ML20216J941

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Summary of 970903 Meeting W/Baltimore Gas & Electric in Rockville,Md Re Calvert Cliffs Nuclear Power Plant,Units 1 & 2,service Water Modifications.List of Attendees & Copy of Viewgraphs Distributed at Meeting Encl
ML20216J941
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/10/1997
From: Dromerick A
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9709180155
Download: ML20216J941 (45)
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Text

,f.....% SA-3/7 3/f 9

y* 1 UNITED STATES

" I NUCLEAR REGULATORY COMMISSION

, WASHINGTON, o.C. 3006Ho01

\ ,,, g Septiember 10, 1997 LICENSEE: Baltimore Gas and Electric Company FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2

SUBJECT:

SUMMARY

OF SEPTEMBER 3, 1997, MEETING REGARDING CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT N05. 1 AND 2 - SERVICE WATER MODiflCATIONS On September 3, 1997, the NRC and Baltimore Gas and Electric Company (BGE) the licensee for the Calvert Cliffs Nuclear Power Plant held a meeting in One White Flint North, Rockville, Maryland. The purpose of the meeting was to discuss the salt water heat exchanger replacement and the addition of new active components. A list of attendees is included as Enclosure 1.

Enclosure 2 is a copy of the viewgraphs distributed at the meeting.

The focus of the licensee's presentation during the meeting was to provide information on how they intend to modify the service water system. The two existing shell and tube salt water heat exchanges will be replaced with four new plate and frame heat exchangers (PHEs) having increased thermal performance capability.

The materials chosen for the new PHEs (Titanium for the plates and EPDM for and the method by which the PHEs are assembled, provide deterrence to gaskets) the eros ion / corrosion problem that has damaged the existing heat exchangers. i The salt water and service water piping configurations will be modified as necessary to allow proper fit-up to the new components. A flow control scheme I to throttle salt water flow to the heat exchangers and the associated bypass lines will be added. Salt water strainers with an automatic flushing arrangement will be added upstream of each heat exchanger. The majority of the physical work associated with this modification is restricted to the service water pump room. The licensee indicated that the proposed  !

modification provides an overall gain in nuclear safety by increasing heat exchanger capacity, reducing fouling, providing additional flexibility to the operator and reducing maintenance requirements.

The licensee indicated that they performed a 50.59 Safety Evaluation and determined that (1) The new design and com>onents are consistent with the applicable codes ar.c standards governing tie original structures, systems, and '/

components and (2) Most of the new components are within the existing licensing basis and do not involve an unreviewed safety question. These components are the heat exchangers, piping, and valve design. However, the [' g licensee indicated that the adoition of active components introduced the potential for new equipment ma' functions and was determined to be an unreviewed esfety question. epecifically, the unreviewed safety question was focused on the automatic fle.hing strainers and the active control valves, p"M Mb f?C RM CEE B COPY

  • s, s 32 IILill! ,Illjlll@ll

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i As a result of the detailed discussion, we advised BGE that they should consider revising the technical specifications to address the modified service water system.

BGE indicated that they must receive approval of the unreviewed safety question by October 31, 1997, in order to proceed with the modification.

The staff indicated that we will consider BGE's request.

Sincerely, f "*C ddt' Alaxander W. Dromerick, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosures:

1. List of Attendees
2. Viewgraphs cc w/encis: See next page

4 -

l g September 10, 1997  :

2-  !

As a result of the detailed discussion, we advised BGE that they should

, consider revising the technical specifications to address the modified service '

water system.

BCE indicated that they must receive approval of the unreviewed safety question by October 31, 1997, in order to proceed with the modification.

The staff indicated that we will consider BGE's request.

