ML090410333
| ML090410333 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/30/2009 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Jensen J Indiana & Michigan Electric Co |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| TAC MD9999, TAC ME0001 | |
| Download: ML090410333 (15) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 30, 2009 Mr. Joseph N. Jensen Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS RE: REQUEST TO REVISE ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUBMITTAL DATE (TAC NOS. MD9999 AND ME0001)
Dear Mr. Jensen:
The Commission has issued the enclosed Amendment Nos. 308 and 290 to Facility Operating License Nos. DPR-58 and DPR-74, respectively, for the Donald C. Cook Nuclear Plant. The amendment consists of changes to the Technical Specifications in response to your application dated October 21, 2008.
The amendment revises the submittal date for the Annual Radioactive Effluent Release Report.
Specifically, the required submittal date is revised from "within 90 days after January 1 of each year," to "prior to May 1 of each year."
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Terr A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Amendment No. 308 to DPR-58
- 2. Amendment No. 290 to DPR-74
- 3. Safety Evaluation cc: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 308 License No. DPR-58
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee), dated October 21,2008, 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
- 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. DPR-58 is hereby amended to read as follows.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 308, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR.TH~. N~EG.ULATORY COMMISSION
~tv1~Ic.~
'cJsi,. James, Chief ~
Plant Licensing Branc~II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: March 30, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 308 RENEWED FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following page of Renewed Facility Operating License No. DPR-58 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change.
REMOVE INSERT - 3 Replace the following page of Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE INSERT 5.6-2 5.6-2
- 3 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 material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
This renewed operating 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, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3304 megawatts thermal in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix S, as revised through Amendment No. 308 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Less than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.
(4) Indiana Michigan Power Company shall implement and maintain, in effect, all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 1985, Renewed License No. DPR-58 Amendment No. JOO, JQ.7, 308
5.6 Reporting Requirements 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.
5.6.3 Radioactive Effluent Release Report
NOTE-------------------------------------------------
A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station.
The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.
5.6.4 DELETED 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. SL 2.1.1, "Reactor Core Safety Limits";
- 2. LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";
- 3. LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";
- 4. LCO 3.1.5, "Shutdown Bank Insertion Limits";
Cook Nuclear Plant Unit 1 5.6-2 Amendment No. ~, ~, 308
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, 290 License No. DPR-74 1,
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee), dated October 21, 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
- 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. DPR-58 is hereby amended to read as follows.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 290, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
\\-i~.;tV)~-Yv4r James~.c-Plant Licensing Branch 111-1.
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: March 30, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 290 RENEWED FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the fol/owing page of Renewed Facility Operating License No. DPR-74 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change.
REMOVE INSERT - 3 Replace the following page of Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
REMOVE INSERT 5.6-2 5.6-2
- 3 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 material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 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 following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3468 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to the renewed operating license.
The preoperational tests, startup tests and other items identified in Attachment 1 to this renewed operating license shall be completed. Attachment 1 is an integral part of this renewed operating license.
(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 290 are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Additional Conditions (a) Deleted by Amendment No. 76 (b) Deleted by Amendment No.2 (c) Leak Testing of Emergency Core Cooling System Valves Indiana Michigan Power Company shall prior to completion of the first inservice testing interval leak test each of the two valves in series in the Renewed License No. DPR-74 dment No. ~ 290
5.6 Reporting Requirements 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.
5.6.3 Radioactive Effluent Release Report
NOTE-------------------------------------------------
A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station.
The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.
5.6.4 DELETED 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a.
Core operating limits shall be established prior to each reload cycle. or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the followinq:
- 1. SL 2.1.1, "Reactor Core Safety Limits";
- 2. LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";
- 3. LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";
- 4. LCO 3.1.5, "Shutdown Bank Insertion Limits";
Cook Nuclear Plant Unit 2 5.6-2 Amendment No. -299, 2+4,290
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 308 AND 290 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-58 and DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 and 50-316
1.0 INTRODUCTION
By application dated October 21, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082970187), Indiana Michigan Power Company (I&M, the licensee) requested changes to the Technical Specifications (TS) for the Donald C. Cook Nuclear Plant, Units 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination was published in the Federal Register on December 16, 2008 (73 FR 76412).
The proposed amendment would revise the submittal date for the Annual Radioactive Effluent Release Report. Specifically, the required submittal date is revised from "within 90 days of January 1 of each year" (i.e., prior to Apri/1), to "prior to May 1 of each year."
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.36a(a)(2) states the following:
Each holder of an operating licensee, and each holder of a combined license after the Commission has made the finding under § 52.103(g) of this chapter, shall submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months, including any other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from effluent releases. The report must be submitted as specified in § 50.4, and the time between submission of the reports must be no longer than 12 months. If quantities of radioactive materials released during the reporting period are significantly above design objectives, the report must cover this specifically. On the basis of these reports and any additional information the Commission may obtain from the licensee or others, the Commission may require the licensee to take action as the Commission deems appropriate.
- 2
3.0 TECHNICAL EVALUATION
3.1 Description of Proposed Change The proposed change would revise TS 5.6.3, "Radioactive Effluent Release Report," from the following:
The Radioactive Effluent Release Report covering the operations of the unit in the previous year shall be submitted within 90 days of January 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM [Offsite Dose Calculation Manual] and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix 1,Section IV.B.1.
to the following (change is bold and italicized for emphasis only):
The Radioactive Effluent Release Report covering the operations of the unit in the previous year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluent and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix 1,Section IV.B.1.
3.2 Evaluation of Proposed Changes The proposed wording for TS 5.6.3 would continue to require the same content as the existing wording such that the material provided is consistent with the ODCM, the Process Control Program, and all applicable regulations. The NRC staff finds that the time-frame proposed by the licensee would continue to keep the Commission informed, consistent with the intent of 10 CFR 50.36a(a)(2), while allowing the licensee sufficient time to prepare the report. Given that the information to be submitted will remain the same and the revised reporting date is appropriate, the proposed TS 5.6.3 will continue to meet the requirements of 10 CFR 50.36a(a)(2). The NRC staff, therefore, finds the proposed change to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan 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)(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.
- 3
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: Terry A. Beltz Date: March 30, 2009
March 30, 2009 Mr. Joseph N. Jensen Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REQUEST TO REVISE ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUBMITTAL DATE (TAC NOS. MD9999 AND ME0001)
Dear Mr. Jensen:
The Commission has issued the enclosed Amendment Nos. 308 and 290 to Facility Operating License Nos. DPR-58 and DPR-74, respectively, for the Donald C. Cook Nuclear Plant. The amendment consists of changes to the Technical Specifications in response to your application dated October 21, 2008.
The amendment revises the submittal date for the Annual Radioactive Effluent Release Report.
Specifically, the required submittal date is revised from "within 90 days after January 1 of each year," to "prior to May 1 of each year."
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRAJ Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-:-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Amendment No. 308 to DPR-58
- 2. Amendment No. 290 to DPR-74
- 3. Safety Evaluation cc: Distribution via ListServ DISTRIBUTION:
PUBLIC RidsOgcRp Resource RidsNrrDirsl hpb(RPedersen)
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ADAMS Accession Number* ML090410333 OFFICE LPL3-1/PM LPL3-1/LA LPL3-1/PM DIRS/IHPB DIRSIITSB OGC LPL3-1/BC NAME TBeitz THarris PTam RPedersen ALewin DRoth LJames DATE 02/17/09 02/11/09 03/10/09 02/24/09 02/18/09 03/06/09 03/30/09 OFFICIAL RECORD COpy