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=Text=
=Text=
{{#Wiki_filter:June 5, 2008 Mr. Michael W. Rencheck Senior Vice President and   Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106  
{{#Wiki_filter:June 5, 2008 Mr. Michael W. Rencheck Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106


==SUBJECT:==
==SUBJECT:==
D. C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1) - REQUEST FOR ADDITIONAL INFORMATION, REGARDING RE-ANALYSIS OF LARGE-BREAK LOSS-OF-COOLANT ACCIDENT (TAC NO. MD7556)  
D. C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1) - REQUEST FOR ADDITIONAL INFORMATION, REGARDING RE-ANALYSIS OF LARGE-BREAK LOSS-OF-COOLANT ACCIDENT (TAC NO. MD7556)


==Dear Mr. Rencheck:==
==Dear Mr. Rencheck:==


In a letter dated December 27, 2007, Indiana Michigan Power Company (I&M) requested an amendment to modify Technical Specification (TS) 3.4.1, "RCS [Reactor Coolant System] Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," and TS 5.6.5, "Core Operating Limits Report (COLR)," in support of a new analysis of a large-break loss-of-coolant accident (LBLOCA).
In a letter dated December 27, 2007, Indiana Michigan Power Company (I&M) requested an amendment to modify Technical Specification (TS) 3.4.1, RCS [Reactor Coolant System]
The Nuclear Regulatory Commission (NRC) staff reviewed the December 27, 2007, submittal and issued a draft Request for Additional Information (RAI) on April 10, 2008 (Accession No. ML081010615). On May 15, 2008, the NRC staff discussed the draft RAI with I&M staff, and participants agreed that the draft RAI can be formally issued. Accordingly, the finalized RAI is issued as enclosure to this letter.
Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits, and TS 5.6.5, Core Operating Limits Report (COLR), in support of a new analysis of a large-break loss-of-coolant accident (LBLOCA).
The Nuclear Regulatory Commission (NRC) staff reviewed the December 27, 2007, submittal and issued a draft Request for Additional Information (RAI) on April 10, 2008 (Accession No.
ML081010615). On May 15, 2008, the NRC staff discussed the draft RAI with I&M staff, and participants agreed that the draft RAI can be formally issued. Accordingly, the finalized RAI is issued as enclosure to this letter.
In accordance with the timeliness provision of 10 CFR 2.108, please respond within 30 days of receipt of this letter. Feel free to contact me if you need clarification of this RAI.
In accordance with the timeliness provision of 10 CFR 2.108, please respond within 30 days of receipt of this letter. Feel free to contact me if you need clarification of this RAI.
Sincerely, /RA/   Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315  
Sincerely,
                                              /RA/
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315


==Enclosure:==
==Enclosure:==
As stated cc: See next page
As stated cc: See next page


ML081570070 OFFICE LPL3-1\PM LPL3-1/LA SRSB SRSB/BC LPL3-1/BC NAME PTam   THarris FOrr GCranston JCushing for LJames DATE 6/3/08 6/3/08   6/5/08 6/5/08 6/5/08
ML081570070 OFFICE     LPL3-1\PM     LPL3-1/LA     SRSB         SRSB/BC       LPL3-1/BC NAME       PTam         THarris       FOrr         GCranston     JCushing for LJames DATE       6/3/08       6/3/08       6/5/08       6/5/08         6/5/08


