ML20217K592

Summary of 980407 Meeting W/Util Re Control Room Habitability Issue W/Main Steam Line Break.List of Attendees,Util Presentation Matls & NRC Concept of CR Ventilation Sys Encl

ML20217K592
Person / Time
Site:	Calvert Cliffs
Issue date:	04/20/1998
From:	Vissing G NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9805040032
Download: ML20217K592 (17)

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• , UNITED STATES g -j NUCLEAR REGULATORY COMMISSION i

e WASHINGTON, D.C. =a "1 April 20, 1998

%..... l LICENSEE: Baltimore Gas and Electric Company I FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2

SUMMARY

OF THE APRIL 7,1998, MEETING WITH REPRESENTATIVES OF BALTIMORE GAS AND ELECTRIC (BGE) COMPANY CONCERNING THE  !

CONTROL ROOM HABITABILITY ISSUE WITH A MAIN STEAM LINE BREAK INTRODUCTION In conjunction with a license amendment request of January 31,1997, to change the reactor i coolant system flow requirements to allow increased steam generator tube plugging, the NRC l staff identified concems regarding the dose to the control room during various accidents. In addition to request for additional information of March 30,1998, the staff felt it necessary to have a meeting with the licensee to gain further knowledge on the licensee's plans to alleviate the dose to the control room and the status of Calvert Cliffs to meet General Design Criterion (GDC) 19 for all postulated accidents. Enclosure 1 provides the list of attendees of the meeting.

Enclosure 2 provides the licensee's presentation on the in leakage concems of the control room ventilation system. Enclosure 3 provides the staff's concept of the control room ventilation system.

1 DISCUSSION The staff identified the concem that the March 17,1998, submittal on control room operator dose /

was based upon the condition of the control room ventilation system repairs and modifications are completed. The existing control room condition was shown to have an in leakage, based

/

upon tracer gas tests, of greater than 4000 cfm. No analysis has been presented to the staff that d provides the doses based upon the existing control room conditions. It was prudent for the U.

licensee to identify the in leakage into the control room ventilation system and to make modifications that would seal the areas of concem especially in the roof area where the consequences of a postulated steam line break would be most severe. Also, the licensee needed to tell the staff how they are presently meeting GDC-19.

Enclosure 2 provides the licensee's presentation on the testing of the control room ventilation system for in leakage and the areas of modifications being made or planned to reduce the leakage. The licensee indicated that the modifications would not be completed before December 1999. The licensee also presented a discussion of their response to the request for additional information of March 30,1998. This response is soon to be sent to the NRC. In addition the licensee will include in that response a concem of the sequence of shutdown - whether reactor trip, turbine trip and loss of offsite power are assumed to occur concurrently for a main steam line break accident.

Discussion was held on the surveillance requirements for the laboratory testing of the charcoal filters in the control room ventilation system. Calvert Cliffs current Technical Specifications requires the filters to have a 90% efficiency. The Calvert Cliffs's procedures test the filters for 94% efficiency which, in their view, would provide a margin to allow degradation between refueling outages of 4%. Such a procedure could be changed through the 10 CFR 50.59 process. The staff's view was that the surveillance should incorporate a safety factor. This would assure at least a 90% efficiency through out the operating cycle and would provide some

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9905040032 900420 PDR ADOCK 05000317 P PDR

2-assurance that a procedure change would not be made which inadvertently negates the previously approved licensing analysis. The staff recognized that because of the unique operation of the control room ventilation system during an accident (the ventilation system is operated in the recirculation mode), with technicaljustification, the filters could be tested at a relative humidity of 70% rather then the existing 95%.

CONCLUSIONS The staff concluded that the licensee needed to document to the staff an analysis which demonstrates the Calvert Cliff Plant's capability to meet GDC 19 in its present condition. The ,

staff also needs the licensee to document the basis for delaying control room repairs until December 1999. The staff has requested a response to the testing requirements for the l efficiency of the charcoal filters and how the requirements would be controlled. Finally, clarification is required as to whether, for a main steam line break accident, the reactor trip, turbine trip and loss of off site power are assumed to occur concurrently.

