ML023120449
| ML023120449 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/07/2002 |
| From: | Stang J NRC/NRR/DLPM/LPD3 |
| To: | Bakken A Indiana Michigan Power Co |
| References | |
| TAC MB5498 | |
| Download: ML023120449 (4) | |
Text
November 7, 2002 Mr. A. Christopher Bakken III, Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 1 - SECOND REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST, POWER UPRATE MEASUREMENT UNCERTAINTY RECAPTURE (TAC NO. MB5498)
By application dated June 28, 2002, Indiana Michigan Power Company (the licensee) submitted a license amendment request that would revise the Operating Licenses for the Donald C. Cook Nuclear Plant, Unit 1, and the technical specifications to allow the use of a more accurate flow measurement instrumentation and power calorimetric uncertainty value to allow the licensed core thermal power to be increased by 1.66 percent from 3250 megawatts thermal to 3304 megawatts thermal.
By letter dated October 2, 2002, the U.S. Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) to allow the NRC staff to make an independent assessment of the application. Specifically, question 25 requested the licensee to docket the calculation that establishes the thermal power measurement uncertainty. By letter dated October 17, 2002, the licensee docketed the calculations. The NRC staff has reviewed the calculation and found issues that were not adequately addressed. To enable the staff to complete the review of the proposed amendment, the licensee needs to provide additional information. Enclosed is the NRC staffs RAI.
The RAI was discussed with Mr. Brian McIntyre, et al., of your staff on October 31, 2002, during a telephone conference call. The enclosed RAI is similar in content to the RAI discussed with your staff during the conference call. A mutually agreeable target date of November 12, 2002, for your response was established.
If there is need to revise that target date, please contact me at (301) 415-1345.
Sincerely,
/RA/
John F. Stang, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
Request for Additional Information cc w/encl: See next page
ML OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME JStang THarris LRaghavan DATE 11/07/02 11/07/02 11/07/02
Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, MI 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, MI 49127 David W. Jenkins, Esquire Indiana Michigan Power Company One Cook Place Bridgman, MI 49106 Mayor, City of Bridgman P.O. Box 366 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 Drinking Water and Radiological Project Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr. Blvd.
P. O. Box 30630, CPH Mailroom Lansing, MI 48909-8130 Scot A. Greenlee Director, Nuclear Technical Services Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 Michael J. Finissi Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Joseph E. Pollock Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION SUBMITTAL AEP: NRC 2900-03 MEASUREMENT UNCERTAINTY RECAPTURE DATED OCTOBER 17, 2002 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK, UNIT 1 DOCKET NO. 50-315 The following two questions are generated from the NRC staff review of the measurement uncertainty calculation.
1.
The issue of common (ie non-independent) influences must be addressed. Some examples of common influences are listed below:
- a. common instrument environments,
- b. common Measurement and Testing Equipment related uncertainty, and c.
common source for feed water flow and temperature data (ref. the Caldon caveat in calculation Attachment 8 against using square root sum of the squares for flow and temperature).
2.
Figure 4.2 and Table 4.2 show the use of several parameters and calculations that influence the core thermal power calculation, but for which no uncertainty allowance is provided. Please justify that there is no uncertainty associated with these parameters and calculations, or account for the associated uncertainties. Note that there are two issues for each parameter or calculation: 1) establishing what uncertainty value is appropriate, and 2) accounting for the effect of each uncertainty upon the overall uncertainty in the core thermal power evaluation. The parameters in question are:
a.
net heat loss, b.
steam quality (both the value for main steam and the value for the blowdown flow from each steam generator, and c.
steam table data (both the uncertainties involved in the Plant Process Computer calculations that generate the steam table values and the uncertainties inherent in the steam tables themselves).