Letter Sequence Request |
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MONTHYEARML0401306822003-12-15015 December 2003
Application for Technical Specification Change Regarding Mode Change Limitations Additional Information
Project stage: Request
ML0402907492004-01-14014 January 2004
Response to NRC RAIs Pertaining to the Review of the License Applications - Scoping and Screening Methodology and Results
Project stage: Response to RAI
ML0412704842004-04-23023 April 2004
Supplemental Information for Plant License Renewal Application - Aging Management Program Audit
Project stage: Supplement
ML0413903602004-05-0707 May 2004
Units I and 2, License Renewal Application - Response to Requests for Additional Information on Scoping and Screening Results
Project stage: Response to RAI
ML0413305512004-05-10010 May 2004
03/25-26/2004 Summary of Telephone Conferences with Indiana Michigan Power Company (I&M Representatives Regarding Draft Request for Additional Information on DC Cook Nuclear Plant, Units 1 & 2, LRA
Project stage: Draft RAI
ML0415500382004-05-20020 May 2004
License Renewal Application - Response to Requests for Additional Information on Scoping & Screening Results
Project stage: Response to RAI
ML0415304722004-06-0101 June 2004
Summary of Telephone Conference Between U.S. Nuclear Regulatory Commission (NRC) and Indiana Michigan Power Company (I&M) Representatives Concerning Draft Requests for Additional Information on Donald C. Cook, Nuclear Plants
Project stage: Draft RAI
ML0416802552004-06-0808 June 2004
License Renewal Application - Response to Requests for Additional Information on Electrical and Auxiliary Systems
Project stage: Response to RAI
ML0416705232004-06-0808 June 2004
License Renewal Application - Response to Requests for Additional Information on Structures and Component Supports
Project stage: Response to RAI
ML0418104272004-06-29029 June 2004
Summary of Telephone Conference Held on May 12, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) and Indiana Michigan Power Company Representatives Concerning Draft Requests for Additional Information on DC Cook, Units 1 & 2, LRA
Project stage: Draft RAI
ML0421102752004-07-27027 July 2004
& 05/21/2004 Summary of Telephone Conference Calls with Indiana Michigan Power Co Regarding Responses to Request for Additional Information on D. C. Cook Units 1 & 2, LRA
Project stage: RAI
ML0421204802004-07-30030 July 2004
Summary of Telephone Conference Between the NRC and Indiana Michigan Power Company (I & M) Representatives Concerning Requests for Additional Information on Donald C. Cook Nuclear Plant, Units 1 & 2, License Renewal Application
Project stage: RAI
ML0425100272004-08-0303 August 2004
Summary of Meeting Between the NRC, the NEI, and the Three Pilot Program LRA Held on June 3, 2004, to Discuss Generic License Renewal Topics and Lessons Learned on the Pilot Program for the New LRA Review Process
Project stage: Meeting
ML0424704022004-08-11011 August 2004
Units I and 2, License Renewal Application -- Supplemental Responses to Requests for Additional Information
Project stage: Supplement
ML0424506002004-08-11011 August 2004
License Renewal -Application - Response to Requests for Additional Information on Reactor Vessel, Internals, and Reactor Coolant System
Project stage: Response to RAI
ML0424704102004-08-11011 August 2004
Units I and 2, License - Renewal Application - Response to Requests for Additional Information on Aging Management Programs, (TAC Nos. Mc 1202 and Mc 1203)
Project stage: Response to RAI
ML0423904692004-08-19019 August 2004
License Renewal Application - Response to Requests for Additional Information on Aging Management Programs (TAC Nos. Mc 1202 and Mc 1203)
Project stage: Response to RAI
ML0423703752004-08-23023 August 2004
Summary of Telephone Conference Held on July 29, 2004 Between the U.S. Nuclear Regulatory Commission (NRC) and Indiana Michigan Power Company (I&M) Representatives Concerning Requests for Additional Information on Donald C. Cook Nuclear Pla
Project stage: RAI
