ML15261A452
| ML15261A452 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/27/2015 |
| From: | John Hickman Reactor Decommissioning Branch |
| To: | Hobbs T Duke Energy Florida |
| Orenak M | |
| References | |
| CAC L53082, TAC MF6235 | |
| Download: ML15261A452 (10) | |
Text
November 27, 2015 Mr. Terry D. Hobbs General Manager, Decommissioning Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - ISSUANCE OF AMENDMENT REGARDING TECHNICAL SPECIFICATION CHANGE OF MANAGEMENT TITLES TO GENERAL MANAGER DECOMMISSIONING (CAC NO. L53082)
Dear Mr. Hobbs:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 249 to Facility Operating License No. DPR-72 for the Crystal River Unit 3 Nuclear Generating Plant in response to your letter dated May 7, 2015. The amendment revises Technical Specifications (TSs) 5.1.1, 5.3.2, and 5.6.2.3 by changing the management title from the Plant Manager to the General Manager Decommissioning. The amendment also revises TS 5.2.1.b, by changing the management titles of both the Decommissioning Director and the Plant Manager to the General Manager Decommissioning.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
John B. Hickman, Project Manager Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards Docket No. 50-302
Enclosures:
- 1. Amendment No. 249 to DPR-72
- 2. Safety Evaluation cc w/enclosures: Distribution via Listserv
- SE memo dated OFFICE NRR/DORL/LPL4-2 NRR/DORL/LPL4-2 NRR/DRA/APHB*
NRR/DSS/STSB NAME SKoenick PBlechman SWeerakkody RElliott DATE 9/30/15 9/30/15 8/11/15 10/15/15 OFFICE OGC NLO NRR/DORL/LPL4-2 NMSS/DUWP/RDB NMSS/DUWP NMSS/DUWP/RDB NAME MSpencer MKhanna BWatson APersinko JHickman DATE 11/2/15 11/12/15 11/24/15 11/27/15 11/27/15
DUKE ENERGY FLORIDA, INC.
SEMINOLE ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 249 License No. DPR-72
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Crystal River Unit 3 Nuclear Generating Plant (the facility) Facility Operating License No. DPR-72 filed by Duke Energy Florida, Inc. and Seminole Electric Cooperative, Inc. (the licensees), dated May 7, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; 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; and
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 249, are hereby incorporated in the license. Duke Energy Florida, Inc. shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Andrew Persinko, Acting Director Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: November 27, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 249 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of Facility Operating License DPR-72 and Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License No. DPR-72 REMOVE INSERT Technical Specifications REMOVE INSERT 5.0-1 5.0-1 5.0-2 5.0-2 5.0-4 5.0-4 5.0-9 5.0-9
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 249 TO FACILITY OPERATING LICENSE NO. DPR-72 DUKE ENERGY FLORIDA, INC.
SEMINOLE ELECTRIC COOPERATIVE, INC.
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302
1.0 INTRODUCTION
By application dated May 7, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15134A160), Duke Energy Florida, Inc. (the licensee), requested changes to the technical specifications (TSs) for Crystal River Unit 3 Nuclear Generating Plant (CR-3).
The proposed changes would revise the titles of Plant Manager and Decommissioning Director to General Manager Decommissioning in the Administrative Controls section of the TSs. The affected TSs include 5.1.1, 5.2.1.b, 5.3.2, and 5.6.2.3. The Decommissioning Director position underwent a title change to General Manager Decommissioning. Further, the Plant Manager position is being eliminated and will not be in effect once CR-3 enters the SAFSTOR phase of decommissioning. All responsibilities of the Plant Manager, as delineated in the CR-3 TS, are being transferred to the General Manager Decommissioning.
2.0 REGULATORY EVALUATION
The regulatory requirements and guidance that the Nuclear Regulatory Commission (NRC) staff considered in its review of the license amendment request are as follows:
Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the application. The NRCs regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications. Pursuant to 10 CFR 50.36, each operating license issued by the Commission includes TSs including items in a category on administrative controls. Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. In addition, the regulation in 10 CFR 50.36(c)(6), Decommissioning,
applicable to nuclear reactor facilities that have submitted the certifications required by 10 CFR 50.82(a)(1), states that technical specifications will be determined on a case-by-case basis.
NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP), Chapter 13, Section 13.1.2/3, Operating Organization, Revision 6, dated March 2007 (ADAMS Accession No. ML070250009).
3.0 TECHNICAL EVALUATION
The scope of this evaluation is the Administrative Controls section of CR-3s permanently defueled technical specifications, specifically TSs 5.1.1, 5.2.1.b, 5.3.2, and 5.6.2.3. The licensee proposes organizational changes associated with decommissioning and placing CR-3 in a permanently defueled safe condition. The licensee states that the responsibility, review and approval authority for these administrative controls remains at the same or higher level.
3.1 Responsibility Current TS 5.1.1 states:
The Plant Manager shall be responsible for overall facility functions and shall delegate in writing the succession to this responsibility during his absence.
