Text

Requested Amendment No. 8 to Facility Operating License No. R-130, Mcclellan Nuclear Research Center
	ML11199A214
Person / Time
Site:	University of California-Davis
Issue date:	07/15/2011
From:	Steingass W; McClellan Nuclear Research Center
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML11199A214 (20)
	v • d • e

m m~in

~

~\\'5335 PRICE AVENUE, BUILDING 258 lnmr

....SACRAMENTO, CA 95652 EVE.

PHONE: (916) 614-6200 McCLELLAN NUCLEAR RESEARCH CENTER FAX: (916) 614-6250 July 15, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 1 White Flint North Rockville MD 20852 Ref:

University of California, Davis McClellan Nuclear Research Center (UCD/MNRC), Docket No. 50-607, Facility Operating License No. R-130

Subject:

Requested Amendment No. 8 to Facility Operating License No. R-130, McClellan Nuclear Research Center Gentlemen It is requested that the attached proposed Revision 14 to the UCD/MNRC Technical Specifications be approved for use. The nature of the changes are explained below.

The following describes the changes to the document submitted:

1. The proposed new Technical Specifications (Rev 14) have been revised to remove/delete the management position of "Operations Manager" which was incorporated in Rev 13. The responsibilities and duties of this position have been removed in this revision.

In addition, the UCD/M1NRC Organization Chart, Fig 6.1, has been changed to reflect this organizational change.

2. The other changes are to make corrections in the definition of a standard fuel element, and in the Administrative Controls Staffing section to change the minimum staffing requirement when the reactor is not shutdown to not secured which is the more correct term.

3. The Quorums requirement for the NSC Charter and rules has been changed.

Page 1 of 2 Printed On: 7/15/2011

All changes (i.e., Rev 14) to the Technical Specifications are marked by vertical lines in or near the right hand margin.

Sincerely, Walter Guy Steingass Associate Director of Operations, UCD/MVNRC Attachments

1. UCD/MNRC Tech Specs Rev 14 (2 copies) cc: Dr. Barry Klein, UCD/MNRC Director In accordance with 10 CFR Part 50.30(b), I declare under foregoing is true and correct penalty of perjury that the Executed on Date

//ýgnaturt Page 2 of 2 Printed On: 7/15/2011

TECHNICAL SPECIFICATIONS FOR THE UNIVERSITY OF CALIFORNIA - DAVIS MCCLELLAN NUCLEAR RADIATION CENTER (UCD/MNRC)

DOCUMENT NUMBER: MNRC-0004-DOC-14 Rev 14 12/09

Summary of Changes to Technical Specifications For the University of California-Davis McClellan Nuclear Research Center (UCD/MNRC)

Document Number: MNRC-0004-DOC-14 Affected page Reason for change Title Current revision Approval Page Current revision 02 Para. 1.6 Hydrogen to zirconium is correct 31 Para 6.1, 6.1.2 Reflects current organization, removes Operation Manager and corrects reporting responsibilities.

31 Para 6.1.3.1 Changed shutdown to secured. This is the more correct term 32 Para 6.2.2.c Changed Quorum from 7 to 5 members 33 Para 6.3 Changed Operations Manager to UCD/MNRC Director.

40 Figure 6.1 Deleted Operations Manager block

Revision 14 of the "Technical Specifications" for the University of California at Davis/McClellan Nuclear Radiation Center (UCD/MNRC) Reactor have undergone the following coordination:

Reviewed by:

Radiation Safety Officer Date Reviewed by:

Approved by:

41351/

Date Date J

Date Approved by: Scu,ý KA&

Cha p-erson, UCD/MNRC Nuclear Safety Committee

Technical Specifications Rev 14 12/2009 Page Title Page Rev 14 12/2009 Approval Page Rev 14 12/2009 02 Rev 14 12/2009 31 Rev 14 12/2009 32 Rev 14 12/2009 33 Rev 14 12/2009 Figure 6.1 Rev 14 12/2009

1.5.2 Experiment, Secured. A secured experiment is any experiment, experiment facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining force must be substantially greater than those toWhich the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which can arise as a result of credible conditions.

