ML082390707
| ML082390707 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Oyster Creek, Byron, Braidwood, Clinton, Quad Cities, LaSalle, Crane |
| Issue date: | 08/21/2008 |
| From: | Gratton C Plant Licensing Branch III |
| To: | Pardee C AmerGen Energy Co, Exelon Generation Co |
| Gratton C, NRR, DORL, 415-1055 | |
| Shared Package | |
| ML080860679 | List: |
| References | |
| TAC MD6373, TAC MD6375 | |
| Download: ML082390707 (9) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 25, 2008 Mr. Charles G Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - ISSUANCE OF AMENDMENTS TO CHANGE TECHNICAL SPECIFICATION UNIT STAFF QUALIFICATIONS EDUCATION AND EXPERIENCE ELIGIBILITY REQUIREMENTS FOR LICENSED OPERATORS (TAC NOS. MD6364 THRU MD6378)
Dear Mr. Pardee:
The Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 152 to Facility Operating License No. NPF-72 and Amendment No. 152 to Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, respectively, and Amendment No. 156 to Facility Operating License No. NPF-37 and Amendment No. 156 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively, and Amendment No. 180 to Facility Operating License No. NPF-62 for the Clinton Power Station Unit No. 1, and Amendment No. 228 to Renewed Facility Operating License No. DPR-1 9 and Amendment No. 220 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, respectively, and Amendment No. 189 to Facility Operating License No. NPF-1 1 and Amendment No. 176 to Facility Operating License No.
NPF-1 8 for the LaSalle County Station, Units 1 and 2, respectively, and Amendment No. 267 to Facility Operating License No. DPR-1 6 for the Oyster Creek Nuclear Generating Station, and Amendment No. 267 to Facility Operating License No. DPR-44 and Amendment No. 271 to Facility Operating License No. DPR-56 for the Peach Bottom Atomic Power Station, Units 2 and 3, respectively, and Amendment No. 240 to Renewed Facility Operating License No.
DPR-29 and Amendment No. 235 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively, and Amendment No. 265 to Facility Operating License No. DPR-50 for the Three Mile Island Nuclear Station, Unit 1 (TMI-1).
The amendments are in response to your application dated July 19, 2007, as supplemented. on July 7, 2008.
I
C. Pardee
-2 The amendments will change the licensed operator training, qualification education and experience eligibility requirements in the Technical Specifications to correspond to the eligibility requirements contained in the National Academy for Nuclear Training Academy Document, ACAD 00-003, Revision 1, "Guidelines for Initial Training and Qualification of Licensed Operators," dated April 2004.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
Christopher Gratton, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461, 50-237, 50-249, 50-373, 50-374, 50-219, 50-277, 50-278, 50-254, 50-265, and 50-289
Enclosures:
- 1. Amendment No. 152
- 2. Amendment No. 152
- 3. Amendment No. 156
- 4. Amendment No. 156
- 5. Amendment No. 180
- 6. Amendment No. 228
- 7. Amendment No. 220
- 8. Amendment No. 189
- 9. Amendment No. 176
- 10. Amendment No. 267
- 11. Amendment No. 267
- 12. Amendment No. 271
- 13. Amendment No. 240
- 14. Amendment No. 235
- 15. Amendment No. 265
- 16. Safety Evaluation cc w/encls: See next page to NPF-72 to NPF-77 to NPF-37 to NPF-66 to NPF-62 to DPR-19 to DPR-25 to NPF-11 to NPF-18 to DPR-16 to DPR-44 to DPR-56 to DPR-29 to DPR-30 to DPR-50 I
Td-
,UNITED STATES 0NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 AMERGEN ENERGY COMPANY, LLC DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT RENEWED FACILITY OPERATING LICENSE Amendment No. 267 License No. DPR-16
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by AmerGen Energy Company, LLC, et al., (the licensee), dated July 19, 2007, as supplemented on July 7, 2008, 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, 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 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.
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 Facility Operating License No. DPR-1 6 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specificationz contained in Appendices A and B, as revised through Amendment No.267,, are hereby incorporated in the license. AmerGen Energy Company, LLC, shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION IRA!
