ML062510470: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:September 20, 2006Mr. H. L. Sumner, Jr. Vice President - Farley Project Southern Nuclear Operating Company, Inc.
{{#Wiki_filter:September 20, 2006 Mr. H. L. Sumner, Jr.
Vice President - Farley Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295
Post Office Box 1295 Birmingham, Alabama 35201-1295


==SUBJECT:==
==SUBJECT:==
NRC RECEIPT OFJOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2,RESPONSE TO GENERIC LETTER 2003-01 "CONTROL ROOM HABITABILITY" (TAC NOS. MB9802 AND MB9803)
NRC RECEIPT OFJOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2, RESPONSE TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NOS. MB9802 AND MB9803)


==Dear Mr. Sumner:==
==Dear Mr. Sumner:==


The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses toGeneric Letter (GL) 2003-01 "Control Room Habitability" dated August 4, 2003 (ML032190245)and August 25, 2004 (ML042400122) for the Farley Nuclear Plant, Units 1 and 2, (Farley).
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to Generic Letter (GL) 2003-01 Control Room Habitability dated August 4, 2003 (ML032190245) and August 25, 2004 (ML042400122) for the Farley Nuclear Plant, Units 1 and 2, (Farley). This letter provides the status of our review of your response and describes any actions that may be necessary to consider your response to GL 2003-01 complete.
Thisletter provides the status of our review of your response and describes any actions that may benecessary to consider your response to GL 2003-01 complete.The GL requested that you confirm that your control rooms meet their 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 your design bases for meeting control room operator dose limits from accidents (GL item 1a); (2) Determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments; and (3)
The GL requested that you confirm that your control rooms meet their design bases (e.g.,
Determination that reactor control capability is maintained in the control room or at the alternateshutdown location in the event of smoke (GL item 1b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans toretire them (GL item 2).You reported the results of ASTM E741, (American Society for Testing Materials, Standard TestMethod for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution), tracergas tests for the Farley control room which is pressurized for accident mitigation. You determined that the maximum tested unfiltered inleakage into the Control Room Envelope(CRE) was 25 cubic feet per minute (cfm), which is less than the unfiltered inleakage value of 53 cfm assumed in your latest design basis radiological dose calculation. You also reported that the maximum tested inleakage value of 87 cfm into the CRE is less thanthe value of 2350 cfm incorporated into the hazardous chemical assessments, and that reactorcontrol capability is maintained from either the control room or the alternate shutdown panel inthe event of smoke.The GL further requested that you assess your Technical Specifications (TS) to determine ifthey verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for control room habitability, in light of the demonstrated inadequacyof a differential pressure measurement alone to provide such verification (GL Item 1.c). The H. Summer, Jr.- 2 -NRC staff noted that you have recently revised your TS to incorporate inleakage surveillancebased on the model TS and TS Bases contained in NRC Regulatory Guide 1.196, "ControlRoom Habitability at Light-Water Nuclear Power Reactors". The information you provided also confirms that no compensatory measures are required todemonstrate control room habitability and that Farley conforms to the GDC regarding controlroom habitability.Based on your responses, the NRC staff finds that no additional actions are required andconsiders your response to GL 2003-01 to be complete.Sincerely,    /RA/Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-348 and 50-364 cc w/encl:  See next page H. Summer, Jr.- 2 -NRC staff noted that you have recently revised your TS to incorporate inleakage surveillancebased on the model TS and TS Bases contained in NRC Regulatory Guide 1.196, "ControlRoom Habitability at Light-Water Nuclear Power Reactors". The information you provided also confirms that no compensatory measures are required todemonstrate control room habitability and that Farley conforms to the GDC regarding controlroom habitability.Based on your responses, the NRC staff finds that no additional actions are required andconsiders your response to GL 2003-01 to be complete.Sincerely,  /RA/Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-348 and 50-364 cc w/encl:  See next page DISTRIBUTION
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 your design bases for meeting control room operator dose limits from accidents (GL item 1a); (2) Determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments; and (3)
: PublicRidsAcrsAcnwMailCenter RidsNrrPMRjerveyLPL2-1 R/FG. Hill, OiS (4 hard copies)RidsNrrDorlDpr (BSingal)RidsNrrDorlLpl2-1(EMarinos)RidsNrrDirsItsb(TKobetz)RidsNrrPMRMartin(hard copy)RidsOgcRpRidsRgn2MailCenter(SShaeffer)RidsNrrLARSola(hard copy)Accession No.:  ML062510470NRR-106OFFICENRR/LPL2-1/PMNRR/LPL2-1/LANRR/PGCB/BCNRR/SCVB/BCNRR/LPL2-1/BCNAMERMartinRSolaCJacksonRDennigEMarinosDATE8/24/0609/11/0608/29/0608/24/0609/20/06OFFICIAL RECORD COPY Joseph M. Farley Nuclear Plant, Units 1 & 2 cc:
Determination that reactor control capability is maintained in the control room or at the alternate shutdown location in the event of smoke (GL item 1b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire them (GL item 2).
Mr. J. R. JohnsonGeneral Manager Southern Nuclear Operating Company, Inc.
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 Farley control room which is pressurized for accident mitigation. You determined that the maximum tested unfiltered inleakage into the Control Room Envelope (CRE) was 25 cubic feet per minute (cfm), which is less than the unfiltered inleakage value of 53 cfm assumed in your latest design basis radiological dose calculation.
You also reported that the maximum tested inleakage value of 87 cfm into the CRE is less than the value of 2350 cfm 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 you assess your Technical Specifications (TS) 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, in light of the demonstrated inadequacy of a differential pressure measurement alone to provide such verification (GL Item 1.c). The


