ML120540291
| ML120540291 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/02/2012 |
| From: | Hall J Plant Licensing Branch IV |
| To: | Matthew Sunseri Wolf Creek |
| Poole J, NRR/DORL/LP-WB, 301-415-2048 | |
| References | |
| TAC ME6151 | |
| Download: ML120540291 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 2, 2012 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION -ISSUANCE OF AMENDMENT REGARDING TECHNICAL SPECIFICATION 5.3, "UNIT STAFF QUALIFICATIONS" (TAC NO. ME6151)
Dear Mr. Sunseri:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 198 to Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated April 22, 2011.
The amendment approves changes to TS 5.3, "Unit Staff Qualifications," by making two administrative changes to TS 5.3.1.1. Specifically, the changes remove the operator license applicants' education and experience eligibility requirements, and correct inadvertent omissions in previous amendments relative to the Licensed Operators' and Senior Operators' qualification requirements.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, JI (70 "1.."". ~
J, S R. Hall, sen;o: Project Manager J::
fJ Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Amendment No. 198 to NPF-42
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 198 License No. NPF-42
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility)
Renewed Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated April 22, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, 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 Oi) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license 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 Commission's regulations and all applicable requirements have been satisfied.
-2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-42 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 198, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley. Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: April 2, 2012
ATTACHMENT TO LICENSE AMENDMENT NO. 198 RENEWED FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Renewed Facility Operating License No. NPF-42 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.
Renewed Facility Operating License REMOVE INSERT 4
4 T echnica\\ Specifications REMOVE INSERT 5.0-4 5.0-4
4 (5)
The Operating Corporation, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
The Operating Corporation, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission, now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The Operating Corporation is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 198, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions Kansas Gas &Electric Company and Kansas City Power &Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.
(4)
Environmental Qualification (Section 3.11, SSER #4, Section 3.11, SSER#5)""
Deleted per Amendment No. 141.
- The parenthetical notation following the title of many license conditions denotes the section of the supporting Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-42 Amendment No. 198
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSIIANS 3.1-1978 with the following exceptions:
5.3.1.1 Licensed Operators and Senior Operators shall meet or exceed the qualifications of ANSIIANS 3.1-1981 as endorsed by Regulatory Guide 1.8, Revision 2, and 10 CFR 55.
5.3.1.2 The Radiation Protection Manager shall be a supervisor with line responsibility for operational health physics who meets or exceeds the qualifications of Regulatory Guide 1.8, September 1975 for a Radiation Protection Manager. The Radiation Protection Manager will be designated by the plant manager.
5.3.1.3 The position of operations manager shall hold or have previously held a senior reactor operator license for a similar unit (PWR).
5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).
Wolf Creek - Unit 1 5.0-4 Amendment No. 123, 140, HiO, 150, 198
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 198 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By application dated April 22, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11123A226), Wolf Creek Nuclear Operating Corporation (the licensee) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC) to revise the Technical Specifications (TSs) for Wolf Creek Generating Station (WCGS). The amendment would approve changes to TS 5.3, "Unit Staff Qualifications,"
by making two administrative changes to TS 5.3.1.1. Specifically, the changes would remove the operator license applicants' education and experience eligibility requirements, and correct inadvertent omissions in previous amendments relative to the Licensed Operators' and Senior Operators' qualification requirements.
The current requirement specifies that operator license applicants' education and experience eligibility requirement shall be reviewed and approved by the NRC and that the positions of Shift Manager and Control Room Supervisor shall meet or exceed the qualifications of American National Standards Institute/American Nuclear Society (ANSI/ANS) 3.1-1981. The current requirement does not address position qualification requirements for licensed operators that were inadvertently deleted as a result of Amendment No. 150, dated November 26, 2002 (ADAMS Accession No. ML023380193). The licensee proposed to revise TS 5.3.1.1 to remove operator license applicants' education and experience requirements and add the requirement that licensed operators and senior operators shall meet or exceed the qualifications of ANSI/ANS 3.1-1981 as endorsed by NRC Regulatory Guide 1.8, Revision 2, "Qualification and Training of Personnel for Nuclear Power Plants," April 1987 (ADAMS Accession No. ML003739928), and Part 55, "Operators' Licenses," of Title 10 of the Code of Federal Regulations (10 CFR). The proposed changes will align the wording to language approved in NUREG-1431, Revision 3, "Standard Technical Specifications Westinghouse Plants,"
June 2004 (ADAMS Accession No. ML041830612).
-2
2.0 REGULATORY EVALUATION
In Section 50.36, "Technical specifications," of Title 10 of the Code of Federal Regulations (10 CFR), the NRC established its regulatory requirements related to the content of TSs.
Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
On March 20, 1985, the NRC issued the Commission Policy Statement on training and qualification of nuclear power plant personnel which endorsed the training accreditation process and the National Academy for Nuclear Training (NANT) guideline. In NRC Generic Letter (GL) 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing 10 CFR 55 and Conforming Amendments," dated March 19, 1987 (ADAMS Accession No. ML031150669), and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses,"
published November 1987 (publicly available at http://www.nrc.gov/reading-rm/doc collections/nuregs/staff/sr1262/#pubinfo), the NRC indicated it would accept a facility's licensed operator training program if the facility certified in writing that the program was accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel,"
and ANSI/ANS-3.1-1978, "Selection, Qualification and Training of Personnel for Nuclear Power Plants." Facility licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to revise or delete, as appropriate, the requirements that had been superseded.
On January 7,1992 (57 FR 537), the NRC published its proposed rule 10 CFR 50.120, "Training and qualification of nuclear power plant personnel." The proposed rule stated that, if adopted, the rule would supersede the Commission's Policy Statement on training and qualification of nuclear power plant personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistent with industry objectives and criteria, would be in compliance with this regulation. On April 26, 1993 (58 FR 21904), the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 10 CFR 50.120.
On January 18, 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-01, "Eligibility of Operator License Applicants" (ADAMS Accession No. ML003733003), to familiarize licensees with the NRC's current guidelines for the qualification and training of reactor operator and senior operator license applicants. RIS 2001-01 acknowledged that 10 CFR 55.31 (a)(4) allows the NRC to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program that is based on a SAT. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the National Nuclear Accrediting Board (NNAB); (2) accreditation of operator training programs suggests that facilities are implementing the education and experience guidelines endorsed by the NNAB; (3) NANT guidelines for education and experience (those in effect in 1987 or those issued in
- 3 January 2000) outline acceptable methods for implementing the Commission's regulations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator and senior operator education and experience and to update their documentation (e.g., Final Safety Analysis Report, Technical Specifications, and training program descriptions) to "enhance consistency and minimize confusion."
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes
Current TS 5.3.1.1 states:
The education and experience eligibility requirements for operator license applicants, and changes thereto, shall be those previously reviewed and approved by the NRC, specifically those referenced in letter dated October 7, 2004 0NO 04-0031). The positions of Shift Manager and Control Room Supervisor shall meet or exceed the qualifications of ANSIIANS 3.1-1981.
Revised TS 5.3.1.1 would state:
licensed Operators and Senior Operators shall meet or exceed the qualifications of ANSIIANS 3.1-1981 as endorsed by Regulatory Guide 1.8, Revision 2, and 10 CFR 55.
3.2
NRC Staff Evaluation
The licensee has proposed to remove the education and experience requirements for operator license applicants from the TS. The licensee stated in its letter dated April 22, 2011, that WCGS licensed operator training is accredited by the NANT and is based on a SAT. Since 10 CFR 55.31 (a)(4) allows the NRC to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program that is based on a SAT in lieu of details of operator license applicant's education and experience, this change meets the 10 CFR 55.31 (a)(4) requirements to apply for an operator's license and ensures the facility licensee maintains administrative controls that assure the operation of the facility in a safe manner by properly qualified licensed operators.
Therefore, the NRC staff concludes that removal of the education and experience requirements from the TS is acceptable.
The licensee has also proposed to apply the current qualification requirements for certain senior operators (the shift manager and control room supervisor positions) to all senior operators and to add qualification requirements for licensed operators that were inadvertently eliminated through the issuance of Amendment No. 150, dated November 26,2002. Additionally, TS 5.3.1.1 would also be revised to specify that the current qualification requirements of ANSIIANS 3.1-1981 are endorsed by Regulatory Guide 1.8, Revision 2. The NRC staff considers these changes to be administrative changes because they do not modify, add, delete, or relocate any technical requirements of the TSs and are consistent with NUREG-1431, "Standard Technical Specifications Westinghouse Plants"; therefore, the changes are
- 4 acceptable. In addition, the changes will not affect the 10 CFR 50.36(c)(5) requirement to ensure the licensee maintains administrative controls that assure the operation of the facility in a safe manner by properly qualified licensed operators.
Based on the above, the NRC staff concludes that the proposed revision and editorial changes to TS 5.3.1.1 are consistent with 10 CFR Part 55 and do not adversely affect nuclear safety or plant operations. Therefore, the staff concludes that the proposed changes to TS 5.3.1.1 are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
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)(1 0). 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.
6.0 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) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Currie Date: April 2, 2012
April 2, 2012 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION -ISSUANCE OF AMENDMENT REGARDING TECHNICAL SPECIFICATION 5.3, "UNIT STAFF QUALIFICATIONS" (TAC NO. ME6151)
Dear Mr. Sunseri:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 198 to Renewed Facility Operating License No. NPF-42 for the Wolf Creek Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated April 22, 2011.
The amendment approves changes to TS 5.3, "Unit Staff Qualifications," by making two administrative changes to TS 5.3.1.1. Specifically, the changes remove the operator license applicants' education and experience eligibility requirements, and correct inadvertent omissions in previous amendments relative to the Licensed Operators' and Senior Operators' qualification requirements.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RN James R. Hall, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Amendment No. 198 to NPF-42
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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