ML051150380
| ML051150380 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/15/2005 |
| From: | Nazar M Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:5901-03, TAC MC2629, TAC MC2630 | |
| Download: ML051150380 (6) | |
Text
INDIANA MICHIGAN POWER' A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, MI 49106 AEPcom April 15,2005 AEP:NRC:5901-03 10 CFR 50.90 Docket Nos.
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant, Units I and 2 COPY OF PROPOSED FACILITY OPERATING LICENSES, IMPROVED TECHNICAL SPECIFICATIONS, AND IMPROVED TECHNICAL SPECIFICATIONS BASES PAGES (TAC NOS. MC2629 AND MC2630)
References:
- 1. Letter from M. K. Nazar, Indiana Michigan Power Company, to Nuclear Regulatory Commission Document Control Desk-, 'Donald C. Cook Nuclear Plant Unit 1 and Unit 2, License Amendment Request - Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS)," AEP:NRC:4901, dated April 6, 2004.
- 2. Letter from J. N. Jensen, Indiana Michigan Power Company, to Nuclear Regulatory Commission Document Control Desk, 'Donald C. Cook Nuclear Plant Units I and 2, Supplement to License Amendment Request - Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS),
(TAC Nos. MC2629 and MC2630)," AEP:NRC:5901, dated April 15, 2005.
Dear Sir or Madam:
By References 1 and 2, Indiana Michigan Power Company (I&M) submitted an original and supplemental application to amend Appendix A, Technical Specifications, of Donald C. Cook Nuclear Plant (CNP) Unit 1 and Unit 2 Facility Operating Licenses DPR-58 and DPR-74, respectively, revising the current Technical Specifications (CTS) to the Improved Technical Specifications (ITS) consistent with Improved Standard Technical Specifications as described in NUREG-1431, "Standard Technical Specifications - Westinghouse Plants," Revision 2, and certain generic changes to the NUREG.
U. S. Nuclear Regulatory Commission AEP:NRC:5901-03 Page 2 The purpose of this letter is to provide a copy of the CNP Unit 1 and Unit 2 Facility Operating Licenses DPR-58 and DPR-74, respectively (Attachments Al and A2), showing changes to delete and add specific License Conditions, and to provide a complete copy of the CNP Unit 1 and Unit 2 ITS (Attachments BI and B2) and Revision 0 of the CNP Unit I and Unit 2 ITS Bases (Attachments Cl and C2) for issuance with the associated License Amendments as complete replacements for the existing Facility Operating Licenses, CTS, and CTS Bases. These documents are based upon the original and supplemental application in References 1 and 2, and incorporate all original requests and changes required as a result of the U. S. Nuclear Regulatory Commission (NRC) review of the associated original application. As of the date of this letter, no outstanding open items are anticipated to require any change to the documents provided.
The proposed CNP Unit 1 and Unit 2 Facility Operating Licenses (Attachments Al and A2) contain the following changes from the current Facility Operating Licenses as previously described in References 1 and 2:
- A new Unit 1 License Condition 2.C.(13) and Unit 2 License Condition 2.C.(3)(aa) have been added to address the schedule for relocating certain CTS requirements to licensee-controlled documents, as approved by the NRC, as follows:
"Relocation of Certain Technical Specification Requirements License Amendment No. XXX authorizes the relocation of certain current Technical Specification requirements and operating license conditions to other licensee-controlled documents.
Implementation of this amendment shall include the relocation of these requirements to the other documents, as described in (1) Section 5.0 of the NRC staffs Safety Evaluation, and (2) Table LA of Removed Details and Table R of Relocated Specifications attached to the NRC staffs Safety Evaluation, which is enclosed with this amendment.
- A new Unit 1 License Condition 2.C.(14) and Unit 2 License Condition 2.C.(3)(ab) have been added to address the schedule for implementing new and revised Surveillance Requirements, as approved by the NRC, as follows:
"Schedule for New and Revised Surveillance Requirements (SRs)
The schedule for performing the new or revised SRs in License Amendment No. XXX shall be as follows:
For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.
U. S. Nuclear Regulatory Commission AEP:NRC:5901-03 Page 3 For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment, except as noted below for SRs that have modified acceptance criteria as a result of revised Allowable Values.