P.O. Box 470 Ashford, AL  36312Mr. B. D. McKinney, Licensing ManagerSouthern Nuclear Operating Company, Inc.
H. Summer, Jr.                               NRC staff noted that you have recently revised your TS to incorporate inleakage surveillance based on the model TS and TS Bases contained in NRC Regulatory Guide 1.196, Control Room Habitability at Light-Water Nuclear Power Reactors.
P.O. Box 1295 Birmingham, AL  35201-1295Mr. M. Stanford BlantonBalch and Bingham Law Firm
The information you provided also confirms that no compensatory measures are required to demonstrate control room habitability and that Farley conforms to the GDC regarding control room habitability.
Based on your responses, the NRC staff finds that no additional actions are required and considers your response to GL 2003-01 to be complete.
Sincerely,
                                              /RA/
Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: See next page


P.O. Box 306 1710 Sixth Avenue North Birmingham, AL  35201Mr. J. GasserExecutive Vice President Southern Nuclear Operating Company, Inc.
H. Summer, Jr.                                                     NRC staff noted that you have recently revised your TS to incorporate inleakage surveillance based on the model TS and TS Bases contained in NRC Regulatory Guide 1.196, Control Room Habitability at Light-Water Nuclear Power Reactors.
P.O. Box 1295 Birmingham, AL  35201State Health OfficerAlabama Department of Public Health 434 Monroe St.
The information you provided also confirms that no compensatory measures are required to demonstrate control room habitability and that Farley conforms to the GDC regarding control room habitability.
Montgomery, AL  36130-1701Chairman Houston County Commission P.O. Box 6406 Dothan, AL  36302Resident InspectorU.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL  36319William D. OldfieldSAER Supervisor Southern Nuclear Operating Company, Inc.
Based on your responses, the NRC staff finds that no additional actions are required and considers your response to GL 2003-01 to be complete.
Sincerely,
                                                                  /RA/
Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: See next page DISTRIBUTION:
Public                          RidsAcrsAcnwMailCenter          RidsNrrPMRjervey              LPL2-1 R/F G. Hill, OiS (4 hard copies)    RidsNrrDorlDpr (BSingal)        RidsNrrDorlLpl2-1(EMarinos)  RidsNrrDirsItsb(TKobetz)
RidsNrrPMRMartin(hard copy)      RidsOgcRp                      RidsRgn2MailCenter(SShaeffer) RidsNrrLARSola(hard copy)
Accession No.: ML062510470                                                                              NRR-106 OFFICE    NRR/LPL2-1/PM    NRR/LPL2-        NRR/PGCB/BC            NRR/SCVB/BC            NRR/LPL2-1/BC 1/LA NAME      RMartin          RSola            CJackson                RDennig                EMarinos DATE      8/24/06          09/11/06          08/29/06                08/24/06              09/20/06 OFFICIAL RECORD COPY


P.O. Box 470 Ashford, AL 36312}}
Joseph M. Farley Nuclear Plant, Units 1 & 2 cc:
Mr. J. R. Johnson                          William D. Oldfield General Manager                            SAER Supervisor Southern Nuclear Operating Company, Inc. Southern Nuclear Operating Company, Inc.
P.O. Box 470                                P.O. Box 470 Ashford, AL 36312                           Ashford, AL 36312 Mr. B. D. McKinney, Licensing Manager Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm P.O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 Mr. J. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Birmingham, AL 35201 State Health Officer Alabama Department of Public Health 434 Monroe St.
Montgomery, AL 36130-1701 Chairman Houston County Commission P.O. Box 6406 Dothan, AL 36302 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL 36319}}

Revision as of 15:18, 23 November 2019

Closeout Ltr GL2003-01 Control Room (TAC Nos. MB9802 and MB9803)
ML062510470
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 09/20/2006
From: Martin R
NRC/NRR/ADRO/DORL/LPLII-1
To: Sumner H
Southern Nuclear Operating Co
Martin R, NRR/DORL, 415-1493
References
GL-03-001, TAC MB9802, TAC MB9803
Download: ML062510470 (4)
v • d • e


Text

September 20, 2006 Mr. H. L. Sumner, Jr.

Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

NRC RECEIPT OFJOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2, RESPONSE TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NOS. MB9802 AND MB9803)

Dear Mr. Sumner:

The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to Generic Letter (GL) 2003-01 Control Room Habitability dated August 4, 2003 (ML032190245) and August 25, 2004 (ML042400122) for the Farley Nuclear Plant, Units 1 and 2, (Farley). This letter provides the status of our review of your response and describes any actions that may be necessary to consider your response to GL 2003-01 complete.

The GL requested that you confirm that your control rooms meet their 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 your design bases for meeting control room operator dose limits from accidents (GL item 1a); (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 (GL item 1b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability, and plans to retire them (GL item 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 Farley control room which is pressurized for accident mitigation. You determined that the maximum tested unfiltered inleakage into the Control Room Envelope (CRE) was 25 cubic feet per minute (cfm), which is less than the unfiltered inleakage value of 53 cfm assumed in your latest design basis radiological dose calculation.

You also reported that the maximum tested inleakage value of 87 cfm into the CRE is less than the value of 2350 cfm 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 you assess your Technical Specifications (TS) 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, in light of the demonstrated inadequacy of a differential pressure measurement alone to provide such verification (GL Item 1.c). The

H. Summer, Jr. NRC staff noted that you have recently revised your TS to incorporate inleakage surveillance based on the model TS and TS Bases contained in NRC Regulatory Guide 1.196, Control Room Habitability at Light-Water Nuclear Power Reactors.

The information you provided also confirms that no compensatory measures are required to demonstrate control room habitability and that Farley conforms to the GDC regarding control room habitability.

Based on your responses, the NRC staff finds that no additional actions are required and considers your response to GL 2003-01 to be complete.

Sincerely,

/RA/

Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: See next page

H. Summer, Jr. NRC staff noted that you have recently revised your TS to incorporate inleakage surveillance based on the model TS and TS Bases contained in NRC Regulatory Guide 1.196, Control Room Habitability at Light-Water Nuclear Power Reactors.

The information you provided also confirms that no compensatory measures are required to demonstrate control room habitability and that Farley conforms to the GDC regarding control room habitability.

Based on your responses, the NRC staff finds that no additional actions are required and considers your response to GL 2003-01 to be complete.

Sincerely,

/RA/

Robert E. Martin, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 cc w/encl: See next page DISTRIBUTION:

Public RidsAcrsAcnwMailCenter RidsNrrPMRjervey LPL2-1 R/F G. Hill, OiS (4 hard copies) RidsNrrDorlDpr (BSingal) RidsNrrDorlLpl2-1(EMarinos) RidsNrrDirsItsb(TKobetz)

RidsNrrPMRMartin(hard copy) RidsOgcRp RidsRgn2MailCenter(SShaeffer) RidsNrrLARSola(hard copy)

Accession No.: ML062510470 NRR-106 OFFICE NRR/LPL2-1/PM NRR/LPL2- NRR/PGCB/BC NRR/SCVB/BC NRR/LPL2-1/BC 1/LA NAME RMartin RSola CJackson RDennig EMarinos DATE 8/24/06 09/11/06 08/29/06 08/24/06 09/20/06 OFFICIAL RECORD COPY

Joseph M. Farley Nuclear Plant, Units 1 & 2 cc:

Mr. J. R. Johnson William D. Oldfield General Manager SAER Supervisor Southern Nuclear Operating Company, Inc. Southern Nuclear Operating Company, Inc.

P.O. Box 470 P.O. Box 470 Ashford, AL 36312 Ashford, AL 36312 Mr. B. D. McKinney, Licensing Manager Southern Nuclear Operating Company, Inc.

P.O. Box 1295 Birmingham, AL 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm P.O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 Mr. J. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.

P.O. Box 1295 Birmingham, AL 35201 State Health Officer Alabama Department of Public Health 434 Monroe St.

Montgomery, AL 36130-1701 Chairman Houston County Commission P.O. Box 6406 Dothan, AL 36302 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL 36319

Retrieved from "https://kanterella.com/w/index.php?title=ML062510470&oldid=2186675"