ML070440058
| ML070440058 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/28/2007 |
| From: | Tam P NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Nazar M Indiana Michigan Power Co |
| Tam P | |
| References | |
| GL-03-001, TAC MB9794, TAC MB9795 | |
| Download: ML070440058 (4) | |
Text
February 28, 2007 Mr. Mano K. Nazar 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, UNITS 1 AND 2 (DCCNP-1 AND DCCNP-2) -
NRC RECEIPT OF RESPONSE TO GENERIC LETTER (GL) 2003-01 CONTROL ROOM HABITABILITY (TAC NOS. MB9794 AND MB9795)
Dear Mr. Nazar:
The Nuclear Regulatory Commission (NRC) acknowledges receipt of your responses to Generic Letter 2003-01 Control Room Habitability dated December 4, 2003 (Accession No. ML033460373); December 20, 2004 (Accession No. ML043630275); and December 21, 2005 (Accession No. ML060040237). This letter provides a status of your response and describes any actions that may be necessary to consider your response to GL 2003-01 complete.
GL 2003-01 requested that you confirm that your control room meet its design bases (e.g.,
General Design Criterion (GDC) 1, 3, 4, 5, and 19, draft GDCs, or principal design criteria), with special attention to: (1) determination of the most limiting unfiltered and/or filtered inleakage into the control room and comparison to values used in your design bases for meeting control room operator dose limits from accidents (Issue 1(a)); (2) determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments; and (3) determination that reactor control capability is maintained in the control room or at the alternate shutdown location in the event of smoke (Issue 1(b)). The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire them (Issue 2).
You reported the results of ASTM E741 (American Society for Testing Materials, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution) tracer gas tests for the plant, which has two separate but similar control room envelopes with the control rooms being adjacent to each other on the same elevation. The control rooms are pressurized for accident mitigation. For DCCNP-1, you determined that the most limiting unfiltered inleakage into the control room envelope (CRE) was 94 cfm, which is less than the value of 98 cfm assumed in the design-basis radiological analyses for control room habitability.
For DCCNP-2, you determined that the most limiting unfiltered inleakage into the CRE was 98 cfm, which is equal to the value of 98 cfm assumed in the design basis radiological analyses for control room habitability.
You provided information that adequately supports your conclusion that the most limiting unfiltered inleakage into the CRE is incorporated into the hazardous chemical assessments,
M. K. Nazar and that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
The GL further requested that you assess your technical specifications to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design-basis analysis for control room habitability, and in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (Issue 1c). As permitted by the GL, you provided a schedule for revising the surveillance requirement in the technical specifications to reference an acceptable surveillance methodology. In your December 4, 2003, response, you stated that you would determine the applicability of the approved TSTF-448 and submit a license amendment application to require periodic measurement of unfiltered control room envelope inleakage.
The information you provided supports the fact that there are no compensatory measures in place to demonstrate control room habitability.
The information you provided also supports the conclusion that DCCNP-1 and DCCNP-2 meet the intent of the draft GDC regarding control room habitability as documented in the D. C. Cook Updated Final Safety Analysis Report.
Your commitment (above) to submit a license amendment application based on TSTF-448 is acceptable for the purpose of closing out NRCs review of your response to GL 2003-01.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 cc: See next page
M. K. Nazar and that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
The GL further requested that you assess your technical specifications to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design-basis analysis for control room habitability, and in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (Issue 1c). As permitted by the GL, you provided a schedule for revising the surveillance requirement in the technical specifications to reference an acceptable surveillance methodology. In your December 4, 2003, response, you stated that you would determine the applicability of the approved TSTF-448 and submit a license amendment application to require periodic measurement of unfiltered control room envelope inleakage.
The information you provided supports the fact that there are no compensatory measures in place to demonstrate control room habitability.
The information you provided also supports the conclusion that DCCNP-1 and DCCNP-2 meet the intent of the draft GDC regarding control room habitability as documented in the D. C. Cook Updated Final Safety Analysis Report.
Your commitment (above) to submit a license amendment application based on TSTF-448 is acceptable for the purpose of closing out NRCs review of your response to GL 2003-01.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316 cc: See next page DISTRIBUTION:
PUBLIC LPL3-1 r/f JRobinson RidsNrrDorlLple RidsNrrLATHarris GTesfaye RidsNrrPMPTam RidsOgcRp RidsAcrsAcnwMailCenter RidesRgn3MailCenter Accession Number: ML070440058 OFFICE LPL3-1/PM LPL3-1/ LA SCVB/BC PGCB LPL3-1/BC NAME PTam THarris RDennig CJackson LRaghavan DATE 2/23/07 2/21/07 2/26/07 2/26/07 2/28/07 OFFICIAL RECORD COPY
Donald C. Cook Nuclear Plant, Units 1 and 2 cc:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 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 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 Susan D. Simpson 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.
Hazardous Waste & Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P. O. Box 30241 Lansing, MI 48909-7741 Lawrence J. Weber, Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Mark A. Peifer, Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106