ML061030379
| ML061030379 | |
| Person / Time | |
|---|---|
| Site: | 05000157, 05000097 |
| Issue date: | 06/06/2006 |
| From: | Hughes D NRC/NRR/ADRA/DPR/PRTA |
| To: | Fay C Cornell Univ |
| Hughes D, NRR/DPR/PRT, 301-415-1631 | |
| References | |
| TAC MC0212 | |
| Download: ML061030379 (18) | |
Text
June 6, 2006 Dr. Charles R. Fay Vice Provost for Research Administration Cornell University 314 Day Hall Ithaca, NY 14853-2801
SUBJECT:
ISSUANCE OF LICENSE AMENDMENT NO. 13 REMOVING AUTHORIZATION TO OPERATE AND TO POSSESS FUEL FOR WARD CENTER FOR NUCLEAR STUDIES AT CORNELL UNIVERSITY TRIGA REACTOR (TAC NO. MC0212)
Dear Dr. Fay:
In accordance to your request of June 24, 2003, as supplemented December 6, 2005, and January 19 and March 27, 2006, the Commission has issued the enclosed Amendment No. 13 to Facility Operating License for the TRIGA Reactor, Docket No. 50-157, License No. R-80.
The amendment removes authorization to operate the reactor and possess special nuclear material, and makes changes to the Technical Specifications (TS) in order to remove or modify TSs so that they are compatible with the license changes, and to structure the administrative TSs to support the decommissioning of the Ward Center for Nuclear Studies (WCNS).
A copy of the related safety evaluation supporting Amendment No. 13 is also enclosed.
Sincerely,
/RA/
Daniel E. Hughes, Project Manager Research and Test Reactor Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-157
Enclosures:
- 1. Amendment No. 13
- 2. Safety Evaluation cc w/enclosures: Please see next page
Cornell University Docket Nos. 50-157/97 cc:
Dr. Joseph Burns, Vice Provost for Physical Sciences and Engineering Cornell University 314 Day Hall Ithaca, NY 14853-2801 Barbara Youngberg Chief, Radiation Section NYS Dept. of Environmental Conservation 625 Broadway Albany, NY 12233-7255 Mr. Howard C. Aderhold Ward Center for Nuclear Sciences Cornell University 105 Ward Laboratory Ithaca, NY 14853 Mr. John P. Spath NYS Energy Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Thomas McGiff, RSO 125 Humphreys Service Building Ithaca, NY 14853 Steve Beyers, P.E.
Cornell Decommission Project Manager Cornell University Environmental Compliance Offices 129 Humphreys Service Building Ithaca, NY 14853 Dr. William Vernetson Director of Nuclear Facilities Department of Nuclear Engineering Sciences University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
June 6, 2006 Dr. Charles R. Fay Vice Provost for Research Administration Cornell University 314 Day Hall Ithaca, NY 14853-2801
SUBJECT:
ISSUANCE OF LICENSE AMENDMENT NO. 13 REMOVING AUTHORIZATION TO OPERATE AND TO POSSESS FUEL FOR WARD CENTER FOR NUCLEAR STUDIES AT CORNELL UNIVERSITY TRIGA REACTOR (TAC NO. MC0212)
Dear Dr. Fay:
In accordance to your request of June 24, 2003, as supplemented December 6, 2005, and January 19 and March 27, 2006, the Commission has issued the enclosed Amendment No. 13 to Facility Operating License for the TRIGA Reactor, Docket No. 50-157, License No. R-80.
The amendment removes authorization to operate the reactor and possess special nuclear material, and makes changes to the Technical Specifications (TS) in order to remove or modify TSs so that they are compatible with the license changes, and to structure the administrative TSs to support the decommissioning of the Ward Center for Nuclear Studies (WCNS).
A copy of the related safety evaluation supporting Amendment No. 13 is also enclosed.