ML0424304652004-08-30030 August 2004
Summary of Telephone Conference Between U.S. Nuclear Regulatory Commission & Indiana Michigan Power Company Representatives Concerning Requests for Additional Information on Donald C. Cook Nuclear Plant, Units 1 & 2, License Renewal
Project stage: RAI
ML0424406712004-08-31031 August 2004
Summary of Telephone Conference Held on August 10, 2004 Between the U.S. Nuclear Regulatory Commission (NRC) and Indiana Michigan Power Company (I&M) Representatives Concerning Requests for Additional Information on Donald C. Cook Nuclear P
Project stage: RAI
ML0425305512004-09-0202 September 2004
License Renewal Application - Response to Requests for Additional Information
Project stage: Response to RAI
ML0425100172004-09-0202 September 2004
Summary of Meeting with NEI and the Three Pilot Program LRA to Discuss Generic License Renewal Topics and Lessons Learned on the Pilot Program for the New LRA Review Process
Project stage: Meeting
ML0427404392004-09-21021 September 2004
License Renewal Application - Supplemental Responses to Requests for Additional Information (TAC Nos. Mc 1202 and Mc 1203)
Project stage: Supplement
ML0426005992004-09-22022 September 2004
Audit Trip Report Regarding the Indiana Michigan Power Company License Renewal Application for the Donald C. Cook Nuclear Plant, Units 1 and 2, Dated October 21, 2003
Project stage: Other
ML0429600282004-10-18018 October 2004
License Renewal Application - Response to Requests for Additional Information
Project stage: Response to RAI
ML0430904672004-10-28028 October 2004
License Renewal Application - Annual Update Information
Project stage: Other
ML0433503982004-11-18018 November 2004
License Renewal Application - Clarification to Request for Additional Information Responses
Project stage: Supplement
ML0503303732005-01-21021 January 2005
Response to Open and Confirmatory Items in the Draft Safety Evaluation Report Related to the License Renewal
Project stage: Draft Other
ML0506903282005-03-0202 March 2005
Applicants Comments on the Safety Evaluation Report with Open Items Related to the License Renewal
Project stage: Other
ML0523404812005-08-30030 August 2005
Renewed Facility Operating License No. DPR-74, Donald C. Cook Nuclear Plant, Unit No. 2 - Docket No. 50-316
Project stage: Other
ML0523404112005-08-30030 August 2005
Mano K. Nazar Ltr Re. Donald C. Cook Nuclear Plant, Units 1 and 2 - Issuance of Renewed Facility Operating Licenses Nos. DPR-58 and DPR-74
Project stage: Approval
ML0523404472005-08-30030 August 2005
Renewed Facility Operating License No. DPR-58, Donald C. Cook Nuclear Plant, Unit No. 1 - Docket No. 50-315
Project stage: Other
2004-07-27
[Table View] |
Similar Documents at Cook |
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Text
Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1395 INDIANA MICHIGAN POWER December 15, 2003 AEP:NRC:3304-01 10 CFR 50.90 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant, Units 1 and 2 APPLICATION FOR TECHNICAL SPECIFICATION CHANGE REGARDING MODE CHANGE LIMITATIONS ADDITIONAL INFORMATION
Reference:
"Donald C. Cook Nuclear Plant Units I and 2, Application for Technical Specification Change Regarding Mode Change Limitations, and Adoption of a Technical Specifications Bases Control Program and Standard Technical Specification Surveillance Requirement 3.0.1 and Associated Bases, Using The Consolidated Line Item Improvement Process,"
letter AEP:NRC:3304, dated August 27, 2003.
In the referenced document, Indiana Michigan Power Company (I&M),
requested a license amendment utilizing the Consolidated Line Item Improvement Process (CLIIP). The license amendment adopted the industry Technical Specification Task Force (TSTF) standard technical specification (TS) change TSTF-359, Revision 9. TSTF-359, Revision 9 allows mode changes with inoperable equipment provided one of three conditions specified in the TS is met. Although TSTF-359, Revision 9 was written for the Improved Technical Specifications (ITS), the CLIIP can be used by all licensees.