1.5.3 Experiment Facilities. Experiment facilities shall mean the pneumatic transfer tube, beamtubes, irradiation facilities in the reactor core or in the reactor tank, and radiography bays.

1.5.4 Experiment Safety System. Experiment safety systems are those systems, including their associated input circuits, which are designed to initiate a scram for the primary purpose of protecting an experiment or to provide information which requires manual protective action to be initiated.

1.6 Fuel Element, Standard. A fuel element is a single TRIGA element. The fuel is U-ZrH clad in stainless steel. The hydrogen to zirconium ratio is nominally 1.65 +/- 0.05. The weight percent (wt%) of uranium can be either 8.5, 20, or 30 wt%, with an enrichment of less than 20% U-235. A standard fuel element may contain a burnable poison.

1.7 Fuel Element, Instrumented. An instrumented fuel element is a standard fuel element fabricated with thermocouples for temperature measurements. An instrumented fuel element shall have at least one operable thermocouple embedded in the fuel near the axial and radial midpoints.

1.8 Measured Value. The measured value is the value of a parameter as it appears on the output of a channel.

1.9 Mode, Steady-State. Steady-state mode operation shall mean operation of the UCD/MNRC reactor with the selector switch in the automatic or manual mode position.

1.10 Mode, Square-Wave. Square-wave mode operation shall mean operation of the UCD/MNRC reactor with the selector switch in the square-wave mode position.

1.11 Mode, Pulse. Pulse mode operation shall mean operation of the UCD/MNRC reactor with the selector switch in the pulse mode position.

1.12 Operable. Operable means a component or system is capable of performing its intended function.

1.13 Operatingq. Operating means a component or system is performing its intended function.

1.14 Operatinq Cycle. The period of time starting with reactor startup and ending with reactor shutdown.

1.15 Protective Action. Protective action is the initiation of a signal or the operation of equipment within the UCD/MNRC reactor safety system in response to a variable or condition of the UCD/MNRC reactor facility having reached a specified limit.

1.15.1 Channel Level. At the protective instrument channel level, protective action is the generation and transmission of a scram signal indicating that a reactor variable has reached the specified limit.

1.15.2 Subsystem Level. At the protective instrument subsystem level, protective action is the generation and transmission of a scram signal indicating that a specified limit has been reached.

NOTE: Protective action at this level would lead to the operation of the safety shutdown equipment.

2

5.4 Fissionable Material Storage Applicability - This specification applies to the storage of reactor fuel at a time when it is not in the reactor core.

Obiective - The objective is to assure that the fuel which is being stored will not become critical and will not reach an unsafe temperature.

Specification -

a. All fuel elements not in the reactor core shall be stored (wet or dry) in a geometrical array where the keff is less than 0.9 for all conditions of moderation.

b. Irradiated fuel elements shall be stored in an array which shall permit sufficient natural convection cooling by water or air such that the fuel element temperature shall not exceed the safety limit.

Basis - The limits imposed by Technical Specifications 5.4.a and 5.4.b assure safe storage.

6.0 Administrative Controls 6.1 Orqanization. The Vice Chancellor for Research shall be the licensee for the UCD/MNRC. The UCD/MNRC facility shall be under the direct control of the UCD/MNRC Director or a licensed Senior Reactor Operator (SRO) designated by the UCD/MNRC Director to be in direct control. The UCD/MNRC Director shall be accountable to the Vice Chancellor for Research for the safe operation and maintenance of the facility.

6.1.1 Structure. The UCD/MNRC management for reactor operation, licensing and safety shall consist of the organizational structure as shown in Figure 6.1.

6.1.2 Responsibilities. The UCD/MNRC Director shall be accountable to the Vice Chancellor for Research for the safe operation and maintenance of the facility. The UCD/MNRC Director, or his designated alternate, shall review and approve all experiments and experiment procedures prior to their use in the reactor. Individuals in the management organization (e.g., Reactor Supervisor and Radiation Safety Officer) shall be responsible for implementing UCD/MNRC policies and for operation of the facility, and shall be responsible for safeguarding the public and facility personnel from undue radiation exposures and for adhering to the operating license and technical specifications. The Reactor Supervisor and Radiation Safety Officer report directly to the UCD/MNRC Director.