Harold K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: July 25, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 267 RENEWED FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Facility Operating License and Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License DPR-16 Page 3 TS 6-2a License DPR-16 Page 3 TS 6-2a (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, or special nuclear materials as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
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 materials without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate such byproduct, source, or special nuclear materials as may be produced by the6 operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter 1 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 AmerGen Energy Company, LLC is authorized to operate the facility at steady-state power levels not in excess of 1930 megawatts (thermal) (100 percent rated power) in accordancewith the conditionsspecified herein.
(2)
Technical Specifications The Technical Specificationscontained in Appendices A and B, as revised through Amendment No. 267, are hereby incorporated in the license. AmerGen Energy Company, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Fire Protection AmerGen Energy Company, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report dated March 3, 1978, and supplements thereto, subject to the following provision:
Implemented AMENDMENT NO. 267
- c.
A break of at least eight hours should be allowed between work period, including shift turnover time.
- d.
In a, b, and c above, the time required to'complete shift turnover is to be countedas breaktime and is not to be counted as: work time.
- e.
Except during extended shutdown periods, the use of overtime.
should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Department Managers; or higher levels of management, in' accordance with established procedures and with documentation of the basis for granting the deviation.
- j.
The Senior Manager - Operations or an Operations Manager, and the Shift Manager require Senior Reactor Operators licenses.. The licensed Nuclear Plant Operators require a Reactor Operators license.
6.2.2.3 Individuals who train the operating staff and those who carry out the health physics.
and quality assurance function shall have sufficient Organizational freedom to be independent of operational pressures, however, they may report to the appropriate.
manager on site.
6.3 Facility Staff Qualifications 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications, with the following exceptions: 1.) the education and experience eligibility requirements for operator license applicants (described in Exelon letter RS-07-078, dated July 19, 2007), and changes thereto, shall be approved by the NRC and described in an applicable station training procedure, and 2) technicians and maintenance personnel who do not meet ANSI/ANS 3.1 of 1978, Section 4.5, are permitted to perform work for which qualification has been demonstrated.
6.3.2 The management position responsible for radiological controls shall meet.or exceed the.
qualifications, of Regulatory Guide 1.8 (Rev.l-R, 9/75). Each-other member of the radiation protection organization for which there is a comparable position described in ANSI N1 8.1-1971 shall meet or exceed the minimum qualifications specified therein, or in the case of radiation protection technicians, they shall have at least one year's continuous experience in applied radiation protection work in a nuclear facility dealing with radiological problems similar to thoseencountered in nuclear power stations and shall have beencertified by the management position responsible for radiological controls as qualified to perform assigned functions. This certification must be based on an NRC approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by responsible supervision that the Individual has demonstrated his ability to perform each specified procedure and assigned function with an understanding of its basis and purpose.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent ina scientific or engineering discipline with specific training in plant design, response and analysis of the plant for transients and accide6ts.
OYSTER CREEK 6-2a Amendment No.: 131,203,220,226ý232, 267
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 152 TO FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 152 TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 156 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 156 TO FACILITY OPERATING LICENSE NO. NPF-66, AMENDMENT NO. 180 TO FACILITY OPERATING LICENSE NO. NPF-62, AMENDMENT NO. 228 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19, AMENDMENT NO. 220 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25, AMENDMENT NO. 189 TO FACILITY OPERATING LICENSE NO. NPF-1 1, AMENDMENT NO. 176 TO FACILITY OPERATING LICENSE NO. NPF-18, AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-16, AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-44, AMENDMENT NO. 271 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-56, AMENDMENT NO. 240 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29, AMENDMENT NO. 235 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30, AMENDMENT NO. 265 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-50 EXELON GENERATION COMPANY, LLC, AMERGEN ENERGY COMPANY, LLC, BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION. UNITS 2 AND 3
(5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the.facility.
C.
This renewed license shall be deemed.to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50,54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 271
, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.'
(3)
Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans2, submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program,.Revision?3." -The-set
-contains Safe--raid 7f r-mtin protected under 10 CFR 73.21.
(4)
Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection, program as described in the Updated Final Safety Analysis Report for the facility, and as approved in
'Licensed power level was revised by Amendment-No-250, dated-November 22, 2002, and wvill implemented following the 14'h refueling outage currently scheduled for Fall 2003.
2The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-56 Revised by letter dated October 28, 2004 Revised. by letter dated November 5, 2004 Revised by letter dated May 29, 2007 Amendment No. 271 Page 3