The licensee indicated they would be responding by letter shortly to the accident analysis issues raised in the March 30,1998, request for additional information and also to the sequence of shutdown during a main steam line break accident. For the charcoal filter and other issues, the licensee will consider the staff's views and provide a response later.

) =I Guy S. Vissing, Senior roject Manager Project Directorate 1-1 <

Division of Reactor Projects - 1/11 l Docket Nos. 50-317 4 and 50-318

Enclosures:

1. List of attendees

2. BG&E presentation materials ,

3. NRC staff concept of CR ventilation system I l

cc w/encis

See next page l j

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Calvert Cliffs Nuclear Power Plant  ;

Baltimore Gas & Electric Company Unit Nos.1 and 2 i cc:

President Mr. Joseph H. Walter, Chief Engineer Calvert County Board of Public Service Commission of l Commissioners Maryland I 175 Main Street Engineering Division  !

Prince Frederick, Md 20678 6 St. Paul Centre Baltimore, MD 21202-6806 James P. Bennett, Esquire Counsel Kristen A. Burger, Esquire  !

Baltimore Gas and Electric Company Maryland People's Counsel l P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2101 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire Shaw, Pittman, Potts and Trowbridge Patricia T. Bimie, Esquire

! 2300 N Street, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Thomas N. Pritchett, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatelt 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road

, Chattanooga, TN 37411-4017 l Resident inspector

c/o U.S. Nuclear Regulatory Mr. Charles H. Cruse Commission Vice President- Nuclear Energy  ;

P.O. Box 287 Baltimore Gas and Electric Company i St. Leonard, MD 20685 Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Mr. Richard I. McLean, Manager Lusby, MD 20657-4702 Nuclear Programs l Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401 l Regional Administrator, Region l l U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

LIST OF ATTENDEES BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 AND 2 APRIL 7,1998 Name Orainization Guy Vissing NRR/DRPE/PDI-1 Gerard Gryczkowski BGE Pat Funo BGE Jack Hayes NRR/DRPM/PERB John Segala NRR/DSSA/SPLB Mark Finley BGE l Gus Wolf BGE John Wynn BGE i Andrew Henni BGE Frank Orr l NRR/DSSA/SRXB Rich Emch {

NRR/DRPM/PERB Janak Raval NRR/DSSA/SPLB Singh Bajwa NRR/DRPE/PDI-1 i Harold Walker NRR/DSSA/SPLB l

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Meeting Summary Distribution: Dated: April 20, 1998 LICNENSEE: Baltimore Gas and Electric Company FACILITY: Calvert Cliffs Nuclear Powser Plant, Unit Nos.1 and 2

SUMMARY

OF THE APRIL 7,1998, MEETING WITH REPRESENTATIVES OF BALTIMORE GAS AND ELECTRIC (BGE) COMPANY CONCERNING THE CONTROL ROOM HABITABILITY ISSUE WITH A MAIN STEAM LINE BREAK E-Mail (w/ encl.1) Hard Copy (w/all encts.)

S. Collins /F, Miraglia (SJC1FJM)

-a 1:3

[ Docket File B. Boger (A) (BAB2) PUBLIC J. Zwolinski (A) P DI-1 ! Y  ;

S. Bajwa G. Vissaig S. Little A. Dromerick T. Martin (SLM3) OGC J. Hayes ACRS J. Segala ,

F. Orr J R. Emch cc: Licensee & Service List J. Raval H. Walker B. McCabe (BCM) rrg n y ~ ~. ,,

te irar EFjiER 00Py I

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April 20,1998 assurance that a procedure change would not be made which inadvertently negates the previously approved licensing analysis. The staff recognized that because of the unique operation of the control room ventilation system during an accident (the ventilation system is operated in the recirculation mode), with technicaljustification, the filters could be tested at a relative humidity of 70% rather then the existing 95%.