Sincerely,
/RA/
Daniel E. Hughes, Project Manager Research and Test Reactor Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-157
Enclosures:
- 1. Amendment No. 13
- 2. Safety Evaluation cc w/enclosures: Please see next page DISTRIBUTION:
PUBLIC PRT/R&TR r/f BThomas AAdams CBassett PDoyle TDragoun WEresian DHarrison DHughes EHylton PIsaac MMendonca JQuichocho WSchuster MVoth OGC KWitt PYoung WKennedy GHill (2) CGrimes HNieh ADAMS ACCESSION NO: ML061030379 TEMPLATE No.: NRR-056 OFFICE RNRP:PM RNRP:LA OGC RNRP:BC NAME DHughes:tls* EHylton* SUttal* BThomas:tls*
DATE 6/1/2006 4/25/2006 6/1/2006 6/6/2006 OFFICIAL RECORD COPY
CORNELL UNIVERSITY TRIGA REACTOR DOCKET NO. 50-157 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 13 License No. R-80
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for an amendment to Facility Operating License No. R-80 filed by Cornell University, (the licensee) on June 24, 2003, as supplemented December 6, 2005, and January 19 and March 27, 2006, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in Chapter I of Title 10 of the Code of Federal Regulations (10 CFR);
B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) such activities will be conducted in compliance with the regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. This amendment is issued in accordance with the regulations of the Commission as stated in 10 CFR Part 51, and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105, and publication of notice for this amendment is not required by 10 CFR 2.106.
- 2. Accordingly, the license is amended by changes to the following paragraphs which are hereby amended to read as follows:
1.B. The facility will be possessed, but not operated, in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1.H. The possession and disposal of byproduct, as authorized by this license, will be in accordance with the Commissions regulations in 10 CFR Part 30.
2.A. This license applies to the TRIGA nuclear reactor that is owned by Cornell University (the licensee), located on the Universitys campus in Ithaca, New York.
2.B.1. Pursuant to Section 104(c) of the Act and 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, to possess, but not operate, the reactor at the designated location in Ithaca, New York, in accordance with the procedures and limitations described in the application and in this license.
2.B.4 Pursuant to the Act and 10 CFR Part 30, Rules of General Applicability to Domestic Licensing of Byproduct Material at the reactor facility, to possess, but not separate, such byproduct materials as may have been produced by operation of the reactor prior to its permanent shutdown.
2.C.1 Maximum Power Level The licensee shall not possess fuel and therefore cannot load the core and operate the reactor.
2.C.2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 13, are hereby incorporated in the license. The licensee shall possess and decommission the facility in accordance with the Technical Specifications.
- 3. Accordingly, the license is amended by deleting paragraphs 2.B.2 and 2.B.3.
- 4. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Brian E. Thomas, Branch Chief Research and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
Enclosure:
Appendix A, Technical Specifications Changes Date of Issuance: June 6, 2006
ENCLOSURE TO LICENSE AMENDMENT NO. 13 FACILITY OPERATING LICENSE NO. R-80 DOCKET NO. 50-157 Appendix A, "Technical Specifications," is replaced in its entirety.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 13 TO FACILITY OPERATING LICENSE NO. R-80 CORNELL UNIVERSITY WARD CENTER FOR NUCLEAR STUDIES TRIGA REACTOR DOCKET NO. 50-157
1.0 INTRODUCTION
By letter dated June 24, 2003, as supplemented December 6, 2005, and January 19 and March 27, 2006, Cornell University (the licensee) submitted a request for amendment of Facility Operating License No. R-80 for the Cornell University Ward Center for Nuclear Studies (WCNS) TRIGA Reactor. The requested changes removes authorization from the license to operate the reactor and possess special nuclear material.
2.0 EVALUATION The WCNS TRIGA Reactor ceased operations on April 21, 2003. The TRIGA reactor's fuel was shipped to the U.S. Department of Energy (DOE), arriving at the Idaho National Laboratory on November 20, 2003. A WCNS Decommissioning Plan (WCNS DP) is currently being reviewed by the NRC staff. If approved, by the Commission, the licensee, stated that it intends to aggressively pursue the completion of decommissioning activities.
