ML20044A681
| ML20044A681 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 06/26/1990 |
| From: | Soong S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Bidinger G NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9007020051 | |
| Download: ML20044A681 (5) | |
Text
...
JUN 2 6'1990
' Docket No. 70 1201 License No. SNM.1168 4
e MEMORANDUM FOR: George H. Bidinger, Section Leader Uranium Fuel Section fuel Cycle Safety Branch i
Division of Industrial and Medical Nuclear Safety, HMSS FROM:
Sean Soong Uranium Fuel Section fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS
SUBJECT:
TRIP REPORT 1.
Purpose TodiscusslicenserenewalwithB&WFuelCompany(B&W).
!!. Place and Date Lynchburg, Virginia, June 18, 1990.
111. Attendees:
B&W NRC R. A. Alto G. H. Bidinger K. S. Lester S. Soong G. B. Lindsey J. W. Harwell IV.
Summary On June 18, 1990, staffvisitedB&Wtodiscusstheircomments(enclosed)onthe B&W license renewal application. As a result of the meeting,-the licensee plans to revise the application to incorporate most of NRC's comments and Will submit it to NRC by June 22, 1990. After the meeting, the staff toured the facility.
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Uranium fuel Section fuel Cycle Safety Branch Division of Industrial and
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BWFC/70-1201 LICENSE CONDITIONS Maximum 6.
Material 7.
Form 8.
Quantity A.
Uranium enriched A. Uranium A. 25,000 kilogrcms t
up to 4.1 w/o U 235 0xide, pellet or of U-235 powder B.
Uranium enriched B. ufo B 5,000 kilograms up to 5.0 w/o U-235 of U-235 C.
Uranium, natural or C. Oxide,_ pellet or C. 1,000,000 kilograms depleted powder of uranium D.
Uranium, natural D. UFs D. 1,400,000 kilograms of uranium E.
Byproduct material E. Sealed sources E. 51 curies with atomic numbers 3 to 83,-
inclusive t
F.
Plutonium F. Sealed sources F. 6 grams plutonium G.
Californium-252 G. Sealed sources G. 3 milligrams of Californium-252 H.
Uranium enriched
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I.
Americium-241 I. Sealed sources I
5 curies Americium-241 J.
Byproduct material J. Contamination or J. 20 curies, total and Pu waste associated with the equipment used in field service operations 9.
Authorized Use:
For use in accordance with statements, representations, and conditions of Part I of the licensee's application dated June 21, 1989.
10.
Authorized place of use:
The licensee's existing facilities at Lynchburg,
- Virginia, 11.
The plant manager shall have, as a minimum, a bachelor's degree in science or engineering, 10 years of experience in the nuclear industry, and 5 i
years experience in management positions.
The incumbent plant manager is l
deemed to have the equivalent of these requirements.
l
hr BWFC/70-1201 LCS ;
12.
The Health and Safety Monitors shall have, as a minimum, a high school diploma with 6 month of experience as a Health and Safety Monitor trainee.
i 13.
The Operational Area Supervisors shall have, as a minimum, a bachelor's degree in science or engineering, followed by 2 years experience in the nuclear industry.
14.
The individual performing the independent review of the nuclear criticality safety evaluation shall have, as a minimum, two years of i
experience as a Nuclear Criticality Safety Specialist.
15.
The Safety Review Board chairman shall have, as a minimum, the i
qualifications of the Manager, Quality and Safety.
16.
The Safety Review Board members shall have, as a minimum, a bachelor's
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degree in science or engineering, followed by 4 years experience in the nuclear industry.
17.
Prior to implementation, new or revised operating procedures shall be approved in writing by the cognizant Operating Area Supervisor and i
the Manager, Quality and Safety.
18.
Safety related operating procedures shall be reviewed, at least every 2 years, by the cognizant Operational Area Supervisor, the Health Physicist, nd the Nuclear Criticality Specialist, The Nuclear Criticality dpecialist shall have, as a minimum, the qualifications of an individual who is qualified to perform independent reviews of nuclear criticality safety evaluations.
19.
The licensee shall conduct a written test for evaluating the effectiveness of the training program.
1 l
20.
Notwithstanding Section 3.1.3 of the application, the RWP shall be used only for non-routine operations, reviewed for industrial safety and be approved by an individual meeting the minimum qualifications of the Health Physicist.
A RWP previously approved may be reissued and approved by the Health Safety Foreman.
21.
The annual ALARA report shall be reviewed by the Safety Review Board to determine:
(1) if there are any upward trends developing in personnel exposures (internal and external) for identifiable categories of workers, types of operation, or effluent releases; (2) if exposuras and releases might be lowered in accordance with the ALARA concept; and.(3) if equipment for effluent and exposure controls is being properly used, maintained, and inspected.