In a telephone conversation with Nuclear Regulatory Commission (NRC) personnel on November 24, 2003, the NRC personnel noted two differences between the Donald C. Cook Nuclear Plant (CNP) TS and the ITS in the areas of low temperature overprotection (LTOP) and auxiliary feedwater (AFW). The NRC requested that CNP provide additional information addressing the effect of these differences on the adoption of TSTF-359, Revision 9 for CNP.
proo()1
U. S. Nuclear Regulatory Commission AEP:NRC:3304-01 Page 2 The ITS requires that LTOP be operable in Mode 4.
The ITS changes in TSTF-359, Revision9 prohibit entering Mode 4 from Mode 5 with LTOP inoperable. CNP's TS require LTOP to be operable in Mode 5 with any Reactor Coolant System (RCS) cold leg temperature less than or equal to 152 degrees Fahrenheit (0F) and in Mode 6.
The CNP TS do not require LTOP to be operable in Mode 4 and entry into Mode 4 with LTOP inoperable is not prohibited by the current TS and will not be prohibited by the TS after adoption of TSTF-359.
CNP is in the process of converting to the ITS with submittal expected in the Spring of 2004. As part of the ITS conversion, the applicability of the LTOP specification is being revised to include Mode 4 with any RCS cold leg temperature < 2660F (Unit 1) or < 2990F (Unit 2).
In the interim, plant procedures prohibit entering Mode 4 with LTOP inoperable.
The current procedural controls and the future adoption of the ITS for CNP provide an appropriate level of control over Mode 4 entry with LTOP inoperable.
The ITS requires that one motor driven AFW pump be operable in Mode 4.
CNP uses AFW for normal startup and, therefore, the ITS changes in TSTF-359, Revision 9 prohibit entering Mode 4 from Mode 5 without an operable motor driven AFW pump. The CNP TS require AFW to be operable in Modes 1, 2, and 3. The CNP TS do not require AFW to be operable in Mode 4 and entry into Mode 4 with AFW inoperable is not prohibited by the current TS and will not be prohibited by the TS after adoption of TSTF-359.
As part of the ITS conversion, the applicability of the AFW specification is being revised to Modes 1, 2, and 3 and Mode 4 when a steam generator is being used for heat removal.
In the ITS, the Limiting Condition for Operation is modified by a Note stating that only one AFW train, which includes a motor driven AFW pump, is required to be operable in Mode 4. This will prohibit entry into Mode 4 from Mode 5 without an operable motor driven AFW pump.
In the interim, plant procedures prohibit entering Mode 4 without an operable motor driven AFW pump.
The current procedural controls and the future adoption of the ITS for CNP provide an appropriate level of control over Mode 4 entry with AFW inoperable.
U. S. Nuclear Regulatory Commission Page 3 AEP:NRC:3304-0 1 This letter contains no new commitments.
Should you have any questions, please contact Mr. Brian D. Mann, Acting Manager of Regulatory Affairs, at (269) 697-5806.
Sincerely, c:
J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP J. T. King, MPSC MDEQ - WHMD/HWRPS NRC Resident Inspector J. F. Stang, Jr., NRC Washington, DC
JANl-08-2004 14:34 EN 3IET AEPNG 3 WEST P. 02/02 U. S. Nuclear Regulatory Commission AEP:NRC:3304-01 Page 4 bc:
D. C. Baker G. E. Carlson M. J. Finissi D. W. Jenkins J. N. Jensen B. D. Mann D. A. Moul M. K. Nazar J. E. Newmiller D. J. Poupard M. K. Scarpello T. K. Woods J. A. Zwolinski TOTAL P.02
U. S. Nuclear Regulatory Commission Page 5 AEP:NRC:3304-01 AFFIRMATION I, Joseph N. Jensen, being duly sworn, state that I am Site 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.
Indiana Michigan Power Company Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS /<
DAY OF Sea r,
2003
-/ /-
Notark Public JULIE E. NEWMILLER Notary Public, Berrien County, Ml My Commission Expires Aug 22, 2004 My Commission Expires 9 -S OM
