided contami-nation at these locations is likely to be representative of interior e
conditions.
If such access locations are not likely to be' represen-t tative, or if interior surfaces are inaccessible, the interior surfaces will be assumed to be contaminated in excess of levels specified in Table 1
" Acceptable Surface Contamination Levels" in l
" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct.
Source, or Special Nuclear Material," dated May,1987, as amended.
License No SNM 778 Docket No.70-824 Date July, 1990 i
Amendment No.
10 Revision No.
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7.1.5 A radiological survey plan shall be designed and implemented to assess the extent of decontamination necessary. The survey plan will include the taking of smear samples of roofs, ceilings, walls, floors, and equipment.
It shall also include the taking of core samples of concrete floors, walls, ceilings and pools. Core samples shall also be taken of soil beneath ficors and pools and in the vicinity of under ground drainlines. Records of the survey and sample results shall be prepared and maintained.
7.1.6 Equipment will be disposed of by burial or sale. The decontami-nation of equipment scheduled for burial will be sufficient to meet the requirements of transportation and those of the receiving facility. The decontamination of equipment scheduled for sale to a licensed facility will be sufficient to meet the requirements of transportation and those of the receiving facility. Equipment scheduled for receipt by a non-licensee shall be decontaminated to levels specified in Table 1
" Acceptable Surface Contamination Levels
- in " Guidelines for Decontamination of Facilities and Equip-ment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated May, 1987, as amended.
7.1.7 At the completion of decommissioning activities, a report of the final survey shall be prepared and submitted to the NRC with a request that a confirmatory inspection be made and that the
'i facility be released for unrestricted use.
7.2 COST AND FINANCIAL ARRANGEMENTS 7.2.1 Financial Arrangenents - Financial arrangements to cover the cost of decommissioning are set forth in the letter dated September 16, 1985, from L. V. Jordan, Assistant Controller.
7.2.2 Cost Estimate Guidelines - The following are the general guidelines upon which the estimates are based.
7.2.2.1 No facility will be razed.
7.2.2.2 No "mothballing" of any facility or perpetual surveillance is contemplated. All facilities will be released for unrestricted use upon approval by NRC.
7.2.2.3
" Reasonable" efforts to decontaminate below levels specified in Table 1, " Acceptable Surface Contamination Levels" shall be required l
only-to the extent that the benefits derived clearly justify the additional cost expenditures.
License No SNM 778 Docket No. 70 824 Date July, 1990 Amendment No.
10 Revision No.
13 Page 7-2 Babcock &Wilcox a McDermott company
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i TABLE OF CONTENTS
{
4 Section Page 9.0 OVERVIEW 0F 0PERATION.
9-1 i
9.1 CORPORATE INFORMATION..
9-1 l
[
9.2 FINANCIAL QUALIFICATIONS.
9-2 9.3
SUMMARY
OF OPERATING OBJECTIVE AND PROCESS.
9-3 9.4 SITE DESCRIPTION 9-3 9.5 LOCATION OF SITE BUILDINGS 9-4 i
9.6 LICENSE HISTORY.
9-4 l
9.7 CHANGES IN PROCEDURES, FACILITIES, AND EQUIPMENT.
9-5 l
List of Figures Figure Fdge 9-1 SITE LOCATION IN VIRGINIA 9-7 9-2 FIVE MILE RADIUS OF SITE.
9-8 9-3 SITE BUILDING LAYOUT 9-9 l
9-4 FACILITY WORK ORDER FORM.
9-10 i
l.
f l
l l
l:
License No SNM 778 Docket No.70-824 Date July, 1990 i
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Amendment No.
Revision No.
Page i
Babcock &Wilcox a McDermott company i
PART 11 SAFETY DEMONSTRATION 9.0 OVERVIEW OF OPERATION 9.1 CORPORATE INFORMATION
9.1.1 LICENSEE
BABC0CK & WILCOX INVESTMENT CO.