The Board shall report the results of its review and recommendations to the Plant Manager.
22.
The licensee shall take corrective action when the face velocity of the ventilated hood is below 100 LFM.
The record of the investigation shall be kept for 2 years.
23.
The breathing zone air in a Radiation Control Zone shall be sampled continuously and analyzed for airborne concentrations of radioactivity' after each operational shift.
If an individual's internal exposure exceeds 8 MPC-hr per operational shift, an investigation of the cause shall be conducted and corrective action shall be taken and documented.
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BWFC/70-1201 LCS
-J-24.
When beta-gamma contamination above action lovels is identified, cleanup operations shall commence no later than at the start of the next work shift.
25.
After each operational day, the change area for the beta gamma radiation work areas shall be surveyed for removable contamination lhe action level for cleanup will be 1,000 dpm/100cm' for removable contamination.
26.
Notwithstanding Section 10.4.2. of the application, solid waste material containing less then 0.002uc/gm shall be treated as radioactive material and be disposed at a licensed burial site.
27.
Process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions Lofore a criticality accident is passible.
28.
Notwithstanding the statements in Section 4.1,3, all nuclear criticality safety evaluations and interpretations shall be performed by the nuclear criticality safety specialist.
29.
Prior to initiation of a new or changed process, the individual who performed either the nuclear criticality safety evaluation or the independent review shall participate in the pre-operational inspection.
30.
The number of fuel assemblies in the fuel assembly storage area shall not exceed 100, 31.
The licensee shall submit semlannual effluent results to the NRC as required by 10 CFR 70.59, in accordance with Section 5 of Regulatory Guide 4.16 dated December 1985.
32.
If quarterly averaged concentration of radioactivity of the liquid offluent discharging from retention tank exceeds 2.5 percent of MPC (based on a gross alpha count of uranium) in 10 CFR 20, Appendix B, Table II, Vol. 2, the licensee shall conduct an investigation of the source and take corrective action, if necessary.
33.
The licensee shall inform the NRC within 30 days if the State permitting agency revokes, supersedes, conditions, modifies, or otherwise nullifies the effectiveness of the State-issued NPDES permit for the discharge of liquid effluents.
34.
The licensee shall conduct a characterization survey and develop an action plan for the cleanup of the contaminated soil f rom the wet-weather stream and submit the plan for NRC review within 9 months from the date of l
1
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h SWFC/70-1201 LCS 4'-
35.
The licensee shall conduct environmental monitoring in accordance with approved procedures, which require the generated data be evaluated against an internal action level.
36.
ADatta LC 37.
The licensee is hereby exempted from the labeling requirements in 10 CFR 20.203(e) and (f) provided a sign bearing the words " Caution Radioactive Material.
Any Area or Container Within This Area May Contain Radioactive Material" or equivalent words is posted outside the specific work areas.
l 38.
Notwithstanding the statement in Section 1.7.4 Part I of the application dated June 21, 1989, release of equipment and material from the plant to offsite for unrestricted use or from contaminated to clean area onsite shall be in accordance with the attached, " Guideline for Decontamination i
of Facilities an Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source or Special Nuclear Material," August 1987.
39.
The licensee is hereby granted the exemptions and special authorizations in Sections 1.7.2 and 1.7.3, Chapter 1, of the application.
40.
At not more than 2 year intervals from July 31, 1990, the licensee shall update the demonstration sections of the renewal application to reflect the licensee's current operations.
The updates to the application shall, as a minimum, include information for the health and safety section of the application as required by 10 CFR Part 70.22(a) through 70.22(f), and 70.22(i) and operational data or environmental releases as required by 70.21.
[
In lieu of an update at the end of the 10 year renewal period the licensee shall file an application for renwal on or before July 31, 1999.
41.
On or before July 31, 1995, the license shall be_in compliance with the financial assurance for decommissioning provisions of 9 70.25 of 10 CFR Part 70, S 40.36 (d) and (e) of 10 CFR Part 40, and S 30.35 (e) and (f) of 10 CFR Part 30.
42.
On or before July 31, 1990, the licensee shall be in full compliance with the emergency plan requirements of Section 70.22(i) of 10 CFR Part 70, S 40.31(j) of 10 CFR Part 40, and S 30.32(i) of 10 CFR Part 30, as appropriate.
43.
On or before July 31, 1991, the licensee shall evaluate his safety program against the " Guidance on Management Controls / Quality Assurance, Requirements for Operation, Chemical Safety, and Fire Protection for Fuel Cycle Facilities", Federal Register, March 21, 1989, and shall propose license conditions, as appropriate, to modify the license in accordance with the " Guidance...."
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