ML050750069
| ML050750069 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/04/2005 |
| From: | Fadel D Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:5054-04, GL-04-002 | |
| Download: ML050750069 (6) | |
Text
Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman, MI 49106 VPWWRI AEPcom A unit of American Electric Power March 4, 2005 AEP:NRC:5054-04 10 CFR 50.54(f)
Docket Nos:
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852 Donald C. Cook Nuclear Plant Units 1 and 2 90 DAY RESPONSE TO NUCLEAR REGULATORY COMMISSION GENERIC LETTER 2004-02: POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS
Reference:
Nuclear Regulatory Commission Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," dated September 13, 2004.
In the referenced generic letter, the U. S. Nuclear Regulatory Commission (NRC) requested that addressees perform a mechanistic evaluation, using an NRC-approved methodology, of the potential for the adverse effects of post-accident debris blockage and operation with debris-laden fluids to impede or prevent the recirculation functions of the emergency core cooling systems and containment spray systems. The NRC also requested that, within 90 days of the date of the NRC safety evaluation report providing the guidance for performing the evaluation, addressees provide information regarding their planned actions and schedule to complete the evaluation. The NRC safety evaluation report providing the guidance for performing the evaluation was issued on December 6, 2004. to this letter provides Indiana Michigan Power Company's 90 day response to Generic Letter 2004-02 for the Donald C. Cook Nuclear Power Plant. Attachment 2 identifies the regulatory commitments made in this letter.
- 11IY
U. S. Nuclear Regulatory Commission AEP:NRC:5054-04 Page 2 Should you have any questions, please contact Mr. John A. Zwolinski, Safety Assurance Director, at (269) 466-2428.
Sincerely, Engineering Vice President JW/rdw Attachments:
- 1.
90 Day Response to Nuclear Regulatory Commission Generic Letter 2004-02
- 2.
J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o attachments J. T. King, MPSC C. F. Lyon, NRC Washington, DC MDEQ - WHMD/HWRPS NRC Resident Inspector
U. S. Nuclear Regulatory Commission AEP:NRC:5054-04 Page 3 AFFIRMATION I, Daniel P. Fadel, being duly sworn, state that I am Engineering 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 Daniel P.
Engineering Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ___
DAY OF A c b
, 2005 MyComisonxr lic My Commiission Expires Lk ltGod
ATTACHMENT 1 TO AEP:NRC:5054-04 90 DAY RESPONSE TO NUCLEAR REGULATORY COMMISSION GENERIC LETiTER 2004-02 References for this attachment are identified on Page 2.
In the Requested Action section of Generic Letter 2004-02 (Reference 1), the U. S. Nuclear Regulatory Commission (NRC) requested that addressees perform a mechanistic evaluation, using an NRC-approved methodology, of the potential for the adverse effects of post-accident debris blockage and operation with debris-laden fluids to impede or prevent the recirculation functions of the emergency core cooling systems (ECCS) and containment spray systems. In Requested Information Item 1 of the generic letter, the NRC requested that, within 90 days of the date of the NRC safety evaluation report providing the guidance for performing the evaluation, addressees provide information regarding their planned actions and schedule to complete the evaluation.
The NRC safety evaluation report (Reference 2) providing the guidance for performing the evaluation was issued on December 6, 2004.
This attachment provides Indiana Michigan Power Company's (I&M's) 90 day response to Requested Information Item 1 of Generic Letter 2004-02 for the Donald C. Cook Nuclear Power Plant (CNP).
Requested Information Item l(a)
A description of the methodology that is used or will be used to analyze the susceptibility of the ECCS and CSS recirculation functions for your reactor to the adverse effects identified in this generic letter of post-accident debris blockage and operation with debris-laden fluids identified in this generic letter. Provide the completion date of the analysis that will be performed.
Response
I&M has established a contract with Westinghouse Electric Company LLC (Westinghouse) to perform a CNP-specific evaluation of post-accident debris generation, and develop a computational fluid dynamics model of the containment to determine sump fluid velocity profiles, debris transport to the ECCS recirculation sump screens, head loss associated with debris accumulation, and the effect of the head loss on available net positive suction head. The effect of debris that passes through the screens on components in the ECCS flow path such as pumps, valves, and core components will also be evaluated.