BABC0CK & WILCOX NAVAL NUCLEAR FUEL DIVISION NNFD RESEARCH LABORATORY
9.1.2 Address
Babcock & Wilcox Naval Nuclear Fuel Division NNFD Research Laboratory P. O. Box 11165 Lynchburg, Virginia 24506-1165 9.1.3 Principal Of fices:
Babcock & Wilcox Investment Co.
l Babecek & Wilcox 1010 Common Street P. O. Box 60035 New Orleans, Louisiana 70160 9.1.4 Principal Officers:
Robert E. Howson l
Chairman of the Board &
Chief Executive Officer 1010 Common Street P. O. Box-60035 New Orleans, Louisiana 70160 U. S. Citizen License No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
10 Revision No.
13 Page 9-1 Babcock &Wilcox a McDermott company
John A. tynott Executive Vice President r
Chief Financial Officer 1010 Connon Street P. O. Box 60035 New Orleans, Louisiana 70160 U. S. Citizen 9.1.5 State of Incorporation:
Delaware 9.1.6 Alien or Foreign Control:
Babcock & Wilcox is incorporated under the laws of the State of Delaware.
In 1978 McDermott Inc., a Delaware corporation, acquired Babcock & Wilcox.
In 1983 McDermott International, Inc., incorpo-rated under the laws of the Republic of Panama, became the parent company of the McDermott group of companies. This reorganization was reviewed by the NRC prior to its implementation.
In a letter dated December 17, 1982, to Mr. J. H. MacMillan, William Dirks summarized the Commission's finding that the change was not inimical to the common defense and security or the health and t
safety of the public. Based on this conclusion, the change was approved under Section 104(b) of the Atomic Energy Act as it related to the operation of a critical experiment reactor owned by Babcock & Wilcox at the site.
Such approval was_not required under the Act for material licensees.
In July of 1990, the Babcock &
Wilcox investment Company (BWICO), incorporated under the laws of the state of Delaware, became the parent company for Babcock &
Wilcox. B&W is a wholly-owned subsidiary of BWIC0 and BWICO is a wholly-owned subsidiary of McDermott, Inc.
9.2 FINANCIAL QUALIFICATIONS i
9.2.1 The financial qualifications of the Corporation to continue opera-i tions at the site and to perform the necessary deconnissioning at the end of plant life will be submitted by July 27, 1990 in ac-cordance with 10 CFR 70.25.
License No SNM 778 Docket No.70-824 Date July,1990 Amendment No.
10 Revision No.
13 p.g.
9-2 Babcock &Wilcox a McDermott company
i i
9.3
SUMMARY
OF OPERATING OBJECTIVE AND PROCESS 9.3.1 Activi',ies, utilizing licensed material, are conducted at the site l
in support of the operating divisions of Babcock & Wilcox and for 1
other companies and government organizations. The broad range of i
projects that have been conducted pursuant to the license cannot be
]
described in terms of through-put or any single process. Radio-active materials are handled and stored, principally in Building B.
1 That building houses the Hot Cells, Radiochemistry Laboratory, i
Scanning Electron Microscopy Laboratory Metallurgy Laboratories, Analytical Chemistry Laboratory, Fatigue and Fracture Laboratory, l
Failure Analysis Laboratory Crane and Cask Handling Area, a Hot 1
Machine Shop, the Counting Room, and a Health Physics Laboratory.
i Licensed material in the form of liquid waste is collected in tanks E
that are located -in the Liquid Waste Disposal Facility. The l
laundry is located in the Liquid Waste Disposal Facility.
Solid radioactive waste is stored in Building J, the Annex to Building J, the storage area adjacent to Building J and the Temporary Storage Facili ty.
i 9.4 $1TE DESCRIPTION l
The site is located on the James River about four miles east of Lynch-burg, Virginia.
The site, which comprises 525 acres, lies within Campbell County and borders on Amherst County. The site occupies about 13.6 acres of the site.