With Amendment No. 13 to the Facility Operating License No. R-80, the licensee has proposed to remove the authority to operate the reactor and eliminate the possession of special nuclear material from the license.
In support of the request for license amendment, the licensee has taken the following actions and changes to the license.
Licensee Actions Taken in Support of the Amendment Request The following actions document the removal of all SNM and sealed neutron sources from Facility Operating License No. R-80.
D. On April 21, 2003, the Cornell TRIGA Reactor was permanently shut down.
E. TRIGA fuel was removed from Ward Laboratory during the week of November 10, 2003, and arrived at the storage site of the Idaho National Engineering and Environmental Laboratory facility in Idaho Falls, Idaho on November 20, 2003.
F. On January 28, 2004, forty four grams of Pu-239 in the form of three sealed Pu-Be sources were transferred to Los Alamos National Laboratory, Los Alamos, NM.
G. On June 8, 2004, 76 grams of 93% enriched uranium in the form of metal foil were transferred to Kansas State University, Facility License No. R-88.
H. On June 23, 2004, four grams of 93% enriched uranium in the form of fission chambers were transferred to IST Corporation, Horseheads, NY.
I. On March 13, 2006, the 2 curie sealed Americium-Beryllium neutron source was transferred to NSSI, Houston, TX.
J. The residual material from a Polonium 210-Beryllium sealed neutron source was transferred to the Cornell Environmental Health and Safety byproduct license for decay and disposal.
Remove the authority to operate the reactor To reflect this change in the status of the facility, the licensee requested that license condition 2.B.1 be changed to possess, but not to operate. Therefore the license condition 2.B.1. is amended to read:
2.B.1. Pursuant to Section 104c of the Act and 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, to possess, but not operate, the reactor at the designated location in Ithaca, New York, in accordance with the procedures and limitations described in the application and in this license.
In addition paragraph 2.C.1. is amending to reflect that the facility is not authorized to operate and will read:
2.C.1 Maximum Power Level The licensee shall not possess fuel and therefore cannot load the core and operate the reactor.
Since the special nuclear material that may have been produced during past operation was shipped to DOE with the fuel, the license condition 2.B.4 is amended to retain possession, but not separation, of byproduct material produced by past operation of the facility. Therefore paragraph 2.B.4. shall read:
2.B.4 Pursuant to the Act and 10 CFR Part 30, Rules of General Applicability to Domestic Licensing of Byproduct Material at the reactor facility, to possess,
but not separate, such byproduct materials as may have been produced by operation of the reactor prior to its permanent shutdown.
All fuel has been permanently removed from the reactor and shipped to the U.S. DOE and it is not possible for the licensee to operate the reactor. The staff finds these changes to the license acceptable because they remove authority to operate the reactor and to possess special nuclear material as requested by the licensee.
Eliminate Possession of Special Nuclear Material Specified Sealed Sources The licensee has requested the authority to possess special nuclear material be removed. To that end license conditions 2.B.2 and 2.B.3 for the possession of special nuclear material and sealed neutron sources are deleted. All special nuclear material and sealed neutron sources licensed under license R-80 have been returned to the U.S. DOE or disposed of after decay.
The staff finds these changes to the license acceptable. Current license conditions 2.B.2 and 2.B.3 are deleted from Facility Operating License No. R-80.
