ML20249A927

Summary of 980604 Meeting W/Licensee in Rockville,Md to Discuss Replacement of Svc Water Heat Exchanges During Spring 1999 Refueling Outage on Unit 2.List of Attendees & Licensee Agenda Encl

ML20249A927
Person / Time
Site:	Calvert Cliffs
Issue date:	06/16/1998
From:	Dromerick A NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9806190138
Download: ML20249A927 (15)

Text

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.-- . June 16, 1998 LICENSEE: B;ltimore G:s End Electric Comp:ny FACILITY: Calvert Cliffs Nuciscr Power Plant, Unit N:s.1 cnd 2

SUMMARY

OF THE JUNE 4,1998, MEETING REGARDING CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 - REPLACEMENT OF SERVICE WATER HEAT EXCHANGERS

- On June 4,1998, the U.S. Nuclear Regulatory Commission (NRC) staff held a meeting at the NRC Headquarters in Rockville, .'Aaryland, with representatives from Baltimore Gas and Elactric

! Company (BGE/ the licensee) for Calvert Cliffs, to discuss the replacement of the service water heat exchangers during the spring 1999 refueling outage on Unit 2. The list of meeting attendees is included as Enclosure 1. Enclosure 2 is a copy of the licensee's agenda.

In order to replace the service water heat exchangers during the Unit 2 refueling outage, BGE discussed several approaches for establishing plant conditions that would support safe shutdown operations. BGE indicated that the best approach was to temporarily modify the SRW system by (1) cross connecting SRW Subsystem 12 to DG2A, (2) cross connecting SRW Subsystem 11 to SFPC Subsystem 12, and (3) establishing a temporary cooling system to DG2B ths,t will not be safety-related, seismically qu .lified or tomado-mis.sile protected. (See Figures 1 and 2 in

- Enclosure 2). BGE indicateo that this approach provides reliable defense in depth by sustaining the availability of both the Unit 2 normal safety-related diesel generators without over reliance on the station's blackout diesel (DGOC); does not affect the indepcadent nature of each unit's subsystems or channels; and supports operability of both trains of shutdown cooling to the shutdown unit whenever the steam generators are unavailable and fuel is in the reactor vessel.

BGE indicated that the temporary modification constitutes an unreviewed safety question and will require a license amendment. BGE further indicated that the license amendment will be submitted to the NRC staff by mid-July 1998. Original Si n.ed Alexander W. Dro'menck, S0nior kroj;ect Manager Project Directorate 1-1 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation Docket No. 50-317

Enclosures:

1. List of Attendees

2. Meeting Handouts l f' cc w/encls: See next page _I BM DISTRIBUTION: See next page g\

DOCUMENT NAME: G:\CC1-2\980604M. SUM To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E' .

= Copy with attachment / enclosure "N" = No copy 0FFICE PM:PDI 1 /L //)] E LA:PDI 1 M L l D: POI-1 _o l l l l NAME ADromeri6lfi g 7 SLittt F S8ajus l M ,l

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DATE 064 & /98 06/Ra/98 06//h /98 06/ /98 06/ /98 j Official Record Copy a h hN 9906190139 990616 -

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June 16, 1998 LICENSEE: B:ltimore G:s cnd Electric Comp:ny FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2

SUMMARY

OF THE JUNE 4,1998, MEETING REGARDING CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 - F.EPLACEMENT OF SERVICE WATER HEAT EXCHANGERS On June 4,1998, the U.S. Nuclear Regulatory Commission (NRC) staff held a meeting at the NRC Headquarters in Rockville, Maryland, with representatives from Ba'timore Gas and Electric Company (BGE/ the licensee) for Calvert Cliffs, to discuss the replacement of the service water heat exchangers during the spring 199g refueling outage on Unit 2. The list of meeting attendees is included as Enclosure 1. Enclosure 2 is a copy of the licensee's agenda.