The location of the site within the Commonwealth of Virginia is shown in Figure 9-1.
l The irregularly shaped property is bounded on three sides by a large loop of the James River and on the fourth side by State Route 726, I
which closely' follows the base of Mount Athos, Th's mountain rises i
rapidly from about 500 feet MSL to 900 feet MSL, making.it the dominant feature of the surrounding landscape.
The Babcock & Wilcox property consists of large sections of relatively flat floodplain along the James River lying at about 470 feet MSL. The interior of i
the property is largely composed of rolling hills, one of which rises to almost 700 feet MSL. The site location with respect to a five mile radius is shown in Figure 9-2.
The land in the immediate vicinity of the plan: is sparsely inhabited.
The severe topography makes it unsuitable for commercial farming. The Lynchburg Foundry, a producer of light metal castings, occupies a I
parcel of land which abuts the south boundary of the Babcock & Wilcox 1
property. The Foundry is approximately.5 miles from the site.
License No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
Revision No.
10 13 Page 93 L
Babcock & Wilcox a McDermott company 1
I The site is serviced by a spur of the Chessie System Railroad which runs through the Babcock & Wilcox property. The property is also conveniently located for truck and automobile access. About three miles from the site, State Route 726 connects with U.S. Highway 460, a major link between Roanoke and Richmond. The site is located about 100 feet above the James River and for that reason no dams on the rive' would threaten the site should they fail.
9.5 LOCATION OF SITC BUILDINGS 9.6.1 Figure 9-3 shows the layout of buildings at the site. All buildings are of masonry construction.
9.6 LICENSE HISTORY, 9.6.1 License SNM-778 was issued on September 16, 1966.
Since that time the following renewals and amendments have been approved:
February 15, 1974 First renewal July 21,1980 Second renewal August 28, 1981 Amendment No. 1, approved a change in the organization.
February 25, 1982 Amendment No. 2, approved the Radiological Contingency Fic..
May 11. 1982 Amendment No. 3, approved the reduction in the possession limit for unitradiated Pu to 0.9 kilograms May 14, 1982 Amendment No. 4, added four license conditions requiring surveys of 8 & W and railroad property and established a restricted zone.
August 11, 1983 Amendment No. 5, approved the reduction of the possession limits of SNM to below one effective kilogram.
February 28, 1984 Amendment No. 6, approved a revision to the Radiological Contingency Plan.
November 6, 1984 Amendment No. 7, approved a revision to the definition of the Restricted Area.
License No SNM 778 Docket No.70-824 Date July, 1990 Amendment No.
10 Revision No.
13 Page 9-4 I
Babcock &Wilcox a McDermor, company s
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July 25, 1985 Amendment No. 8, approved the extension of the expiration date of the license to January 1, 1986.
October 15, 1985 Amendment No. 9, approved a change in the organization.
9.7 CHANGES IN PROCEDURES, FACILITIES, AND EQUIPMENT l
9.7.1 Changes in Procedures - Changes, revisions, or additions to Area Operating Procedures are submitted to the Licensing & Compliance Officer. The Licensing & Compliance Officer is responsible for assuring that changes are reviewed as required on the procedure
' (
form. Area Operating Procedures (AOP) must be reviewed and approved by the Nuclear Criticality Safety Officer, Supervisor, Health Physics, Licensing & Compliance Officer, the Industrial Safety Officer, and the Safety Review Committee.
[
Changes and revisions to A0P's may be implemented after the change has been approved by the Nuclear Criticality Safety Officer, Super-i visor, Health Physics, the Industrial Safety Oficer and the Licensing & Compliance Officer.
The Licensing & Compliance Officer l
1s responsible for assuring that the change is placed on the agenda of the Safety Review Committee at their next regularly scheduled
- meeting, l
9.7.2 Changes in Facilities - Changes and modifications to buildings, exhaust ventilation systems, emergency electrical systems, and r
other facilities and services that may affect the safe handling of l
licensed material are requested on the Facilities Work Order Form
- (Figure 9-4). These forms are first submitted to the Plant Engi-l neering Supervisor.
