ML062510064

GL 2003-01 Closeout Letter

ML062510064
Person / Time
Site:	Saint Lucie
Issue date:	10/04/2006
From:	Moroney B NRC/NRR/ADRO/DORL/LPLII-2
To:	Stall J Florida Power & Light Co
Moroney B, NRR/DORL, 415-3974
References
GL-03-001, TAC MB9849, TAC MB9850
Download: ML062510064 (4)

Text

October 4, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE NUCLEAR PLANT, UNITS 1 AND 2 - NRC RECEIPT OF RESPONSE TO GENERIC LETTER 2003-01, CONTROL ROOM HABITABILITY (TAC NOS. MB9849 AND MB9850)

Dear Mr. Stall:

The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your response to Generic Letter (GL) 2003-01, Control Room Habitability, in letters dated August 11, 2003 (Agencywide Documents Access and Management System Accession No. ML032250375),

December 9, 2003 (ML033450304), and October 29, 2004 (ML043070441). This letter provides a status of your response and describes any additional information that may be necessary to consider your response to GL 2003-01 complete.

The GL requested that you confirm that the St. Lucie Unit 1 and 2 control rooms meet their design bases (e.g., General Design Criteria [GDC] 1, 3, 4, 5 and 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 your 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 your 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 (CRH) and plans to retire them (GL 2003-01, Item 2).

You reported the results of tracer gas tests for the St. Lucie Unit 1 and 2 control rooms, which are separate control rooms that are pressurized for accident mitigation, using American Society for Testing and Materials standard ASTM E741, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution.

For Unit 1, you determined that the maximum tested value for inleakage into the Control Room Envelope (CRE) was 423 cubic feet per minute (cfm), which is less than the value of 500 cfm assumed in your operability determination using the current methodology in the Updated Final Safety Analysis Report (UFSAR).

For Unit 2, you determined that the maximum tested value for inleakage into the CRE was 229 cfm, which is less than the value of 430 cfm assumed in your operability determination using the current UFSAR methodology.

Mr. J. A. Stall You stated your plan to revise each units design basis radiological dose analysis for CRH using Alternate Source Term (AST) methodology, which will add some margin by increasing the allowable leakage value.

You indicated that, based on your evaluation, you have concluded that no hazards exist to the control room personnel from postulated chemical releases in and around the plant. You also indicated 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 (TSs) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analyses for CRH, in light of the demonstrated inadequacy of a delta () P measurement as the only method to provide such verification (GL 2003-01, Item 1c). As permitted by the GL, you provided a schedule for revising the surveillance requirements (SRs) in the TSs to reference an acceptable surveillance methodology. In your October 29, 2004, response, you indicated that you will submit a license amendment request (LAR) to adopt TS SRs that verify CRH per TS Task Force (TSTF) traveler TSTF-448 within 6 months following NRC approval of TSTF-448.

The information you provided indicated that there are no interim compensatory measures currently required to demonstrate CRH. The NRC staff notes that you rely on an operability determination to demonstrate CRH, which needs to be retired by changing the design basis information in the UFSAR. However, the NRC staff also notes that you have committed to revise your UFSAR design basis radiological dose analyses for CRH using AST methodology.

The information you provided supported the NRC staff conclusion that your are committed to meet the draft GDC for Unit 1 and the GDC for Unit 2 regarding CRH.

Your commitment to revise your design basis radiological dose analyses for CRH using AST methodology and to adopt industry standard TSs based on TSTF-448 is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submission of the LARs and interact with you, as necessary, during the amendment process.

If you have any questions regarding this correspondence, please contact me at (301) 415-3974.

Sincerely,

/RA Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: See next page

ML062510064 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA SCVB/BC PGCB/BC LPL2-2/BC(A)

NAME BMoroney BClayton RDennig CJackson LRaghavan DATE 09/14 /06 09/14/06 09/18/06 09/18/06 10/04/06

Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:

Mr. William E. Webster Mr. Christopher R. Costanzo Vice President, Nuclear Operations Plant General Manager Florida Power & Light Company St. Lucie Nuclear Plant P.O. Box 14000 6351 South Ocean Drive Juno Beach, FL 33408-0420 Jensen Beach, Florida 34957 Senior Resident Inspector Mr. Terry Patterson St. Lucie Plant Licensing Manager U.S. Nuclear Regulatory Commission St. Lucie Nuclear Plant P.O. Box 6090 6351 South Ocean Drive Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Craig Fugate, Director Mark Warner, Vice President Division of Emergency Preparedness Nuclear Operations Support Department of Community Affairs Florida Power & Light Company 2740 Centerview Drive P.O. Box 14000 Tallahassee, Florida 32399-2100 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Mr. Rajiv S. Kundalkar Florida Power & Light Company Vice President - Nuclear Engineering P.O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company Mr. J. Kammel 801 Pennsylvania Avenue, NW. Radiological Emergency Suite 220 Planning Administrator Washington, DC 20004 Department of Public Safety 6000 Southeast Tower Drive Mr. Douglas Anderson Stuart, Florida 34997 County Administrator St. Lucie County Mr. Bill Parks 2300 Virginia Avenue Operations Manager Fort Pierce, Florida 34982 St. Lucie Nuclear Plant 6351 South Ocean Drive Mr. William A. Passetti, Chief Jensen Beach, Florida 34957-2000 Department of Health Bureau of Radiation Control Mr. Seth B. Duston 2020 Capital Circle, SE, Bin #C21 Training Manager Tallahassee, Florida 32399-1741 St. Lucie Nuclear Plant 6351 South Ocean Drive Mr. Gordon L. Johnston Jensen Beach, Florida 34957-2000 Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000