In order to replace the service water host exchangers during the Unit 2 refueling outage, BGE  ;

discussed several approaches for establishing plant conditions that would support safe shutdowin j operations. BGE indicated that the best approcch was to temporarily modify the SRW system by l (1) cross connecting SRW Subsystem 12 to DG2A, (2) cross connecting SRW Subsystem 11 to SFPC Subsystem 12, and (3) establishing a temporary cooling system to DG2B that will not be safety-related, seismically qualified or tomado-missile protected. (See Figures 1 and 2 m  ;

Enclosure 2). BGE indicated that this approach provides reliable defense in depth by sustaining the availability of both the Unit 2 normal safety-related diesel generators without over reliance on the station's blackout diesel (DGOC); does not affect the independent nature of each unit's subsystems or channels; and supports operability of both trains of shutdown cooling to the shutdown unit whenever the steam generators are unavailable and fuel is in the reactor vessel.

BGE indicated that the temporary modification constitutes an unreviewed safety question and will require a license amendment. BGE further indicated that the license smendment will be submitted to the NRC staff by mid-July 1908. ed AlexanderW.briginal Simenck, S$ior krk;eet Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-317

Enclosures:

1. List of Attendees

2. Meeting Handoute.

. cc w/encis: See next page DISTRIBUTION: See next page ,

DOCUMENT NAME: G:\CC1-2%0604M. SUM To rsceive a copy of this document, indicate in the box: "C" = Copy without attachmt nt/ enclosure "E" ,

a Copy with attachment / enclosure "N" = No copy I 0FFICE PM:PDI 1 /L //Jl E LA:P0l=1,Q\L I 0: Pot 1 _ /> I I I WAME ADromer M W 7 SLittI W $8ajus J M DATE 06/s & /96 06/Ra/98 06//h /9s 06/ /98 06/ /98 i

Official Record Copy I

, ,pa car, p k UNITED STATES S NUCLEAR REGULATORY COMMISSION

• "U l WASHINGTON, D.C. 30008 4001 1

• • • • • / June 16,1998 LICENSdE: Baltimore Gas and Electric Company FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2

SUMMARY

OF THE JUNE 4,1998, MEETING REGARDING CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 - REPLACEMENT OF SERVICE WATER HEAT EXCHANGERS On June 4,1998, the U.S. Nuclear Regulatory Commission (NRC) staff beld a meeting at the NRC Headquarters in Rockville, Maryland, with representatives from Baltimore Gas and Electric Company (BGE/ the licensee) for Calveil Cliffs, to discuss the replacement of the service water heat exchangers during the spring 1999 refueling outage on Unit 2. The list of meeting attendees is faciudad as Enclosure 1. Enclosure 2 is a copy of the licensee's agenda.

In order to replace the service water hsat exchangers during the Unit 2 refueling outage, BGE discussed several approaches for establishing plant conditions that would support safe shutdown operations. BGE indicated that the best approach was to temporarily modify the SRW system by (1) cross connea, ting SRW Subsystem 12 to DG2A, (2) cross connecting SRW Subsystem 11 to SFPC Subsystem 12, and (3) establishing a temporary coo!ing system to DG2B that will not be safety-related, seismically qualified or tomado missile protected. (See Figures 1 and 2 in Enclosure 2). BGE indicated that this approach provides reliable defense in depth by sustaining the availability of both the Unit 2 normal safety-related diesel generators without over reliance on the station's blackout diesel (DGOC); does not affect the independent nature of each unit's subsystems or channels; and supports operability of both trains of shutdown cooling to the shutdown unit whenever the steam generators are unavailable and fuel is in the reactor vessel.

BGE indicated that the temporary modification constitutes an unreviewed safety question and will require a license amendment. BGE furtherindicated that the license amendment will be submitted to the NRC staff by mid-July 1998.

A i

Alexander W. Dromerick, Senior Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-318

Enclosures:

1. Ust of Attendees

2. Meeting Handouts cc w/ enc ls: See next page i I

l

0 #

~

Calvert Cliffs Nuclear Power Plant

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

President Mr. Joseph H. Walter, Chief Engineer Ca! vert County Board of Public Service Commission of Commissioners Maryland 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 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 Trowbndge Patricia T. Bimie, Esquire 2300 N Street, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 ,

Mr. Bruce Montgomery, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatell '

1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Chattanooga, Til 37411-4017 Resident inspector .

clo U.S. Nuclear Regulatory Mr. Chasies H. Cruse )

Commission Vice President - Nuclear Energy P.O. Box 287 . Baltimore Gas and Electric Company-St. Leonard, MD 20685 Calvert Cliffs Nuclear Power Plant

. 1650 Calvert Cliffs Parkway Mr. Richard I. McLean, Manager Lusby, MD 20657-4702 Nuclear Programs Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 .