He shall determine if the requested change involves a " Facility Change."
If a facility change is involved, the work order is forwarded to the Licensing & Compliance Officer.
It is the Licensing & Compliance Officer's responsibility to assure l
that all safety and licensing considerations have been addressed.
l He shall assure that the change is approved by the Industrial Safety Officer and the Supervisor, Health Physics. He snall l
determine if the change requires an amendment to the license.
(.
Completed forms are kept on file by the Plant Engineering Super-visor and are audited monthly by the Health Physics Group.
l l
L License No SNM 778 Docket No.70-824 Date July, 1990 p
Amendment No.
10 Revision No.
13 Page 9-5 Babcock &Ullicox a McDermott cortpany
l 1
9.7.3 Changes in Equipment - Changes or modifications in equipment which l
is used to handle licensed material are requested on the Facility Work Order Form. This form is submitted to the Plant Engineering Supervisor who determines that the change or modification involves I
a piece of equipment involved in licensed work.
If he determines i
that the change does involve such equipment, he forwards the form to the Licensing & Compliance Officer. The Licensing & Compliance Officer exercises the same responsibilities as those described in i
Section 9.7.2, above, l
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i License No SNM 778 Docket No.70-824 Date July, 1990 l:
- Amendment No.
10 Revision No.
13 Page 9-6 I
Babcock &Wilcox a McDermott company b
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LloonesNo SNM 778 Docket No.70-824 Date July, 1990 Ameruiment No.
10 Revision No.
13 Page 9-9 Babcock &Wilcox a McDermott company
10.2.5.1 The_Onan emergency generator will start automatically on loss of site power and provides emergency power to one Hot Cell exhaust f an, the stack monitoring system, and emergency lighting. This engine / generator is fueled by natural gas and is provided with a i b, source of propane gas as a backup source of fuel. The Onan system is load tested weekly.
10.2.5.2 An Invertastat provides an uninterruptable source of electrical power for the criticality monitors, emeraency evacuation alarm, and the alarm panel in Building B.
The invertastat operates, upon loss of normal site power, from a battery, with sufficient capacity to provide its loads with power for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The invertastat and battery are load tested weekly.
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10.2.5.3 The stack fan is provided with a backup engine which starts auto-4 matically upon loss of normal site power. The fan supplies of f 7
gas for Building B.
It is coupled to the f an shaf t by a cen-O trifugal clutch, such that when the engine speed equals the fan 6
speed, the clutch engages. The engine is fueled with natural gas and this is backed up by a source of propane gas. The emergency h
fan engine is load tested weekly.
10.3 HEATING, VENTILATION, AND AIR CONDITIONING
=
10.3.1 Heating - Space heating in Buildings A, B, and C is provided by gas fired boilers. The room air in Buildings A and B is partially recirculated. Rc7m air in Building C is recirculated.
10.3.2 Ventilation 10.3.2.1 Building A - Building A has been decommissioned. The ventilation l
consists of the normal room air heating and air conditionirg. No special ventilation is required and none is provided.
License No SNM 778 Docket No.70-824 Date July,1990 Amendment No.
10 Revision No.
13 P.nge 10-2 Babcock &Wilcox a McDermott company
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License No SN4778 Docket Wo.70-824 Date July,1990 Amendment No.
10 Revision No.
13 Page 10-10 Babcock &Wilcox a McDermott company
1 3.
Administering the respiratory protection program 4
Administering the bioassay program 5.
Leak testing radioactive sources 6.
Supervising shipping and receiving of licensed material 7.
Supervising and coordinating 1.he waste disposal program 8.
Assisting in personnel, equipment, h.td facility 6 contamination 9.
Conducting radiation safety training 10.
Providing expertise in all aspects of radiation protection
- 11. Generating, maintaining and distributing records and reports that are required by HRC regulations or Health Physics procedures
- 12. Providing expertise in health physics to the Licensing &
Compliance Officer.
