ML20141M808

Advises That DBAs Re Permanent Loss of Forced Circulation & Rapid Depressurization of Reactor Vessel Must Be Addressed in Equipment Qualification Program.Util Cooperation W/Program Mods Confirmed During 851029 Meeting

ML20141M808
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/14/1986
From:	Berkow H Office of Nuclear Reactor Regulation
To:	Walker R PUBLIC SERVICE CO. OF COLORADO
References
TAC-42527, NUDOCS 8602280258
Download: ML20141M808 (4)

Text

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February 14, 1986 Docket No. 50-267 DISTRIBUTION:

Docket File

• 0 Lynch SSPD~ Re~a'di ng HBerkow Mr. R. F. Walker, President NRC PDR WShields, OELD Public Service Company of Colorado Local PDR PShemanski Post Office Box 840 DCS JCalvo Denver, Colorado 80201 NSIC PNoonan

Dear Mr. Walker:

KHeitner

SUBJECT:

FORT ST. VRAlii DESIGN BASIS ACCIDENTS AND EQUIPMENT QUALIFICATION During our October 29, 1985 meeting on equipment qualification (EQ), the NRC staff expressed concern that the Fort St. Vrain (FSV) Design Basis Accidents (DBAs) were not properly reflected as inputs to the EQ program. The two DBAs in question are:

DBA 6 - Permanent Loss of Forced Circulation, and DBA #2 - Rapid Depressurization of the Reactor Vessel.

These DBAs were selected "as being representative of accidents that, although they are highly improbable, have potentially significant consequences."

It is the NRC's position that these DBAs must be reflected in FSV's EQ program at least as follows:

1. Electric equipment described in the FSV-FSAR under these DBA scenarios should be included in the FSV-EQ program.

2. Harsh environments created by these DBAs as described in the FSV-FSAR should be evaluated in the basis for the FSV-EQ program. The program should also evaluate the spectrum of harsh environments that could be created by accidents less severe than the DBA itself.

In further discussions with your staff since the October 29, 1985 meeting, it is our understanding that the Public Service Company of Colorado intends to adhere to this guidance in its EQ progrn. However, if you have any further questions please contact the NPC Project Manager, Kenneth L.

Heitner, at (301) 492-8288.

Sincerely, Original signed by  ;

Herbert N. Berkow, Director e6022802$ h2Moo267 Standardization and Special PDR ADO PDR Projects Directorate P

Division of PWR Licensing-B, NRR cc: See next page 1  ;

• SEE PREVIOUS CONCURRENCE SHEET DPWRL-B:SSPD* DPWRL-B:SSPD* DPW -B:SSPD* PEICSB* OELD* 4 1 SSPD DPWP,3 PNoonan:ac KHeitner OL ch OParr WShields HB(rjW 01/13/86 01/13/86 01 86 s 01/22/86 0('30/86 02//p86

Docket No. 50-267 DISTRIBUTION:

Docket File 0 Lynch SSPD Reading HBerkow Mr. R. F. Walker, President NRC PDR WShields, OELD Public Service Company of Colorado Local PDR PShemanski Post Office Box 840 DCS JCalvo Denver, Colorado 80201 NSIC PNoonan

Dear Mr. Walker:

KHeitner

SUBJECT:

FORT ST. VRAIN DESIGN BASIS ACCIDENTS AND EQUIPMENT QUALIFICATION During our October 29, 1985 meeting on equipment qualification (EQ), the NRC staff expressed concern that the Fort St. Vrain (FSV) Design Basis Accidents (DBAs) were not properly reflected as inputs to the EQ program. The two DBAs in question are:

DBA #1 - Permanent Loss of Forced Circulation, and DBA #2 - Rapid Depressurization of the Reactor Vessel.

These DBAs were selected "as being representative of accidents that, although they are highly improbable, have potentially significant consequences."

It is the NRC's position that these DBAs must be reflected in FSV's EQ program at least as follows:

1. Electric equipment described in the FSV-FSAR under these DBA scenarios should be included in the FSV-EQ program.

2. Harsh environments created by these DBAs as described in the FSV-FSAR should be evaluated in the basis for the FSV-EQ program. The program should also evaluate the spectrum of harsh environments that could be created by accidents less severe than the DBA itself.

In further discussions with your staff since the October 29, 1985 meeting, it is our understanding that the Public Service Company of Colorado intends to adhere to this guidance in its EQ program. However, if you have any further at (301) questions 492-7364. please contact the NRC Project Manager, Kenneth L. Hietner Sincerely, Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B, NRR cc: See next page KH p g PD DPWRL-B:SSPD WRL- PD OELDs)t$ DPWRL-B:SSID an:ac KHeitner OL OParr WShields HBerkow

, 86 01/b/86 / 01/tt/86 01/'M/86 01/ /86

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1. o s UNITED STATES P 'l NUCLEAR REGULATORY COMMISSION g ap WASHINGTON, D. C. 20555

\...../ February 14, 1986 Docket No. 50-267 Mr. R. F. Walker, President Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201

SUBJECT:

FORT ST. VRAIN DESIGN BASIS ACCIDENTS AND EQUIPMENT QUALIFICATION During our October 29, 1985 meeting on equipment qualification (EQ), the NRC staff expressed concern that the Fort St. Vrain (FSV) Design Basis Accidents (DBfs) were not properly reflected as inputs to the EQ program. The two DBAs in question are:

DBA #1 - Permanent Loss of Forced Circulation, and DBA #2 - Rapid Depressurization of the Reactor Vessel. -

These DBAs were selected "as being representative of accidents that, although they are highly improbable, have potentially significant consequences."

It is the NRC's position that these DBAs must be reflected in FSV's EQ program at least as follows:

1. Electric equipment described in the F.SV-FSAR under these DBA scenarios should be included in the FSV-EQ program.

2. Harsh environments created by these DBAs as described in the FSV-FSAR

_ should be evaluated in the basis for the FSV-EQ program. The program should also evaluate the spectrum of harsh environments that could be created by accidents less severe than the DBA itself.

In further discussions with your staff since the October 29, 1985 meeting, l it is our understanding that the Public Service Company of Colorado intends to adhere to this guidance in its EQ program. However, if you have any further questions please contact the NRC Project Manager, Kenneth L.

Heitner, at (301) 492-8288. j i

Sincerely, I d

• Herbert N. Berkow, Director _ L -

Standardization and Special !

Projects Directorate Division of PWR Licensing-B, NRR cc: See next page

Mr. R. F. Walker Public Service Company of Colorado Fort St. Vrain cc:

Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201 Pir. David Alberstein,14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. L. W. Singleton, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Fort St. Vrain Nuclear Station Denver, Colorade 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 4

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission

-- Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1800 Lincoln Street Denver, Colorado 80203 .

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