6.1.3 Staffing 6.1.3.1 The minimum staffing when the reactor is not secured shall be:

a. A reactor operator in the control room;

b. A second person in the facility area who can perform prescribed instructions;

c. A senior reactor operator readily available. The available senior reactor operator should be within thirty (30) minutes of the facility and reachable by telephone, and;

d. A senior reactor operator shall be present whenever a reactor startup is performed, fuel is being moved, or experiments are being placed in the reactor tank.

6.1.3.2 A list of reactor facility personnel by name and telephone number shall be available to the reactor operator in the control room. The list shall include:

a. Management personnel.

31

b. Reactor Operations personnel.

c. Radiation Safety Officer 6.1.4 Selection and Training of Personnel. The selection, training and requalification of operations personnel shall meet or exceed the requirements of the American National Standard for Selection and Training of Personnel for Research Reactors (ANS 15.4). Qualification and requalification of licensed operators shall be subject to an approved Nuclear Regulatory Commission (NRC) program.

6.2 Review, Audit, Recommendation and Approval General Policy. Nuclear facilities shall be designed, constructed, operated, and maintained in such a manner that facility personnel, the general public, and both university and non-university property are not exposed to undue risk. These activities shall be conducted in accordance with applicable regulatory requirements.

The UCD Vice Chancellor for Research shall institute the above stated policy as the facility license holder. The Nuclear Safety Committee (NSC) has been chartered to assist in meeting this responsibility by providing timely, objective, and independent reviews, audits, recommendations and approvals on matters affecting nuclear safety. The following describes the composition and conduct of the NSC.

6.2.1 NSC Composition and Qualifications. The UCD Vice Chancellor for Research shall appoint the Chairperson of the NSC. The NSC Chairperson shall appoint a Nuclear Safety Committee (NSC) of at least seven (7) members knowledgeable in fields which relate to nuclear safety. The NSC shall evaluate and review nuclear safety associated with the operation and use of the UCD/MNRC.

6.2.2 NSC Charter and Rules. The NSC shall conduct its review and audit (inspection) functions in accordance with a written charter. This charter shall include provisions for:

a. Meeting frequency (The committee shall meet at least semiannually).

b. Voting rules.

c. Quorums (At least Seven (7) members for the full committee, a quorum will be at least five (5) members).

d. A committee review function and an audit/inspection function.

e. Use of subcommittees.

f. Review, approval and dissemination of meeting minutes.

6.2.3 Review Function. The responsibilities of the NSC, or a designated subcommittee thereof, shall include but are not limited to the following:

a. Review approved experiments utilizing UCD/MNRC nuclear facilities.

b. Review and approve all proposed changes to the facility license, the Technical Specifications and the Safety Analysis Report, and any new or changed Facility Use Authorizations and proposed Class I modifications, prior to implementing (Class I) modifications, prior to taking action under the preceding documents or prior to forwarding any of these documents to the Nuclear Regulatory Commission for approval.

c. Review and determine whether a proposed change, test, or experiment would constitute an unreviewed safety question or require a change to the license, to a Facility Use Authorization, or 32

to the Technical Specifications. This determination may be in the form of verifying a decision already made by the UCD/MNRC Director.

d. Review Feactor operations and operationtl maintenance, Class I modification records, and the health physics program and associated records for all UCD/MNRC nuclear facilities.

e. Review the periodic updates of the Emergency Plan and Physical Security Plan for UCD/MNRC nuclear facilities.

f. Review and update the NSC Charter every two (2) years.

g. Review abnormal performance of facility equipment and operating anomalies.

h. Review all reportable occurrences and all written reports of such occurrences prior to forwarding the final written report to the Nuclear Regulatory Commission.

i. Review the NSC annual audit/inspection of the UCD/MNRC nuclear facilities and any other inspections of these facilities conducted by other agencies.

