ML20207N891
| ML20207N891 | |
| Person / Time | |
|---|---|
| Site: | 07000754 |
| Issue date: | 11/17/1986 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 27651, NUDOCS 8701140478 | |
| Download: ML20207N891 (5) | |
Text
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RETURN I.O 396-58 o
.t GENERAL $ ELECTRIC NUCLEAR ENERGY BUSINESS OPERATIONS GENERAL ELECTRIC COMPANY c VALLECDOS NUCLEAR CENTER e PLEASANTON, CAUFORNIA 94566 November 17, 1986
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RECEIVED Leland C. Rouse, Chief OEC 4
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U.S. Nuclear Regulatory Commission 49 Washington, D.C.
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Reference:
LicenseSNM-960, Docket 7di54~s.
Dear Mr. Rouse:
The General Electric Company, Vallecitos Nuclear Center (VNC), requests three amendments be made to Appendix A of License SNM-960.
The amendments.to Sections 4.2.3 and 5.5 of Appendix A require the review of all criticality analyses and thus relieves the manager of the criticality safety function of the responsibility for determining which analyses should receive a review.
The third amendment (Section 4.4, Appendix A) clarifies the fact that the Vallecitos Technological Safety Council is not required to meet every quarter. However, the decision not to meet in any quarter must be a conscious one and documented.
An application fee of $150.00 is enclosed.
If you or your staff have any questions concerning this application, please contact me on (415) 862-4330., Thank you.
Sincerely, 6
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G. E. Cunningh N
Senior Licensing Engineer g
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USNRQ 93 DEC 21986 )
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6 verified by two of the individuals described in 5.5 or by the physics advice function in 5.4 of this Appendix.
4.2.3 The manager of the criticality safety component shall hold a bachelor's degree in science or engineering and have at least five years experience in a responsible position in a nuclear field such as engineering, physics or chemistry.
4.3 RADIATION SAFETY COMPONENT The radiation safety component is defined as that component of the Nuclear Energy Operations with designated responsiblity to provide authoritative professional advice and counsel to area managers at the Vallecitos Nuclear Center on matters of radiation protection and ALARA and to measure the effectiveness of the radiation protection program.
4.3.1 Functions. The functions of the radiation safety component shall exclude direct responsibility for operations involving the manufacture of nuclear products or processing of nuclear materials. The radiation safety component shall be responsible to establish and maintain the radiation safety program to ensure the protection of employees at the Vallecitos Nuclear Center and of the community.
The radiation safety program shall include as a minimum:
the evaluation of release of radioactive effluents and materials from the site, establishment of procedures and training programs to control contamination and exposure i
to individuals, the review of calibration and maintenance activities for radiation detection instruments, maintenance of appropriate records and reports, review of radioactive material handling practices, and review of change procedures (see Section 4.6),
including ALARA considerations.
l 4.3.2 The minimum qualifications of personnel assigned functional l
responsibilities in the radiation safety component shall be as follows:
l l
License No.
$NM-960 Dodet No.70-754 Sect. No.
4 Page A-4-2 APPENDIX A Date 11/17/86 Amends Sect.(s) 4.2.3
7
- i s
1.
Manarer:
B.S. degree in science or engineering with five years experience in assignments involving radiation protecticn.
2.
Soecialists:
B.S. degree in science or engineering with two years experience in assignments involving radiation protection or eight_ years of experience in health physics or radiation protection.
3.
Monitors: High school with two years monitoring experience or two years of college and four months experience; also, successful completion of a General Electric certification program which includes written and oral examinations covering radiation protection procedures and/or criticality procedures.
4.4 VALLECITOS TECHNOLOGICAL SAFETY COUNCIL The functions of the Vallecitos Technological Safety Council (VTSC) shall include responsibility for review of reportable incidents, new facilities or major changes to facilities, and for contributing professional advice and counsel on criticality and radiation safety policy. The VTSC shall review annually the site safety and compliance program performance to include effluent releases and occupational exposures in terms of ALARA and focus on trends for corrective action as necessary.
Its deliberations in any calendar quarter shall be reported in writing to the Manager, Irradiation Processing Operation, and retained two years.
Should the VTSC choose not to meet in any calendar quarter, the Manager, Irradiation Processing Operation, shall be notified in writing.
The Vallecitos Technological Safety Council shall consist of at least five senior members of General Electric's technical and/or management personnel appointed by the Manager, Irradiation Processing Operation, and shall include competence in the physics, chemistry, and engineering disciplines.
Usense No.
SNM-960 Dodet No.70-754 Sect. No.
4 Page A-4-3 APPENOlX A Does 11/17/86 Amends Sect.(s) 44
t' 5.5 VERIFICATION OF CRITICALITY SAFETY ANALYSIS RESULTS The manager of the criticality safety component shall assure that the results of criticality analyses are reviewed.
This review may be performed by the manager of the criticality safety component provided he has acquired a minimum of two years experience in the methods used or by a member of the criticality safety component other than the individual who performed the analysis or an independent reviewer of equivalent education and experience. The neutron physics advice function (5.4) may provide technical review of ccmputation methods. The review need not involve a recalculation of the results.
5.6 RECORDS Records of criticality control analyses shall be maintained in sufficient detail and form to permit independent review of the method of calculation and results. Such records shall be retained for a period of at least six months following the cessation of activities to which they apply.
5.7 CRITICALITY CONTROL INSPECTIONS 5.7.1 The radiation safety component shall be responsible for inspecting each criticality area on an ongoing basis to assure compliance with criticality control procedures.
Items to be inspected shall include, but not be limited to, the posting of criticality control limits, the labeling of SNM containers with information needed for criticality control purposes, the movement of SNM, and general criticality safety work practices.
5.7.2 A program of inspection shall be performed by the criticality safety component to determine that actual operations conform to the physical I
situations on which the calculations of criticality limits have been based.
Inspection reports shall be furnished to area managers. Where situations are identified which require corrective action, such reports shall so indicate. Corrective or follow-up action shall be l
License No.
SNM-960 Dodet No.70-754 Sect. No.
5 Page A-5-2 APPENDIX A Does 11/17/86 Amends $ect.(s) 5.5
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