CONCLUSIONS The staff concluded that the licensee needed to document to the staff an analysis which demonstrates the Calvert Cliff Plant's capability to meet GDC 19 in its present condition. The l staff also needs the licensee to document the basis for delaying control room repairs until December 1999. The staff has requested a response to the testing requirements for the -

efficiency of the charcoal filters and how the requirements wou'd be controlled. Finally, clarification is required as to whether, for a main steam line break ~ accident, the reactor trip, j turbine trip and loss of off site power are assumed to occur concurrently.

- The licensee indicated they would be responding by letter shortly to the accident analysis issues raised in the March 30,1998, request for additional information and also to the sequence of shutdown during a main steam line break accident." For the charcoal filter and other issues, the licensee will consider the staff's views and provide a response later.

l Original Signed by:

l Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 l

Enclosures:

1. List of attendees l 2. BG&E presentation materials

j. 3. NRC staff concept of CR ventilation system cc w/encis: See next page l

l.

DOCUMENT NAME: G:\CC1-2\040798.MTS To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with ettichment/ enclosure "N" = No copy .

OFFICE PM:PDI 1 lE LA:PDIli)( l D:PDI 1 dl b I I I NAME GVlasing:tec 2 Stitt 7 Stejus 8' %

DATE 04//p/96 MX 04/B496 04/AD/98 04/ /96 04/ /98 Official Record Copy

i .

Meeting Summary Distribution: Dated: April 20, 1998 LICNENSEE: Baltimore Gas and Electric Company FACILITY: Calvert Cliffs Nuclear Powser Plant, Unit Nos 1 and 2

SUMMARY

OF THE APRIL 7,1998, MEETING WITH REPRESENTATIVES OF BALTIMORE GAS AND ELECTRIC (BGE) COMPANY CONCERNING THE CONTROL ROOM HABITABILITY ISSUE WITH A MAIN STEAM LINE BREAK E-Mail (w/ encl.1) Hard Coov (w/all encls.) ,

l S. Collins /F. Miraglia (SJCWJM) Docket File B. Boger (A) (BAB2) {

PUBLIC J. Zwolinski (A) PDI-1 R/F S. Bajwa G. Vissing S. Little A. Dromerick T. Martin (SLM3) OGC J. Hayes ACRS J.Segala '

F. Orr R. Emch cc: Licensee & Service List J. Raval H. Walker B. McCabe (BCM) i i

I l

I l

l l 1 l

( , .

'A April 20, 1998 l

2 assurance that a procedure change would not be made which inadvertently negates the previously approved licensing analysis. The staff recognized that because of the unique l operation of the control room ventilation system during an accident (the ventilation system is

! operated in the recirculation mode), with technical justification, the filters could be tested at a relative humidity of 70% rather then the existing 95%. )

CONCLUSION _S l

The staff concluded that the licensee needed to document to the staff an analysis which demonstrates the Calvert Cliff Plant's capability to meet GDC 19 in its present condition. The staff also needs the licensee to document the basis for delaying control room repairs until _

December 1999. The staff has requested a response to the testing requirements for the efficiency of the charcoal filters and how the requirements would be controlled. Finally,

! clarification is required as to whether, for a main steam line break accident, the reactor trip, turbine trip and loss of off site power are assumed to occur concurrently.

The licensee indicated they would be responding by letter shortly to the accident analysis issues raised in the March 30,1998, request for additional information and also to the sequence of shutdown during a main steam line break accident. For the charcoal filter and other issues, the licensee will consider the staff's views and provide a response later.

Original Signed by:

Guy S. Vissing, Senior Project Manager Project Directorate 1-1 Division of Reactor Projects.1/11 1 Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosures:

1. List of attendees i

2. BG&E presentation materials  !

3. NRC staff concept of CR ventilation system cc w/encts: See next page l l DOCUMENT NAME: G:\CC1-2\040798.MTS To recilve a copy of this document. Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with l

ctt?chment/ enclosure "N"= No copy .

! OfflCE PM:PDI-1 lE LA:PDI11)( l D:PDI 1 ggjl3 l l l

(*AME CVissing:lec 2 Stitt f SBeJwa /' ' W DATE 04//y/98 Aff 04/l W 98 04/ 1 0/98 04/ /9s 04/ /98 Official Record Copy