REQUEST FOR ADDITIONAL INFORMATION D.C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1)
REQUEST FOR ADDITIONAL INFORMATION D.C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1)
RE-ANALYSIS OF LARGE-BREAK LOSS-OF-COOLANT ACCIDENT (LBLOCA)
RE-ANALYSIS OF LARGE-BREAK LOSS-OF-COOLANT ACCIDENT (LBLOCA)
(1) To show that the referenced generically approved ASTRUM LOCA analysis methodology applies specifically to DCCNP-1, please provide a statement that Indiana Michigan Power and its vendor (Westinghouse) have ongoing processes which assure that the ranges and values of the input parameters for DCCNP-1 LOCA analyses bound the ranges and values of the as-operated plant parameters.
(1) To show that the referenced generically approved ASTRUM LOCA analysis methodology applies specifically to DCCNP-1, please provide a statement that Indiana Michigan Power and its vendor (Westinghouse) have ongoing processes which assure that the ranges and values of the input parameters for DCCNP-1 LOCA analyses bound the ranges and values of the as-operated plant parameters.
(2) The discussion in the December 27, 2007, submittal did not address the effects of the mixed core on peak cladding temperature (PCT) and oxidation for the pre-resident fuel, but it does seem to address the PCT and oxidation for the new fuel. Please clarify if this is a whole core reload. In its Rulemaking Hearing dated December 28, 1983, the Nuclear Regulatory Commission stated, regarding the performance criteria of 10 CFR 50.46 (b): "In view of the lack of experience in this hypothetical situation, we think it prudent to apply our criteria to all of the core and not to exempt any part."
(2) The discussion in the December 27, 2007, submittal did not address the effects of the mixed core on peak cladding temperature (PCT) and oxidation for the pre-resident fuel, but it does seem to address the PCT and oxidation for the new fuel. Please clarify if this is a whole core reload. In its Rulemaking Hearing dated December 28, 1983, the Nuclear Regulatory Commission stated, regarding the performance criteria of 10 CFR 50.46 (b): "In view of the lack of experience in this hypothetical situation, we think it prudent to apply our criteria to all of the core and not to exempt any part."
Please address PCT and oxidation results for "pre-resident" fuel in the core, if any.
Please address PCT and oxidation results for "pre-resident" fuel in the core, if any.
[Note: In a letter to NEI dated November 8, 1999, G. M. Holahan, reiterated the NRC position that "total oxidation" encompasses accident and pre-accident oxidation. This position continues to apply. Therefore, in response to this question, please provide total oxidation for the "other" (pre-resident) fuel (if any), including pre-accident oxidation, plus LOCA cladding outside oxidation, plus cladding inside oxidation.]
[Note: In a letter to NEI dated November 8, 1999, G. M. Holahan, reiterated the NRC position that "total oxidation" encompasses accident and pre-accident oxidation. This position continues to apply. Therefore, in response to this question, please provide total oxidation for the "other" (pre-resident) fuel (if any), including pre-accident oxidation, plus LOCA cladding outside oxidation, plus cladding inside oxidation.]
(3) Please verify that the treatment of the vessel wall (radial noding, etc.) during reflood remains as historically approved in addressing the issue of downcomer boiling.
(3) Please verify that the treatment of the vessel wall (radial noding, etc.) during reflood remains as historically approved in addressing the issue of downcomer boiling.


Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
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 Inspector's Office 7700 Red Arrow Highway Stevensville, MI 49127 Kimberly Harshaw, 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  
Attorney General Department of Attorney General             Michigan Department of Environmental 525 West Ottawa Street                     Quality Lansing, MI 48913                           Waste and Hazardous Materials Div.
 
Radiological Protection Section Township Supervisor                         Radiological Assessment Unit Lake Township Hall                         Constitution Hall, Lower-Level North P.O. Box 818                               525 West Allegan Street Bridgman, MI 49106                         P. O. Box 30241 Lansing, MI 48909-7741 U.S. Nuclear Regulatory Commission Resident Inspector's Office                 Joel P. Gebbie, Plant Manager 7700 Red Arrow Highway                     Indiana Michigan Power Company Stevensville, MI 49127                     Nuclear Generation Group One Cook Place Kimberly Harshaw, Esquire                   Bridgman, MI 49106 Indiana Michigan Power Company One Cook Place                             Lawrence J. Weber, Site Vice President Bridgman, MI 49106                         Indiana Michigan Power Company Nuclear Generation Group Mayor, City of Bridgman                     One Cook Place P.O. Box 366                               Bridgman, MI 49106 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 James M. Petro, Jr.
James M. Petro, Jr. Regulatory Affairs Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
Regulatory Affairs Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106}}
 
Michigan Department of Environmental            Quality  Waste and Hazardous Materials Div. Radiological Protection Section Radiological Assessment Unit Constitution Hall, Lower-Level North 525 West Allegan Street P. O. Box 30241 Lansing, MI 48909-7741 Joel P. Gebbie, Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI  49106
 
Lawrence J. Weber, Site Vice President  Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI  49106}}

Revision as of 17:02, 14 November 2019

Request for Additional Information Regarding the Re-Analysis of Large-Break Loss-of-Coolant Accident
ML081570070
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 06/05/2008
From: Tam P
NRC/NRR/ADRO/DORL/LPLIII-1
To: Rencheck M
Indiana Michigan Power Co
References
TAC MD7556
Download: ML081570070 (4)
v • d • e


Text

June 5, 2008 Mr. Michael W. Rencheck Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

SUBJECT:

D. C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1) - REQUEST FOR ADDITIONAL INFORMATION, REGARDING RE-ANALYSIS OF LARGE-BREAK LOSS-OF-COOLANT ACCIDENT (TAC NO. MD7556)

Dear Mr. Rencheck:

In a letter dated December 27, 2007, Indiana Michigan Power Company (I&M) requested an amendment to modify Technical Specification (TS) 3.4.1, RCS [Reactor Coolant System]

Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits, and TS 5.6.5, Core Operating Limits Report (COLR), in support of a new analysis of a large-break loss-of-coolant accident (LBLOCA).