6.2.4 Audit/Inspection Function. The NSC or a subcommittee thereof, shall audit/inspect reactor operations and health physics annually. The annual audit/inspection shall include, but not be limited to the following:

a. Inspection of the reactor operations and operational maintenance, Class I modification records, and the health physics program and associated records, including the ALARA program, for all UCD/MNRC nuclear facilities.

b. Inspection of the physical facilities at the UCD/MNRC.

c. Examination of reportable events at the UCD/MNRC.

d. Determination of the adequacy of UCD/MNRC standard operating procedures.

e. Assessment of the effectiveness of the training and retraining programs at the UCD/MNRC.

f. Determination of the conformance of operations at the UCD/MNRC with the facility's license and Technical Specifications, and applicable regulations.

g. Assessment of the results of actions taken to correct deficiencies that have occurred in nuclear safety related equipment, structures, systems, or methods of operations.

h. Inspection of the currently active Facility Use Authorizations and associated experiments.

i. Inspection of future plans for facility modifications or facility utilization.

j. Assessment of operating abnormalities.

k. Determination of the status of previous NSC recommendations.

6.3 Radiation Safety. The Radiation Safety Officer shall be responsible for ensuring that the UCD/MNRC Radiation Safety Program is in compliance with the American National Standard for Radiation Protection at Research Reactor Facilities guidelines (ANSI/ANS 15.11). The Radiation Safety Officer shall be responsible for implementation of the UCD/MNRC Radiation Safety Program. The Radiation Safety Officer shall report to the UCD/MNRC Director.

6.4 Procedures. Written procedures shall be prepared and approved prior to initiating any of the activities listed in this section. The procedures shall be approved by the UCD/MNRC Director. A periodic review of procedures shall be performed and documented in a timely manner by the UCD/MNRC staff to assure that procedures are current. Procedures shall be adequate to assure the safe operation of the 33

UC Davis McClellan Nuclear Radiation Center Organization for Reactor Operation, Licensing and Safety Formal Licensing Channel Administrative Reporting Channel Recognized Communication Channel FIGURE 6.1 40

TECHNLCAL SPECIFICATIONS FOR THE UNIVERSITY OF CALIFORNIA - DAVIS MCCLELLAN NUCLEAR RADIATION CENTER (UCD/MNRC)

DOCUMENT NUMBER: MNRC-0004-DOC-14 Rev 14 12/09

Summary of Changes to Technical Specifications For the University of California-Davis McClellan Nuclear Research Center (UCD/MNRC)

Document Number: MNRC-0004-DOC-14 Affected page Reason for change Title Current revision Approval Page Current revision 02 Para. 1.6 Hydrogen to zirconium is correct 31 Para 6.1, 6.1.2 Reflects current organization, removes Operation Manager and corrects reporting responsibilities.

31 Para 6.1.3.1 Changed shutdown to secured. This is the more correct term 32 Para 6.2.2.c Changed Quorum from 7 to 5 members 33 Para 6.3 Changed Operations Manager to UCD/MNRC Director.

1 40 Figure 6.1 Deleted Operations Manager block

Revision 14 of the "Technical Specifications" for the University of California at Davis/McClellan Nuclear Radiation Center (UCD/MNRC) Reactor have undergone the following coordination:

Radiation Safety Officer Reviewed by:

D/,/t0 Date Date Reviewed by:

Approved by:

Date G

,> /,.

Date ao k Approved by:

Chaiperson, UCD/MNRC Nuclear Safety Committee

Technical Specifications Rev 14 12/2009 Pagge Title Page Rev 14 12/2009 Approval Page Rev 14 12/2009 02 Rev 14 12/2009 31 Rev 14 12/2009 32 Rev 14 12/2009 33 Rev 14 12/2009 Figure 6.1 Rev 14 12/2009

1.5.2 Experiment, Secured. A secured experiment is any experiment, experiment facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining force must be sub-stantially greater than those to Which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which can arise as a result of credible conditions.