Changes to the Technical Specifications The Board of Trustees of Cornell University voted on May 25, 2001, to accept the recommendation of Cornell President Hunter R. Rawlings III to close the WCNS and to decommission the nuclear research reactors associated with the Center. Consequently, by letter on June 24, 2003, as supplemented December 6, 2005, and January 19 and March 27, 2006, Cornell requested that its Operating License No. R-80 be amended to withdraw U. S. Nuclear Regulatory Commission (NRC) authorization to operate the TRIGA reactor and to receive and to possess Special Nuclear Material (SNM), and to make Technical Specification (TS) changes to support those two changes to the license and the decommissioning of WCNS. In addition, these changes will bring alignment between the Administrative Controls section of Appendix A of the license for the TRIGA reactor, R-80, Administrative Controls section of Appendix A of the license for the ZPR, R-89, and the administrative plans in the WCNS DP. This amendment will be issued concurrently with:
- an amendment No. 14 to Facility Operating License No. R-80 approving the DP of the WCNS,
- an amendment No. 8 to Facility Operating License No. R-89 approving the DP of the WCNS, and
- an amendment No. 7 to Facility Operating License No. R-89 removing the authorization to possess SNM and source material.
Specific Changes to Appendix A of Facility Operating License No. R-80 A WCNS DP was submitted to the U.S. NRC on August 22, 2003, as supplemented on May 13, September 27, October 26 and December 13, 2005, and February 13, 2006. In support of that submission and the request for removing authorization to operate the TRIGA reactor and to
possess SNM, changes to Appendix A of the license were requested. Evaluation of those changes follows:
TS 3.0 LIMITING CONDITIONS FOR OPERATION TS 3.1 Reactivity TS 3.2 Steady-State Operation TS 3.3 Pulse Operation TSs 3.1, 3.2, and 3.3 were required during operation to meet 10 CFR 50.36(c)(2)(ii)(B). The licensee certified that they have permanently ceased operation and have shipped the fuel off site. Meeting the above regulation is no longer necessary. The staff finds it acceptable that these TSs be removed.
TS 3.4 Measuring Channels The licensee states that as a result of reactor shut down and removal of all fuel, the danger from radiation is highly reduced. The licensee commits, in the WCNS DP (ref. 1), to meet the need for protection against potential radiation hazards during decommissioning (see Section 3.1.1 of the WCNS DP (ref. 1), RESPIRATORY PROTECTION and TEDE ALARA EVALUATION).
The previously approved TS 3.4 was in place, in part, to meet the requirement of 10 CFR 50.36 (c)(2)(ii)(B). Since the licensee has permanently ceased operation and the fuel has been shipped there is no longer a need to meet this requirement. Therefore, the licensee is proposing to remove specifications of requiring measuring channels (ie. fuel element temperature and reactor power level) that are not needed with a permanently shutdown and decommissioning reactor. Additionally, the previous TS provided for maintaining radiation instruments for the protection of the public and the workers during operation. The radiation levels that exist now after shutdown and will exist during decommissioning are much lower and the instrumentation needed to monitor those conditions are different. The licensee is requesting the change in the TS to allow for those changing conditions by removing the continuous air radiation monitor and the exhaust plenum radiation monitor. The licensee is retaining the requirement for 2 operable area radiation monitors. The licensee has addressed radiation protection in the WCNS DP and those plans have been reviewed by the staff. The staff finds that this change of TS 3.4 follows from the staffs conclusions made in the SE for amendment that accompanies the amendment No. 14 of R-80 approving the WCNS decommissioning amendment (see Section 3.2.2 of the SE for amendment No. 14 of R-80 (ref.
2)) and is therefore acceptable.
TS 3.5 Safety Channels and Control Rod Drop Time TS 3.6 Release of Argon-41 TS 3.5 was required to meet 10 CFR 50.36(c)(2)(ii)(C). Since the licensee has permanently ceased operation and has shipped the fuel off site, the need to meet that requirement is no longer necessary. Since operation of the reactor has permanently ceased, Argon-41 is no longer being produced and the radiation hazard associated with this material no longer exists and therefore the specification is not necessary. The staff finds it acceptable that this TS be removed.