The Nuclear Regulatory Commission (NRC) staff reviewed the December 27, 2007, submittal and issued a draft Request for Additional Information (RAI) on April 10, 2008 (Accession No.

ML081010615). On May 15, 2008, the NRC staff discussed the draft RAI with I&M staff, and participants agreed that the draft RAI can be formally issued. Accordingly, the finalized RAI is issued as enclosure to this letter.

In accordance with the timeliness provision of 10 CFR 2.108, please respond within 30 days of receipt of this letter. Feel free to contact me if you need clarification of this RAI.

Sincerely,

/RA/

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315

Enclosure:

As stated cc: See next page

ML081570070 OFFICE LPL3-1\PM LPL3-1/LA SRSB SRSB/BC LPL3-1/BC NAME PTam THarris FOrr GCranston JCushing for LJames DATE 6/3/08 6/3/08 6/5/08 6/5/08 6/5/08

REQUEST FOR ADDITIONAL INFORMATION D.C. COOK NUCLEAR PLANT, UNIT 1 (DCCNP-1)

RE-ANALYSIS OF LARGE-BREAK LOSS-OF-COOLANT ACCIDENT (LBLOCA)

(1) To show that the referenced generically approved ASTRUM LOCA analysis methodology applies specifically to DCCNP-1, please provide a statement that Indiana Michigan Power and its vendor (Westinghouse) have ongoing processes which assure that the ranges and values of the input parameters for DCCNP-1 LOCA analyses bound the ranges and values of the as-operated plant parameters.

(2) The discussion in the December 27, 2007, submittal did not address the effects of the mixed core on peak cladding temperature (PCT) and oxidation for the pre-resident fuel, but it does seem to address the PCT and oxidation for the new fuel. Please clarify if this is a whole core reload. In its Rulemaking Hearing dated December 28, 1983, the Nuclear Regulatory Commission stated, regarding the performance criteria of 10 CFR 50.46 (b): "In view of the lack of experience in this hypothetical situation, we think it prudent to apply our criteria to all of the core and not to exempt any part."

Please address PCT and oxidation results for "pre-resident" fuel in the core, if any.

[Note: In a letter to NEI dated November 8, 1999, G. M. Holahan, reiterated the NRC position that "total oxidation" encompasses accident and pre-accident oxidation. This position continues to apply. Therefore, in response to this question, please provide total oxidation for the "other" (pre-resident) fuel (if any), including pre-accident oxidation, plus LOCA cladding outside oxidation, plus cladding inside oxidation.]

(3) Please verify that the treatment of the vessel wall (radial noding, etc.) during reflood remains as historically approved in addressing the issue of downcomer boiling.

Donald C. Cook Nuclear Plant, Units 1 and 2 cc:

Attorney General Department of Attorney General Michigan Department of Environmental 525 West Ottawa Street Quality Lansing, MI 48913 Waste and Hazardous Materials Div.

Radiological Protection Section Township Supervisor Radiological Assessment Unit Lake Township Hall Constitution Hall, Lower-Level North P.O. Box 818 525 West Allegan Street Bridgman, MI 49106 P. O. Box 30241 Lansing, MI 48909-7741 U.S. Nuclear Regulatory Commission Resident Inspector's Office Joel P. Gebbie, Plant Manager 7700 Red Arrow Highway Indiana Michigan Power Company Stevensville, MI 49127 Nuclear Generation Group One Cook Place Kimberly Harshaw, Esquire Bridgman, MI 49106 Indiana Michigan Power Company One Cook Place Lawrence J. Weber, Site Vice President Bridgman, MI 49106 Indiana Michigan Power Company Nuclear Generation Group Mayor, City of Bridgman One Cook Place P.O. Box 366 Bridgman, MI 49106 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 James M. Petro, Jr.

Regulatory Affairs Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

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