~ Anaapolis, MD 21401 l Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road 1

' King of Prussia, PA 19406 r.

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' Meeting Summary Distribution Dated: June 16, 1998 F LICENSEE: ' Baltimore Gas and Ele Company -

FACILITY: Calvert CliNs Nuclear Power Plant, Unit Nos.1 and 2 GUBJECT:

SUMMARY

OF THE MARCH 26,1998, MEETING REGARDING THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO 2 - REPLACEMENT OF SERVICE

. WATER HEAT EXCHANGERS g-Mail (w/ encl 1) Hard Copy (w/all encls.)

S. Collins /F. Miraglia (SJC1/FJM) 6 FO-B. Boger (A) (BAB2) ~ PUBLIC J. Zwolinski (A) (JAZ) - PDI-1 R/F-S. Bajwa (SSB1) A. Dromerick S. Little (SLL) OGC T. Martin (SLM3) ACRS V. Ordaz (VLO)

J. Tatum (JEl1) ,

C. Hohl, Region I (CWH) cc: Licensee & Service List B. McCabe (BCM) a' ,

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Meeting Summary Distribution: Dated: June 16, 1998 LICENSEE: Baltimore Gas and Electric Company FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2

SUMMARY

OF THE MARCH 26,1998, MEETING REGARDING THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 - REPLACEMENT OF SERVICE WATER HEAT EXCHANGERS E-Mail (w/ encl.1) tiard Copy (w/all encis.)

S. Collins /F. Miraglia (SJC1/FJM) CD535iFN3 B. Boger (A) (BAB2) PUBLIC J. Zvcolinski(A) (JAZ) PDI-1 R/F S. Bajwa (SSB1) A. Dromerick S. Little (SLL) OGC T. Martin (SLM3) ACRS V. Ordaz (VLO)

J. Tatum (JET 1)

C. Hehl, Region I (CWH) c0: Licensee & Service List B. McCabe (BCM)

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l LIST OF ATTENDEES BALTIMORE GAS AND ELECTRIC COMPANY l CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 AND 2 JUNE 4,1998 Name Organization Alexander W. Dromerick NRR/DRPE/PDI-1 Timothy R. Lupold BGE/ASEU Steve Looper BGE/ASEU Jeff Stone BGE/Reliabi!ity Benjamin Scott BGE/MEU Glen S. Joy BGE/ OPS Bemie Rudell BGE/ Projects Pat Furio BGE/ Licensing Richard Buttner BGE/EEU Vonna Ordaz NRR/DSSA/SPLB James Tatum NRR/DSSA/SPLB l

l 1

Enclosure 1

5 ',.

INFG dMATIONAL EXCHANGE MEETING June 4,1998 TEMPORARY PLANT CONDITIONS TO SUPPORT MAJOR SERVICE WATER SYSTEM IMPROVEMENTS DURING THE CALVERT CLIFFS UNIT 21999 REFUELING OUTAGE l

l Enclosure 2

REASON FOR TEMPORARY LICENSING AMENDMENT During the 1999 outage the Unit 2 SRW System will be mmoved from service to mplace both shell and tube heat exchangers with 4 new plate and frame heat exchangers.

Unit 2 will be in Mode 5 and 6 during the mplacement - both trains of the SRW System will be mstomd to support normal operational mquimments befom m-entering Mode 4.

Although Technicel Specifications mquire only one EDG in Mode 5 and 6, our plant practice ror defense in depth and shutdown safety is to maintain two EDGs available for various conditions during Modes 5,6 and defueled operations.

