ML20249C626

Proposed Tech Specs Pages 17,18,19 & 21 Re Organizational Structure

ML20249C626
Person / Time
Site:	University of Buffalo
Issue date:	06/23/1998
From:	NEW YORK, STATE UNIV. OF, BUFFALO, NY
To:
Shared Package
ML20249C625	List: ML20249C624 ML20249C626
References
NUDOCS 9806300439
Download: ML20249C626 (5)

Text

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3) Hydraulic pressure is available to close the ventilation isolation dampers.

4) Fuel storage canisters, transfer casks, or caskets, shall be:

'. DOT certified packaging or

. Equipped with bales, handles or lifting lugs and or cables or similar lifting gear which are capable or supporting at least twice the weight of the load in air. In addition appropriate safety margins will be used in designing such equipment.

and

. Shall be designed so that fuel elements or assemblies will not spill out in the event the load is dropped.

5) The transfers must be conducted in accordance with a Radiation Work Permit approved by the Radiation Safety Officer.

6) A criticality alarm (s) shall be operating in appropriate location (s), if greater than 374 fuel elements are located in the transfer container, unless the container is DOT certified packaging.

7) Items (1),(2), and (3) above do not apply when handling fuel which is contained in tealed DOT approved canisters or containers.

10.3.5 Fuel Handling within the reactor tank In addition to the requirements of sections 3.2.,3.3,3.4 and 4.0, whenever fuelis handled in the reactor tank the following requirements shall apply:

1) The airlocks and truck door are sealed.

2) The containment pressure is negative with respect to outside atmosphere.

3) Hydraulic pressure is available to close the ventilation isolation dampers.

4) If fuel assemblies are being placed into a geometric configuration which has not been previously loaded, a neutron count rate monitor shall be operating and mo7itored.

5) The neuiron count rate monitor is not required when fuel assemblies are being loaded into or transferred between the standard fuel racks which were originally installed in the reactor tank, or similar racks installed pursuant to 10.3.1 (2),

which utilize an identical geometry. This would include the tronsfer of fuel assemblies from the grid plate to the fuel racks.

. u 11.0 Administration - -

/

11.1 OrganizationalStructure

1) The organizational structure shall be as illustrated in Figure 1.

2) The Director of Occupational and Environmental Safety bears direct administrative and safety responsibility for the Facility.

AMMENDMENT 25 PAGE 17 9806300439 980623 PDR ADOCK 05000057

3) Th3 BMRC Director bears direct responsibility for all surveillance, operations, testing and experiments conducted at BMRC.

4) ,The Radiation Safety Officer bears direct responsibility for all aspects of radiological safety at BMRC and is empowered to stop, or modify any activity for purposes of ensuring the radiological safety cf the staff and the public. i l

s) The Operations Manager is responsible for all activities related to safe storage L and handling of the reactor fuel, maintenance and testing of plant safety l systems and other engineered safety systems, the training and supervision of l licensed operators and Certified Fuel Handlers. '

1 11.2 Reinimum StefHng Requimments As long as irradiated fuel is stored within BMRC, the University staff shall include at l . minimum:

1) The Director of Occupational and Environmental Safety

2) The BMRC Director

3) The BMRC Operations Manager

4) The Radiation Safety Officer l s) At least one licensed Sr. Reactor Operator or Certified Fuel Handler. l For purposes of meeting the requirements of 11.2:

1) A single individual may serve as both the BMRC Director and Director of Occupational and Environmental Safety, or a single individual may serve as both BMRC Director and BMRC Operations Manager.

2) The Operations Manager may be the Senior Reactor Operator or Certified Fuel )

Handler, provided there is at least one additionally licensed Reactor Operator or Certified Fuel Handler on staff.

i 3) Staff members may perform collateral duties in other areas of the University or be part tirm employees.

11.3 Onces SimfHng Rogdoments l

As long as irradiated fuel is stored within BMRC, the University shall meet the I following "on-call" requirements.

1) The Operating Committee will maintain a roster of personnel who are trained in appropriate aspects of facility operation and health physics.

2) At least one individual from this roster will remain within a 50-mile radius of the facility at all times and be reachable by phone, pager or radio.

