ML070100627
| ML070100627 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/02/2007 |
| From: | Wang A NRC/NRR/ADRO/DORL/LPLIV |
| To: | Ridenoure R Omaha Public Power District |
| Wang A, NRR/DORL/LP4, 415-1445 | |
| References | |
| GL-03-001, TAC MB9806 | |
| Download: ML070100627 (4) | |
Text
March 2, 2007 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - CLOSEOUT OF GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NO. MB9806)
Dear Mr. Ridenoure:
The U.S. Nuclear Regulatory Commission (NRC) acknowledges the receipt of Omaha Public Power Districts (OPPDs) responses to Generic Letter (GL) 2003-01, Control Room Habitability, dated December 5, 2003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML033430569), October 5, 2004 (ADAMS Accession No. ML042790399), and December 28, 2006 (ADAMS Accession No. ML063630243). This letter provides a status of OPPDs responses and describes any actions that may be necessary to consider these responses to GL 2003-01 complete.
The GL requested that OPPD confirm that the Fort Calhoun Station, Unit No. 1 (FCS), control room meet its design bases (e.g., General Design Criteria (GDC) 1, 3, 4, 5, & 19, draft GDC, 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 OPPDs design bases for meeting control room operator dose limits from accidents (GL 2003-01, Item 1a);
(2) determination that the most limiting unfiltered inleakage is incorporated into OPPDs hazardous chemical assessments (GL 2003-01, Item 1b); and (3) determination that reactor control capability is maintained in the control room or at the alternate shutdown location in the event of smoke (GL 2003-01, Item 1b).
The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire them (GL 2003-01, Item 2).
OPPD 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 FCS control room, which is pressurized for accident mitigation:
OPPD determined that the most limiting unfiltered inleakage into the Control Room Envelope (CRE) was 8 standard cubic feet per minute (scfm), which is less than
R. T. Ridenoure the value of 38 scfm assumed in the design-basis radiological analyses for Control Room Habitability (CRH).
OPPD also provided information that adequately supported a conclusion that the most limiting unfiltered inleakage into the CRE is incorporated into the hazardous chemical assessments, 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 OPPD assess its Technical Specifications (TSs) 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 (GL 2003-01, Item 1.c). As permitted by the GL, OPPD provided a schedule for revising the surveillance requirement in the TSs to reference an acceptable surveillance methodology. In its October 5, 2004, response, OPPD indicated that it would submit a CRH license amendment request (LAR) within 120 days of the NRC approval of Technical Specification Task Force Traveler 448 (TSTF-448) to include specific exceptions to Regulatory Guide 1.196/1.197 and justification for the exceptions.
The information OPPD provided also supported the fact that there are no compensatory measures needed to be in place to demonstrate control room habitability.
In addition, the information OPPD provided supported the conclusion that OPPD is committed to meet the intent of the draft GDC (with the exception of GDC-19 which you are committed to meet due to the implementation of an Alternate Source Term) regarding control room habitability.
OPPDs commitment to submit an LAR based on TSTF-448, as stated above, is acceptable for purposes of closing out OPPDs response to GL 2003-01.
If you have any questions regarding this correspondence, please contact me at 301-415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: See next page
ML070100627 OFFICE LPL4/PM LPL4/LA DPR/PGCB/BC DRA/SCVB/BC LPL4/BC NAME AWang LFeizollahi CJackson RDennig DTerao DATE 2/5/07 2/5/07 2/5/07 2/5/07 3/2/07
April 2006 Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn ATTN: James R. Curtiss, Esq.
1700 K Street, N.W.
Washington, DC 20006-3817 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319