Temporary Alterations that will provide for the reliable availability of both normal Unit 2 EDGs may msult in an inemcse in the probability of occurrence of a malfunction previously evaluated in the SAR which constitutes an Unreviewed Safety Question (UsQ).

^. .

BACKGROUND Baseline performance testing, in msponse to GL 89-13, identified available heat duty margin in the service water system was low mquiring extensive l modeling, close monitoring, and high maintenance to pmclude challenges to operations.

l A major modification was launched to significantly incmase this system's thermal margin by mplacing the 2 shell and tube heat exchangers per unit 3 with 4 plate and frame heat exchangers per unit. 1 The Unit I heat exchangers wem successfully replaced during the 1997 mfueling outage.  ;

Several approaches were evaluated to best establish plant conditions that would support safe shutdown operations while replacing the Unit 2 service water heat exchangers.

The approach selected pmvides mliable defense in depth by sustaining the availability of both Unit 2 normal safety related diesel generators without over aliance on the station's blackout diesel (DGOC).

The approach does not affect the independent natum of the individual unit's subsystems or channels and supports operability of both trains of shutdown cooling to the shutdown unit whenever steam generators am unavailable and fuel is in the vessel.

A risk assessment of the temporary plant configuration proposed to support service water heat exchanger uplacement concludes the risk is low and comparable to many on-line maintenance activities.

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' NATURE OF UNREVIEWED SAFETY OWSTION Cross-Connection'of DG2A to SRW Subsystem 12:

e. Failum of a DG2A SRW control valve in the open position may usult in insufficient SRW flow to DG1B. This inemases the pmbability of a malfunction of DG1B.

• Failum of a DG1B SRW contml valve in the open position may msult in insufficient SRW flow to DG2A. This inemases the pmbability of a malfunction of CGZA.

• Although type of malfunction is no diffemnt, the probability of malfunction of DG2A may be inemased because the reliability of SRW cooling to this diesel will be dependent on a separate diesel (DG1B).

~

SFPC Subsystem 12 to SRW Subsystem 11:

• The mliance on two diesel generators after a loss of offsite power to  !

accomplish the SFPC Subsystem 12 function .may incmase the probability of a malfunction of SFPC Subsystem 12.

DG2B Temporary Cooling System:

• Because the temporary cooling system will nbt be fully SR, seismic, or tornado-missile protected, the pmbability that DG2B may. fail to function due to a loss of cooling water resulting fmm a seismic event or tornado damage is incmased.

• Because the temporary cooling piping will be added in the DG2B room,

.this activity may incmase the probability of a flooding event in the DG2B mom.

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l RISK ASSESSMENT l

TEMPORARY ALIGNMENTS FOR SRW MODIFICATIONS APPROACH e Modified the base PRA to reflect the new configuration, including the temporary cooling tower. Base PRA analyzes intemal, fire, seismic and high wind events.

e Qualitatively assessed shutdown risk.

KEYINPUTS AND ASSUMPTIONS e EDG 2A will be available during reduced inventory operations.

• Temporary alignment occurs over a 40 day duration a Service Water Header 12 provides cooling to both EDG IB and 2A.

• The installed cooling tower for DG 2B is not seismically rugged.

• Hurricane or Tornado winds fail the cooling tower for EDG 2B.

RESULTS e Instantaneous at-power risk increase is low for Unit 1.

• Curn.41ative at-power risk is comparabl'e to many on-line maintenance activities. !

• Instantaneous shutdown risk increase is assumqd to be comparable to the at-power risk increase for Unit 1.

. . The temporary cooling tower prevents the risk increases associated with an extended outage of EDG 2B (as allowed by Technical Specifications).

l

s BGE REPRESENTATIVES l

Bernie Ru dell ........................................................... Project Management Tim Lu pold........................................................... Auxiliary Systems Unit Steve Imper......................................................... Auxiliary Systems Unit Rich Buttner.................................................. Electrical Engineering Unit Ben Scott.................................................... Mechanical Engineering Unit i

Jeff Stone .............'......................................... Reliability Engineering Unit j 2

Glenn Joy..................................... Operations Maintenance Coordinator Pat Furio ....................................................... Nuclear Regulatory Matters l

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