For SRs that have modified acceptance criteria as a result of revised Allowable Values, the current Allowable Values and current CHANNEL CALIBRATION frequencies are required to be met until the trip setpoints are changed to reflect the new Allowable Values and CHANNEL CALIBRATION frequencies. The trip setpoints are required to be changed no later than the unit startup after the first planned outage of sufficient duration to change all of the trip setpoints for the unit following implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment, except as noted above for SRs that have modified acceptance criteria as a result of revised Allowable Values.
- Unit 1 License Condition 2.C.(7) and Unit 2 License Condition 2.C.(3)(v), Secondary Water Chemistry Monitoring Program, have been deleted since the requirements of this License Condition have been included in the Unit 1 and Unit 2 ITS 5.5.8, "Secondary Water Chemistry Program."
- Unit 1 License Condition 2.H and Unit 2 License Condition 2.G, System Integrity, have been deleted since the requirements of this License Condition have been included in the Unit 1 and Unit 2 ITS 5.5.2, "Leakage Monitoring Program."
- Unit 1 License Condition 2.1 and Unit 2 License Condition 2.H, Iodine Monitoring, have been deleted.
This License Condition is a Specification (Specification 6.8.4.b) in NUREG-0452, Revision 4, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors,"
which was the previous Standard Technical Specifications for Westinghouse plants prior to NUREG-1431.
This requirement is not included in NUREG-1431, Revision 2, and the requirement may be relocated to a licensee-controlled document. Therefore, the requirements of this License Condition are being relocated to the Technical Requirements Manual.
U. S. Nuclear Regulatory Comm-ission AEP:NRC:590 1-03 Page 4, "Affirmation," provides an oath and affirmation affidavit regarding the statements made and matters set forth in this submittal.
Tllis letter contains no commitments. If you have any questions or require additional information, please contact Mr. Richard J. Grumbir, Project Manager, ITS, at (269) 697-5141.
Sincerely, M. K. Nazar and Chief Nuclear Officer GW/rdw
U. S. Nuclear Regulatory Commnission Page 5 AEP:NRC:5901 -03
Enclosure:
- 1. Affirmation Attachments:
Al.
A2.
BI.
B2.
Cl.
C2.
Unit 1 Facility Operating License with Changes Shown Unit 2 Facility Operating License with Changes Shown Unit 1 Improved Technical Specifications Unit 2 Improved Technical Specifications Revision 0 of the Unit 1 Improved Technical Specifications Bases Revision 0 of the Unit 2 Improved Technical Specifications Bases NOTE A single copy of this cover letter, enclosure, and attachments is being submitted to the NRC Document Control Desk. In addition, a single CD-ROM suitable for use for entry of this complete submittal into the NRC Agencywide Documents Access and Management System (ADAMS) is being provided.
The single copy of the submittal and CD-ROM provided meet the applicable requirements of Regulatory Issue Summary (RIS) 2001-05, "Guidance on Submitting Documents to the NRC by Electronic Information Exchange or on CD-ROM."
Additional CD-ROMs are provided for the persons designated below.
c:
T. H. Boyce, NRC Washington, DC, w/o attachments, with CD-ROM J. L. Caldwell, NRC Region III, w/o attachments, with CD-ROM K. D. Curry, Ft. Wayne AEP, w/o enclosure/attachments J. N. Donohew, NRC Washington, DC, w/o attachments, with CD-ROM P. C. Hearn, NRC Washington, DC, w/o attachments, with CD-ROM J. T. King, MPSC, w/o enclosure/attachments C. F. Lyon - NRC Washington DC, w/o attachments, with CD-ROM MDEQ - WHMD/HWRPS, w/o enclosure/attachments NRC Resident Inspector, w/o attachments, with CD-ROM to AEP:NRC:5901-03 AFFIRMATION I, Mano K. Nazar, being duly sworn, state that I am Senior Vice President and Chief Nuclear Officer of American Electric Power Service Corporation and Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.
American Electric Power Service Corporation M. K. Nazar Senior Vice Preside and Chief Nuclear Officer SWORN TO AND SUBSCRIBED BEFORE ME THIS ';JDAY OF
, 2005
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