11.1.8 Industrial Safety Officer - The Industrial Safety Officer reports to the NNFD Manager, Health and Safety.
His responsibilities include the followir.g:
1.
Administering the industrial safety program 2.
Reviwing proposed facility changes to ensure fire safety 3.
Providing expertise in fire prevention to the Licensing &
Compliance Officer and the Safety Review Committee 4.
Performing terts, maintenance, and inspection of fire protection, control, and extinguishing equipment 5.
Providing training for the site Emergency Retntese Team and off l
site support agencies 6.
Inspecting all areas of the site periodically to ensure:
a.
Proper storage and use of flammable solvents b.
Proper placement of fire extinguishing equipment License No SNM 778 Docket No. 70 824 Date July, 1990 Amendment No.
Revision No.
10 13 Page 11-3 I
Babcock &Wilcox l
a McDermott company
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6E ensures that the nrocedure is in the proper format. The Licensing F
& Compliance Officer routes the procedure to the Nuclear Criticality
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Safety Officer who reviews it to assure that any nuclear crii;icality I
safety issues are properly addressed.
If the Nuclear Criticality Safety Officer has additions or corrections, he notes them on the procedure and forwards it to the Supervisor, Health Phvsics.
If E
the Huclear Criticality Safety Officer approves it, he signs the L
procedure in the space provided and forwards it to the Supervisor, Health Physics.
The Supervisor, Health Physics reviews it for proper radiological content.
If he has additions or corrections, he notes them on the procedure and forwards it to the Industrial
=
Safety Of ficer.
If the Supervisor, Health Physics approves the procedure, he signs the procedure in the space provided and forwards it to the Industrial Safety Of ficer. The Industrial Safety Of ficer l
reviews it to assure that any industrial safety issues are properly
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addressed.
If the Industrial Safety Of ficer has additions or T-corrections, he notes them on the procedure and forwards it to the
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Lict.nsing & Compliance Of ficer.
If the Industrial Safety Officer approves it, he signs the procedure in the space provided and forwards it t the Licensing & Compliance Officer. The Licensing &
Compliance Gificer reviews it for general safety and determines its impact on other work and facilities. The Licensing & Compliance
-r Of ficer is responsible for resolving all additions or changes g
recommerided by the previous reviewers. When the procedure is b
approved by the four reviewers, the Licensing & Compliance Officer forwards it to the Safety Review Committee. The Safety Review e
Committee (SRC) may approve the procedure as written, approve the
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procedure conditionally with specific changes to be made prior to issuance or the SRC can disapprove it.
The SRC coordinator signs y
for the SRC when approva'l is vott.d.
The procedure may be inplemented subsequent to SRC approval.
Revisions to A0P's will follow this same approval route, except that
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the revised procedure may be implemented after receiving the approval signatures of the Nuclear Criticality Safety Officer, Supervisor,
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Health Physics, Industrial Safety Officer and the Licensing
' ompl i -
L ance Officer. The revised procedure will be place on the agenda for the next regularly scheduled meeting of the SRC.
A0P manuals shall be placed in areas where the procedures apply.
License No SNM-778 Docket No.
70 824 Date July, 1990 Amendment No.
Revision No.
10 13 Page 11_17 Babcock &Wilcox a McDermott company Y
6.
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3.
Other minor operations requiring respiratory protection t
i are:
changing of HEPA filters, repair wor-k on NPD site support equipment, and any other operation where Health Physics believes that there is a potential of airborne 1
activity.
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12.10.2.3 in-vivo Results (1983) - Wnole body counting was performed by Helgeson Scientific Services. Inc. on 32 workers during 1983.
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Three had detectable activities,.no other workers indicated detectable activity.
The results of the three workers with duectable activity is presented in Table 12-18.
a TABLE 12-18 E.y WHOLE BODY COUNTS - 1983 i
(ALL VALUES IN NAN 0 CURIES)
F Worker lsotope MPBB_
1 2
3 Cs-137 3E4 8+2 4+2 k
- 3. 6E 3 5+2 4+1 h
Co-60 1.1E 3 3+1 7+1 E
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License No SNM-778 Docket No.70-824 Date July, 1990 12-30 Amendment No.
