ML110480461
| ML110480461 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/19/2011 |
| From: | Hall J Plant Licensing Branch IV |
| To: | Matthew Sunseri Wolf Creek |
| Singal, Balwant, 415-3016, NRR/DORL/LPL4 | |
| References | |
| TAC ME4919 | |
| Download: ML110480461 (9) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 19, 2011 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 SUB..IECT:
WOLF CREEK GENERATING STATION -ISSUANCE OF AMENDMENT RE:
CORRECTION OF TYPOGRAPHICAL ERROR IN TECHNICAL SPECIFICATION 5.0, "ADMINISTRATIVE CONTROLS" (TAC NO. ME4919)
Dear Mr. Sunseri:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 196 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 October 21, 2010.
The amendment corrects a typographical error in TS 5.0, "ADMINISTRATIVE CONTROLS."
The current TS, on page 5.0-31, has two paragraphs numbered as 5.7.2.d.3. The amendment renumbers the second paragraph as 5.7.2.d.4.
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, JJ::~S~~jed Manager Plant licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. Amendment No. 196 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. 196 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 October 21, 2010, 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 (ii) 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. 196, 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.
The license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q ':.. \\---:\\ (. S\\~p -t-.
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:
Apr; 1 19, 2011
ATTACHMENT TO LICENSE AMENDMENT NO. 196 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.
The corresponding overleaf pages are provided to maintain document completeness.
Renewed Facility Operating License REMOVE INSERT 4
4 Technical Specifications REMOVE INSERT 5.0-31 5.0-31
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. 196, and the Environmental Protection Plan contained in Appendix S, 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. 196
5.7.2 High Radiation Area 5.7 5.7 High Radiation Area High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation: (continued)
- c.
Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d.
Each individual or group entering such an area shall possess:
- 1.
A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
- 2.
A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area. or
- 3.
A self-reading dosimeter (e.g.. pocket ionization chamber or electronic dosimeter) and.
(i)
Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)
Be under the surveillance as specified in the RWP or equivalent. while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area, or
- 4.
In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.
(continued)
Wolf Creek - Unit 1 5.0-31 Amendment No. 123. 142, 158, 164, 7-9, 196
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 196 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 applic:ation dated October 21,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML103070076), Wolf Creek Nuclear Operating Corporation (the licensee) requested changes to the Technical Specifications (TSs, Appendix A to Renewed Facility Operating License No. NPF-42) for the Wolf Creek Generating Station (WCGS).
The proposed amendment would correct a typographical error in TS 5.0, "ADMINISTRATIVE CONTROLS." The current TS, on page 5.0-31, has two paragraphs numbered as 5.7.2.d.3.
The amendment would renumber the second paragraph as 5.7.2.dA.
2.0 R.EGULATORY EVALUATION Section '182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. These TSs are derived from the plant safety analyses. Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical specifications," contains the requirements for 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.
The proposed amendment corrects a typographical error on page 5.0-31 of TS 5.0, "ADMINISTRATIVE CONTROLS."
3.0 TECHNICAL EVALUATION
By letter dated May 15,1997 (ADAMS Legacy Accession No. 9705210324), the licensee submitted an application for conversion of the existing TSs to Improved TSs, which included TS 5.7.2, "High Radiation Areas with Dose Rates Greater Than 1.0 rem/hour at 30 Centimeters
- 2 from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hr at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation." In response to a request for additional information by the U.S. Nuclear Regulatory Commission (NRC) staff, the licensee provided a revised page for TS 5.7.2 that included paragraph 5.7.2.dA (licensee's letter dated September 24, 1998 (ADAMS Legacy Accession No. 980fI300290)). However, with the issuance of Amendment No. 123 (NRC letter dated March 3'1, 1999 (ADAMS Legacy Accession No. 9904070153), a typographical error was introducE~d in the numbering of paragraph 5.7.2.dA.
The proposed change corrects only a typographical error in TS 5.7.2 by renumbering second paragraph 5.7.2.d.3 to 5.7.2.dA on page 5.0-31 of the TSs. There is no change to the contents of the existing TSs, WCGS design, and/or analysis. Therefore, TS requirements continue to be met and the proposed change does not change any of the TS requirements.
The NRC staff concludes that the change is typographical in nature and 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 changes the format of the license or permit or otherwise makes editorial, correctivl~ or other minor revisions, including the updating of NRC-approved references. 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 O)(v). The Commission previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding published in the Federal Register on December 14, 2010 (75 FR 77917). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10)(v). 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) there is reasonable assurance that 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: Balwant K. Singal Date: Apr; 1 19, 2011
ML110480461 4/PM NRR/LPL4/PM NRR/LPL4/LA DIRS/ITSB/BC OGC NLO NRR/LPL4/BC MMarkley JRHali JBurkhardt RElliott MSpencer (BSingal for)
JRHall 4/5/11 3/31/11 4/11111 4/12111 4118/11 4119111