The methodology used will conform to the intent of NEI 04-07 (Reference 3) and the associated NRC safety evaluation report (Reference 2). The methodology used will reflect specific licensing basis information and contractor specific proprietary information as appropriate. Exceptions to the guidance given in NEI 04-07, should they be taken, will be identified and their basis documented in correspondence submitted to the NRC no later than September 1, 2005. The final Westinghouse report and I&M acceptance reviews will be completed in time to support submittal of the response to Requested Information Item 2 of Generic Letter 2004-02 no later than September 1, 2005.
to AEP:NRC:5054-04 Page 2 Industry efforts are under way to evaluate chemical effects in containment during a loss of coolant accident and the downstream effects of debris laden fluid. I&M will utilize information from these efforts in the requested evaluation to the extent that the information becomes available. However, if information from these efforts is not available, CNP will address the associated issues using appropriate assumptions and methodologies. The response to Requested Information Item 2 of Generic Letter 2004-02 will include descriptions of how these issues have been addressed in the requested evaluation.
Requested Information Item 1(b)
A statement of whether you plan to perform a containment walkdown surveillance in support of the analysis of the susceptibility of the ECCS and CSS recirculation functions to the adverse effects of debris blockage identified in this generic letter. Provide justification if no containment walkdown surveillance will be performed. If a containment walkdown surveillance will be performed, state the planned methodology to be used and the planned completion date.
Response
Containment walkdowns in support of the above described evaluation will be performed during the next CNP Unit 1 and Unit 2 refueling outages. The next Unit 1 refueling outage is scheduled for Spring 2005, and the next Unit 2 refueling outage is scheduled for Spring 2006.
The walkdowns will be perfonned using guidance provided in NEI 02-01 (Reference 4), NEI 04-07 (Reference 3), and the associated NRC safety evaluation report (Reference 2).
References for this Attachment
- 1. NRC Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," dated September 13, 2004.
- 2. Letter from S. C. Black, NRC, to A. R. Pietrangelo, Nuclear Energy Institute, "Pressurized Water Reactor Containment Sump Evaluation Methodology," dated December 6, 2004,
[ML043280631].
- 3. Nuclear Energy Institute report NEI 04-07, "Pressurized Water Reactor Sump Performance Methodology," dated December 2004.
- 4. Nuclear Energy Institute report NEI 02-01, "Condition Assessment Guidelines: Debris Sources Inside PWR Containments," dated September 2002.
ATTACHMENT 2 TO AEP:NRC:5054-04 REGULATORY COMMITMENTS The following table identifies those actions committed to by Indiana Michigan Power Company (I&M) in this document.
Any other actions discussed in this submittal represent intended or planned actions by I&M.
They are described to the Nuclear Regulatory Commission (NRC) for the NRC's information and are not regulatory commitments.
Commitment Date I&M has established a contract with Westinghouse Electric Company LLC (Westinghouse) to provide a Donald C. Cook Nuclear Plant (CNP) plant-specific evaluation of debris generation, and develop a
computational fluid dynamics model of the containment to determine sump fluid velocity profiles, debris transport to the emergency core cooling system (ECCS) recirculation sump screens, head loss associated with debris accumulation, and the effect of the head loss on available net positive suction head. The effect of debris that passes through the screens on components in the ECCS flow path such as pumps, valves, and core components will also be evaluated.
The final Westinghouse report and I&M acceptance reviews will be completed in time to support submittal of the response to Requested Information Item 2 of Generic Letter 2004-02 no later than September 1, 2005.
The methodology used to perform the evaluation requested by NRC Generic Letter 2004-02 will conform to the intent of NEI 04-07 and the associated NRC safety evaluation report.
The methodology used will reflect specific licensing basis information and contractor specific proprietary information as appropriate to the current state of knowledge. Exceptions to the guidance given in NEI 04-07, should they be taken, will be identified and their basis documented in correspondence submitted to the NRC.
No later than September 1, 2005 The response to Requested Information Item 2 of No later than Generic Letter 2004-02 will include descriptions of how September 1, 2005 chemical effects in containment during a loss of coolant accident and the downstream effects of debris laden fluid have been addressed in the requested evaluation.
Additional Unit 1 and Unit 2 containment walkdowns During the next CNP Unit 1 will be performed using guidance provided in NEI 04-07 and Unit 2 refueling outages.
and NEI 02-01.