10 Revision No.
13 Page 1
Babcock & Wilcoh a McDermott company
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mg J13.4.3 : Samp11ng' Each of _ the wells will. be sampled on a quarterly basis for two years, beginning in November,1987. Af ter this period, if no action level
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. is exceeded, the sampling interval will be once each year, in the winter or spring.
13.4.4 Analysis Each well sample will be analyzed for gross beta-gamma activity to detect the. presence of Cesium-137 and Cobalt-60, the principle isotopes present in the liquid waste system.
Currently there is no reason to suspect that alpha activity would be g
present in the groundwater since appreciable levels are not being
. detected during the sampling of the storage tenks.
If significant alpha activity is detected during the sampling of the storage tanks, y
then a decision will be made to sample the wells for alpha activity-
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as well:as for beta-gamma.
.13.4.5 Action
- Levels and Actions to be Taken Gross. beta gamma activity exceeding 30 pCi/L will require the following. actions:
1.
Prepare and implement a plan to determine the source of the I
activi ty. This may include the taking of soil core-samples,
. installation of additional wells, checking for alpha activity, and isotopic analysis of tha samples.
'2.
Submission of the report to NRC Region II in the event that the
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- investigation of the elevated levels shows leakage in the tanks.
13.4;6 ' Records!
Records of well sampling and analyses shall-be retained at the NNFD-RL until. the NRC authorizes their disposition These records shall include = the dates when the sanples were taken, sample analysis results, each instance th;.i the action -level was exceeded, the actions taken in response to the exceeded level, any changes made to the system, and all reports made to the NRC.
License No SNM 778 Docket No.70-824 Date July, 1990 10 Amendment No.
Revision No.
Page Babcock &Wilcox
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License No SNM 778 Docket No. 70 824 Date July, 1990 s
l' Amendment No.
Revision No.
Page i.
900%30lGo-o Babcock &Wilcox a McDermott company
4; y
e The following information is to be included:
o Areas visited.
-o Operations observed-o Unsafe practices or situations noted Nuclear safety activity of the quarter (brief summary) o o Recommendations o Resolution of previous recommendations.
14.2 PREFERRED APPROACH TO DESIGN Research and Development activities are performed at the site. While the use of safe geometry is the preferred approach in a production facility.
it is not appropriate nor practical at a research laboratory.
Since most projects require _only small amounts.of SNM on laboratory benches and in-hoods, the preferred approach is through safe masses in simple arrays;
]
-the lattice density model or arrays found in TID-7016 Rev.1 is the adopted model. The one exception to use of safe masses is when examining
.and testing reactor fuel assemblies. The approach:to such uses is to accept only a limited number of fuel assemblies and then to maintain the fuel _ of an assembly ~ within the dimensional envelope. of the-original assembly's dimensions. Where this is not possible, the fuel of an assembly is handled within the dimensions of safe geometry or as a safe mass.
14.3-BASIC ASSlMPTIONS This section describes basic assumptions and evaluations that have been made to demonstrate nuclear criticality safety for the speci-fications of Section 4.2-(Technical Requirements for Nuclear Criti-~
cality Safety).
14.3.1 Huclear Isolation - Special nuclear material is. isolated from all other special nuclear material for nuclear criticality safety pur-poses -if any of the three conditions -(or equivalent) listed in 4.2.1 are met. These three isolation criteria are accepted industrial practice for maintaining nuclear criticality safety. It is recognized that 12 inches of high density concrete may not be
- License No - SNM 778 Docket No.70-824 Du+
, ; ty,1990
' hmendment No.
Revision No.
10 13 age 9 -2 Babcock &Wilcox a McDermott company
m Approval, by the Licensing a Compliance Officer is
)
required to move any other fissile material Into the area where the assemblies are stored. No more than four unirradiated assemblies may-be stored at once.