The Plant Manager or his designee shall approve, prior to implementation, each proposed test, experiment or modifications to systems or equipment that affect nuclear safety.
Revised TS 5.1.1 will state:
The General Manager Decommissioning shall be responsible for overall facility functions and shall delegate in writing the succession to this responsibility during his absence.
The General Manager Decommissioning or his designee shall approve, prior to implementation, each proposed test, experiment or modifications to systems or equipment that affect stored nuclear fuel.
The proposed TS 5.1.1 changes the Plant Manager title to General Manager Decommissioning.
Since the Plant Manager position will be eliminated as CR-3 enters the SAFSTOR phase of decommissioning, the proposed change transfers the responsibility to the General Manager Decommissioning-a position title change of the Decommissioning Director. According to 10 CFR 50.36(c)(6), Decommissioning, administrative controls can be developed on a case-by-case basis. Given that CR-3 will be entering the SAFSTOR phase of decommissioning, this change is acceptable because the responsibility, review, and approval authority for this TS remains at a similar level.
3.2 Onsite and Offsite Organizations Current TS 5.2.1.b states:
The Decommissioning Director shall have overall responsibility for the safe handling and storage of nuclear fuel and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure the safe handling and storage of nuclear fuel. The Plant Manager shall be responsible to control those onsite activities necessary for the safe handling and storage of nuclear fuel; and Revised TS 5.2.1.b will state:
The General Manager Decommissioning shall have overall responsibility for the safe handling and storage of nuclear fuel and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure the safe handling and storage of nuclear fuel. The General Manager Decommissioning shall be responsible to control those onsite activities necessary for the safe handling and storage of nuclear fuel; and The proposed TS 5.2.1.b changes the Decommissioning Director and the Plant General Manager titles to General Manager Decommissioning. The responsibilities of the positions, although combined, are unchanged. According to 10 CFR 50.36(c)(6), Decommissioning, administrative controls can be developed on a case-by-case basis. Given that CR-3 will be entering the SAFSTOR phase of decommissioning, this change is acceptable because the consolidated position retains sufficient management oversight to maintain the facility in a safe manner.
3.3 Unit Staff Qualifications Current TS 5.3.2 states:
A training and retraining program for the Certified Fuel Handler positions shall be maintained under the direction of the Plant Manager.
Revised TS 5.3.2 will state:
A training and retraining program for the Certified Fuel Handler positions shall be maintained under the direction of the General Manager Decommissioning.
The proposed TS 5.3.2 changes the Plant Manager title to General Manager Decommissioning.
Since the Plant Manager position will be eliminated as CR-3 enters the SAFSTOR phase of decommissioning, the proposed change transfers the responsibility to the General Manager Decommissioning-a position title change of the Decommissioning Director. According to 10 CFR 50.36(c)(6), Decommissioning, administrative controls can be developed on a case-by-case basis. Given that CR-3 will be entering the SAFSTOR phase of decommissioning, this
change is acceptable because the responsibility, review, and approval authority for this TS remains at a similar level.
3.4 Licensee Initiated Changes to the ODCM Current TS 5.6.2.3 states:
Licensee initiated changes to the ODCM [Offsite Dose Calculation Manual]:
- 2. Shall become effective after review and acceptance by the on-site review function and the approval of the Plant Manager; and Revised TS 5.6.2.3 will state:
Licensee initiated changes to the ODCM:
- 2. Shall become effective after review and acceptance by the on-site review function and the approval of the General Manager Decommissioning; and The proposed TS 5.6.2.3 changes the Plant Manager title to General Manager Decommissioning. Since the Plant Manager position will be eliminated as CR-3 enters the SAFSTOR phase of decommissioning, the proposed change transfers the responsibility to the General Manager Decommissioning-a position title change of the Decommissioning Director.
According to 10 CFR 50.36(c)(6), Decommissioning, administrative controls can be developed on a case-by-case basis. Given that CR-3 will be entering the SAFSTOR phase of decommissioning, this change is acceptable because the responsibility, review, and approval authority for this TS remains at a similar level.
4.0
SUMMARY
According to 10 CFR 50.36(c)(6), Decommissioning, administrative controls can be developed on a case-by-case basis. The proposed changes to the TSs are necessary to ensure that all responsibilities, as delineated in the CR-3 TSs, are being transferred from the Plant Manager to the equivalent position within the new organization as CR-3 enters the SAFSTOR phase of decommissioning. As all the responsibilities are being maintained, the proposed changes are acceptable.
5.0 STATE CONSULTATION
Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Ms. Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments. In an email dated July 25, 2012 (ADAMS Accession No. ML12208A014), from Cynthia Becker, Florida State Bureau of Radiation Control, to Farideh Saba, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida confirmed that the May 2003 letter continues to reflect the States position on notification of issuance of license amendments.
6.0 ENVIRONMENTAL CONSIDERATION
S The amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: G. Lapinsky Date: August 11, 2015