TS 3.7 Ventilation System The licensee has proposed a deletion of this TS. The licensee stated that as a result of reactor shut down and removal of all fuel, the ventilation system is no longer needed. However, the need (of ventilation) during decommissioning is addressed in Section 3.1.1 of the WCNS DP, AIRBORNE EFFLUENT MONITORING.
The previously approved TS 3.7 was in place, in part, to meet the requirement of 10 CFR 50.36 (c)(2)(ii)(C). Since the licensee has permanently ceased operation and the fuel has been shipped, there is no longer a need to meet this requirement. The radiations levels that exist now after shutdown and will exist during decommissioning are much lower and the structures needed to support decommissioning have and will continue to change throughout the process.
The licensee is requesting the removal of the specification requiring ventilation during operation, since operation is no longer possible. The licensee has addressed ventilation in the WCNS DP and that plan has been reviewed by the staff. The staff finds that this change of TS 3.7 is consistent with the WCNS DP and the staffs conclusions made in the SE for amendment that accompanies the amendment No. 14 of R-80 approving the WCNS decommissioning amendment (see Section 3.2.2.2.2 of the SE for amendment No. 14 of R-80 (ref. 2)) and is therefore acceptable.
TS 3.8 Limitations on Experiments TS 3.9 Fuel Integrity As stated by the licensee, since operation of the facility has ceased permanently and the fuel has been shipped off site, the above two TSs are no longer needed. There are no experiments being performed and there is no concern of fuel integrity. The staff finds that the removal of TSs 3.8 and 3.9 are acceptable.
TS 3.10 Reactor Pool Water The previously approved TS 3.10 was in place, in part, to meet the requirement of 10 CFR 50.36 (c)(2)(ii)(C). That requirement no longer applies since operations have permanently ceased and all fuel has been transferred to the DOE. The proposed TS 3.10 applies to maintaining the water level in the Cornell TRIGA reactor pool while irradiated reactor hardware is within the pool to reduce radiation levels to acceptable levels as required by 10 CFR Part 20.
It is written to permit draining the pool when the hardware is removed and the shielding afforded by the water is no longer needed to meet 10 CFR Part 20. The staff finds this change acceptable.
TS 3.11 Restricted Mode Operation This TS was originally established to meet the requirement of 10 CFR 50.36(c)(ii)(B). Since, as stated by the licensee, operation has permanently ceased and all fuel has been shipped, this TS is no longer needed. The staff finds this change acceptable.
TS 4.0 SURVEILLANCE REQUIREMENTS TS 4.1 Fuel TS 4.2 Control Rods TS 4.3 Reactor Safety System The first two TSs, 4.1 and 4.2, are no longer required since the fuel has been shipped and operations have ceased. This eliminates the need for surveillance of the fuel and control rods.
TS 4.3 has been eliminated since the operation of the reactor has permanently ceased and the TS requiring the Reactor Safety System has been removed and surveillance of the Reactor Safety System is no longer needed (see the conclusions concerning TS 3.5 above). The staff finds the removal of these three TSs acceptable.
TS 4.4 Radiation Monitoring Equipment This specification is proposed to be modified to reflect the fact that operations have permanently ceased and all fuel has been transferred to the DOE. The proposed change reduces the surveillance frequency to monthly and before any handling or movement of radioactive material within or from the reactor room.
The licensee requested this changed to reflect the new surveillance requirements necessitated by the changes made to TS 3.4 (see the conclusions concerning TS 3.4 above).
TS 4.5 Maintenance This specification established the surveillance requirements following maintenance of the control or safety system. TS 4.5 will be eliminated since the operation of the reactor has permanently ceased and the TS requiring the Reactor Safety System will be removed and the need for a control system will be eliminated (see the conclusions concerning TS 3.5 above).
The staff finds the removal of this TS acceptable.
TS 4.6 Reactor Pool Water The licensee states that as a result of reactor shut down and removal of all fuel, the danger from radiation is highly reduced. Therefore, the pool water level will be maintained at a level to
minimize personnel radiation exposure to irradiated reactor hardware. The maintenance of the conductivity of pool water is no longer required since all fuel has been removed and corrosion is not an issue.