The limit of four assemblies is an _ arbitrary _ limit which the site imposes upon itself and 'does not affect nuclear safety.
' Partially disassembled unirradiated Mark B or Mark C assemblies may also-be stored in air. This is safe dua to the lower moderation characteristics of air compared to water. Air moderated values of K,ff will be-less than those shown in Table 14-6.
Fuel rods from unirradiated, disassembled Mark B or Mark C assemblies will be stored in air in slabs not to exceed 4 I
inches in height (see Section 14.3.2.6.4, statement 2).
B.
Irradiated Fuel Assemblies - Assemblies which have been irradiated may also be stored in their shipping containers or in the hot cell pool. Storage in the hot cell pool is
' limited to four irradiated assemblies. The limit of_four assemblies in the pool is an arbitrary limit which the site imposes upon itself and does not affect nuclear safety since each fuel assembly or rod storage position-is neutronically isolated from any other fissile material by a minimum of 1 foot of water.
Racks and fixtures in the pool are constructed with sufficient integrity and strength to withstand reasonable structural deformity, thereby providing the spacing previously outlined. The racks are also. constructed to preclude inadvertently placing other fissile material closer than the 1-foot minimum spacing. Area Supervisor 1
approval is required for removing or inserting fissile material into or out of any of the racks or fixtures.
Storage of Mark.B and Mark C fuel rods and partially dismantled assemblies into storage racks which restrain the size of each position to a square not exceeding the dimensions of a fresh fuel assembly, i.e., 8.6 inches, is-safe-based upon the analysis demonstrating safety of as assembly during dismantlement. Fuel rods may also be stored in an ever safe cross sectional area fixture, i.e.,
a cross sectional area not exceeding that of a 22.5 cm diameter cylinder.
License No SNM 778 Docket No. 70824 Date July, 1990 Amendment No.
10 Revision No.
13 Page 14-12 Babcock &Wilcox a McDermott company
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l 14.5 DATA SOURCES-Data and Guidance for Nuclear Criticality Safety is taken from one or more of the sources snecified below.
1.
Calculations using methods described-in Section 14.4.
- 2. '" Nuclear Safety Guide, TID-7016, Revision 2,"
NUREG/CR-0095 (0RNL/NUREG/CS0-6),(June,1978.)
.]
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3.
" Nuclear Safety Guide,. TID-7016, Revision 1," (1961). TID-7016, Revision 1 is used only for application of the lattices density method which is Table ~ IV and Figure 22 on.page 26.- Table. IV has L
been modified according to information published in the Federal--
Register, March 5, 1963 on page 2130.
L h
4 American National Standard for Nuclear Criticality Safety in L
Operations with Fissionable Materials Oxide Reactors, ANSI /ANS-8.1-1983).
5.
H. K.. Clark, " Critical and Safe Masses and Dimensions of Lattices of U'and UO Rods in Water" DP-1014,. Savannah River. Laboratory' 2
(1966)..
6.
H. C. Paxton, " Criticality Control. in Operations with Fissile Material," LA-3366(Rev), Los-Alamos Scientific Laboratory, (1972).
1 0
7.
.R.. D. Carter, et al, " Criticality Handbook," ARH-600 Revised'last -
November 6,.1973, Atlantic Richfield Hanford Company.
.1 14.6 FIXED POISONS-The site does not. ow use Fixed Poisons to maintain nuclear criti-cality safety.
14.7 - STRUCTURAL INTEGRITY t
Where structural integrf'4 necessary to provide assurance for
-nuclear cri ~ icality safe 4 e
, any operation, the design and con-
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c struction of those structtan will be evaluated with due regard to load capacity and foreseeable ' ormal loads, accidents and ueterioration.
This engineering activity is the responsibility of the Manager, Industrial Engineering with review and approval by a qualified person.
l License No SNM 778 Docket No.70-824 Date July, 1990 3
Amendment No.
Revision No.
Page 14.ig 10 13 Babcock &Wilcox a McDermott company
-