11AOperationalRequimments

1) All fuel handling must supervised or performed by a licensed Sr. Reactor Operator or Certified Fuel Handler. Non-licensed personnel may assist in the  ;

conduct of the manipulations, but must receive training commensurate with their '

level and nature of participation.

2) All licensed Operators or Certified Fuel Handlers shall participate in the BMRC Requalification program or CFH decertification respectively, as a condition of I

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thQir continuGd assignment to operator or Certified Fuel Handler duties. The Requalification program shall be commensurate and consistent with the current scope and nature of operational activities on site. 1 l

11.5 Review FuncIlons 11.5.1 Reactor Decommissioning Safety Committee

1) A Reactor Decommissioning Safety Committee (RDSC) shall exist for the purpose of reviewing matters related to the health and safety of the public and the staff, in accordance with the Constitution and Bylaws of the committee.

2) The RDSC shall report to the Associate Vice President for Facilities who shall appoint the members and Chair.

3) The RDSC shall inc'ude at least eight members including as ex-officio members ,

p the BMRC Operations Manager, BMRC Director, the Radiation Safety Officer, {

and the Director of Occupational and Environmental Safety. The BMRC Director '

and Operations Manager shall be non-voting members.

4) The RDSC shall meet at least three times per year.

s) A quorum of the RDSC shall consist of at least six mombers, and all questions before the Committee must be approved by a simple majority of the voting members present, but by not less than four voting membert, e) Minutes of all meetings will be maintained on file and distributed to all merobers,

7) The RDSC shall review and approve the following:

l l A) The substantive aspects of short and long term action plans relative to the l reactor decommissioning, reactor plant maintenance and monitoring, except l for those which may be reviewed and approved by the Operating ,

Committee. l B) Reportable Occurrences related to health and safety, and corrective actions.

C) Notices of Violation related to health and safety and corrective actions.

D) Applications for amendment to NRC licenses. i E) Changes in Procedures or facilities implemented in accordance with 10 CFR 50.59, in Post Audit, after Operating Committee approval.

11.5.2 Operating Committee l

1) An Operat'ng Committee shall exist as a sub-group of the RDSC.

! 2) The Operating Committee shall consist of the ex-officio members of the RDSC l plus additional members appointed pursuant to the by-laws.

3) The Operating Committee shall meet as often as required and minutes shall be kept of all formal meetings.

4) The Operating Committee is authorized to act for the RDSC regarding routine occurrences, and approvals for which the safety implications are minor, are well understood, and are within the scope of past practice. This would include but not be limited to:

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2) The Operating Committee will investigate the occurrence and its causes, and will report its findings to the Reactor Decommissioning Safety Committee and to the Senior Vice President, and Associate Vice President for University Facilities.

3) A report shall be filed with the NRC which shallinclude an analysis of the causes of the occurrence, the effectiveness of corrective actions taken and recommendations of measures to be taken to prevent or reduce the probability or consequences of recurrence.

13.0 Written Procedures .

~

13.1 Ploquired Procedures Written procedures will exist that define how and when various aspects of facility operations will be performed. These procedures may include " Operating Procedures", " Emergency Procedures" and " Maintenance and Calibration Procedures."

Written procedures shall at minimum address the following areas:

1) Fuel Handling Operations.

2) Use, surveillance, and maintenance of auxiliary systems.

3) Abnormal and emergency situations.

4) Required reactor electrical and mechanical surveillance cnd maintenance.

s) Operation and calibration of fixed radiological monitors as required by this Technical Specification.

13.2 Approvat, noview and update

1) Operating Procedures and Maintenance and Calibration Procedures will be reviewed and updated as appropriate, but such review shall be no less frequent than once every two years.

2) Emergency Procedures shall be reviewed and updated in accordance v,ith the BMRC Emergency Plan.

3) All new or revised procedures shall be approved by the Operating Committee.

13.3 Temporary Deviation from Written Procedums Temporary changes to written procedures that do not change the original intent may be made with the approval of a Sr. Reactor Operator, the Operations Manager, or the BMRC Director. All such changes shall be documented.

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