The licensee has proposed modification of this TS to reflect the changes to TS 3.10 above.
The pool water level is only needed to meet the requirements of 10 CFR Part 20. When the activated hardware is disposed, the pool water may be removed as needed to continue the decommissioning. The water conductivity requirement was previously required to minimize corrosion of the fuel clad and meet 10 CFR 50.36 (c)(ii)(C). The fuel has been shipped and this amendment will remove the authorization to possess fuel; therefore, the maintenance of pool water conductivity is no longer required. The staff finds the change to TS 4.6 acceptable.
TS 4.7 Special Nuclear Materials This specification applies to the surveillance requirements for the sealed plutonium source material. The licensee shipped all plutonium source material to the DOE. The elimination of this TS is appropriate and the staff finds it acceptable.
TS 5.0 DESIGN FEATURES TS 5.1 Reactor Fuel TS 5.2 Reactor Building TS 5.3 Fuel Storage These TSs were needed to meet in the requirements of 10 CFR 50.36(c)(ii)(C). Since operations has ceased and all fuel has been shipped there is no longer a need to meet this regulation. This amendment removes authorization to possess fuel. The staff finds the removal of these TSs acceptable.
Changes to the Organizational Structure:
The staff has reviewed the changes to the management and organizational structures that include the make up and the specific responsibilities of the Cornell Decommissioning and Decontamination (D and D) Oversight Committee. Before these changes, the management organization and the Ward Center Safety Committee were structured to manage and provide oversight and audit for an operational reactor as opposed to the present permanently shutdown decommissioning reactor. The staff finds that with the changes the management and the Cornell D and D Oversight Committee will be better suited to oversee all decommissioning activities conducted by the decommissioning contractor, including the review and approval of changes to the facility and of decommissioning related plans and procedures, and in accordance with the WCNS DP and the regulations.
The specific changes and evaluation of those changes follow:
TS 6.0 ADMINISTRATIVE CONTROLS
TS 6.1 Organization and Responsibilities of Personnel The licensee proposed modifying TSs 6.1 b), c), h), and i) and the Organizational Chart to specify the new organizational structure to be used during the D and D of the Cornell ZPR, TRIGA, and the WCNS. This structure is delineated in the WCNS DP. The new administrative and oversight organizational structure is better suited to manage D and D activities as opposed to operating a rector. The staff finds the changes acceptable.
TS 6.1 d), e), and f)
The licensee proposed removing TS 6.1 d), e), and f) to specify the new organizational structure to be used during the D and D of the Cornell ZPR, TRIGA, and the WCNS. This structure is delineated in the WCNS DP. The positions that were described in the deleted sections are not required for a permanently shutdown and decommissioning reactor. The staff finds the changes acceptable.
TS 6.2 Review and Audit TSs 6.2 a), c), e), and f) were modified by the licensee to specify the new organizational structure to be used during the Decommissioning and Decontamination of the Cornell ZPR, TRIGA, and the WCNS. This structure is delineated in the WCNS DP (ref. 1). The staff finds the changes acceptable.
TS 6.3 Procedures TSs 6.3 a), b), c), and d) will be modified by the licensee to specify the new organizational structure to be used during the D and D of the Cornell ZPR, TRIGA, and the WCNS. This structure is delineated in the WCNS DP. The changes are being made to reflect the new name of the Cornell D and D Oversight Committee. The staff finds the changes acceptable.
TS 6.3 a) 1, and a) 2 TSs 6.3 a) 1 and 2 will be removed by the licensee since operation has permanently ceased and all fuel has been transferred to the DOE. Since these procedures are no longer needed the staff finds these changes acceptable.
TS 6.4 Review of Proposals for Experiments The licensee stated that since all operation has permanently ceased this TS, which specified limits on experiments, is no longer needed. The staff accepts the removal of this TS.
TS 6.5 Emergency Plan and Procedures This TS will be modified by the licensee to specify the new organizational structure to be used during the D and D of the Cornell ZPR, TRIGA, and the WCNS. This structure is delineated in the WCNS DP. The change is being made to reflect the new name of the Cornell D and D Oversight Committee. The staff finds the changes acceptable.
TS 6.6 Operator Re-qualification TS 6.8 Action To Be Taken In The Event A Safety Limit Is Exceeded The licensee stated that TS 6.6 is no longer needed since the fuel has been shipped and there is no longer a need for licensed operators. The licensee also stated that since operation has permanently ceased and the fuel is shipped a safety limit can no longer be exceeded and therefore TS 6.8 is not needed. The staff finds the removal of TSs 6.6 and 6.8 acceptable.
TS 6.9 Action To Be Taken In The Event Of A Reportable Occurrence This TS will be modified by the licensee to specify the new organizational structure to be used during the D and D of the Cornell ZPR, TRIGA, and the WCNS. This structure is delineated in the WCNS DP. This change removes from the specification those events that are no longer possible for a permanently shutdown and decommissioning reactor. In addition, the new name of the Cornell D and D Oversight Committee is added to the specification. The staff finds the changes acceptable.
TS 6.10 Plant Operating Records TS 6.10 b) 7 will be modified by the licensee to add decontamination shipping records to the list of documents that should be retained for the life of the facility (until license termination). These were not part of the operations documents and were therefore not listed in previous versions of the TSs. The staff finds the changes acceptable.
TS 6.11 Reporting Requirements TS 6.11d) will be removed by the licensee since this specification is meaningless with operation permanently ceased, the fuel shipped, and authorization to possess fuel removed. The staff finds this change acceptable.
6.1.3 Conclusions Concerning Appendix A of License No. R-80 The staff has reviewed and approved the above changes to the technical specifications contained in the referenced license:
- Removal of Authority to Possess Fuel: The licensee has requested that the authority to possess fuel be removed from R-80. The fuel assemblies that once supported reactor operations has been off loaded and removed from the site. With the certification of the material being removed from the site the staff has reviewed and accepted the changes to the referenced license.
- Changes to Surveillance, Limiting Conditions of Operation (LCO), and required operational safety equipment and specifications: The licensee has requested that the authority to operate the reactor and possess fuel be removed from R-80. With that authority change the TSs that are no longer valid or necessary to ensure the health and
safety of the public and protect the environment will be deleted or modified. The staff has reviewed and accepted the changes to the referenced license.
- Changes to the Organizational Structure: The staff has reviewed and accepted the changes to the management and organizational structures that includes specific responsibilities that will be administered by the Cornell D and D Oversight Committee.
These changes reflect the change in the activities at the WCNS from reactor operations to possession and decommissioning. As such, the staff has determined that the project management structure for the decommissioning of the WCNS, which includes the ZPR, is consistent with the guidance on the role and composition of the facility safety committee provided in Appendix 17.1 of NUREG-1537.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes in inspection and surveillance requirements. The staff has determined that this amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released off site, and no significant increase in individual or cumulative occupational radiation exposure. In addition, this amendment involves changes in the category of recordkeeping, reporting, and administrative procedures and requirements. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10) respectively. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, on the basis of the considerations discussed above, that (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated, or create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes; and (3) such changes are in compliance with the Commissions regulations and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public.
5.0 REFERENCES
- 4. Cornell University Decommissioning Plan for the Ward Center for Nuclear Studies at Cornell University, Rev. 1, as supplemented July 2003
- 5. Safety Evaluation by the Office of Nuclear Regulation Related to the Decommissioning of the Ward Center for Nuclear Studies at Cornell University, June 2006 Principal Contributor: Daniel E. Hughes Date: June 6, 2006