Sincerely.

l ORIGINAL SIGNED BY:

Alexander W. Dromerick, Senior Project Manager Project Directorate 1-1 Division nf Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosures:

1. List of Attendees
2. Viewgraphs cc w/encis: See next page DOCUMENT NAME: G:\CCl-2\MTGSUM.9-3 To rcceive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N/" - No copy OfflCE PMtPD Q Q M [E LA;PDi*lil l DIM 9-) m I J4t6RPE A ** l l liAME ADr#Wkla4 L Slittt V AdtJI Oli&( A)

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Offici al Record Copy

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T 'Muot re Gas & Electric Company C41vart Cliffs Nuclear Power Plant Unit Nos. I and 2 c.

Ne vns Mr. Joseph H. Walter, Chief Engineer ra;tt ' evray, kaard of Public Service Commission of

% ' on &s Maryland 1' i (treet Engineering Division

WW ederick, MD 20678 6 St. Paul Centre i 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. S11 berg, Esquire Shaw, Pittman, Potts and Trowbridge Patricia T. Birnie 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. Donate 11 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road 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 St. Leonard, MD 20685 Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Mr. Richard I. McLean Lusby, MD 20657-4702 Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

' l' l

Meetina S - rw Distribution 4

[-Mail - (Enclosure 1) Hard Cony - (Encis. 1 & 2)  !

S. Collins /F. Miraglia- '9echetTFHi R. Zimmerman (RPZ) PUBLIC  !

B. Boger PDl-1 R/F A. Dromerick OGC S. Little ACRS  !

T. Martin (SLM3) i S. Stewart i C. Saadu

V. Ordaz  ;

i J. Tatum

- D. Jackson R. Giardina  !

L. Marsh G..Hubbard- i

- R. Giardino 1

- S. Chaudhary  :

8. McCabe l 4

PMNS (Moeting Announcement Coordinator) t l

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__ - _ . __ ; _ _ . . . _ , .-_...____-_a...__ . - - _ . _ - - . _ _ , _ , . . . . . - _ _ . _ . . . _ - - ~

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LIST OF ATTENDEES BALTIMORE CAS AND ELECTRIC COMPANY  !

i CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.-1 AND 2 -!

September 3, 1997 ,

NAmt Oraanization ,

Alexander Dromerick NRR/DRPE Suresh K. Chaudhary NRC/ Region !

Scott Stewart NPC/SRl/Calvert R. P. Heibel BGE B. H. Scott BGE P. G. Chabot BGE C. H. Cruse BGE

  • T. N. Pritchett BGE  !
Coretta Saadu NRR/SPLB Vonna Ordaz NRR/SPLB

i Jim Tatum NRR/SPLB Diane Jackson NRR/SPLB Robert J. Giardina NRR/TSB

Bruce Boger NRR/DRPE L. B. Marsh NRR/SPLB G. Hubbard NRR/SPLB R. Giardino NRR/TSB s

t 0

t Enclosure 1

I l CALVERT CLIFFS NUCLEAR POWER PLANT

, SERVICE WATER HEAT EXCHANGER REPLACEMENT  ;

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UNREVIEWED SAFETY i

> QUESTION -

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t LW NRC PRESENTATION SEPTEMBER 3,1997 '

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} Service Water Heat Exchangers Replacement Unreviewed Safety Question -

1

/^' Baltimore Gas and Ele crc t i

$bmpany Attendees

! "+C. H. Cruse ...... Vice President, Nuclear Energy i

l +P. G. Chabot ..... Manager, Nuclear

Engineering Deparbiient  !

l + R. P. Heibel ....... Manager, Project 1 l Management Deparhiient l + B. H. Scott ......... Sr. Engineer, Mechanical

! Engineering Unit

+T. N. Pritchett .... Director, Nuclear Regulatory  !

Matters NRC Presentation September 3,1997, Slide 2

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l Service Water Heat Exchangers Replacement Unreviewed Safety Question -

i

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' Background

./y 4

19

+ Service Water Heat Exchangers - operating -

margins unsatisfactory 4

+1nstall Plate and Frame Heat Exchangers, Unit-1 1998, Unit-21999

+Unreviewed Safety Question identified, i submitted May 1997

> Auto Flushing Strainers 1

> Control Valve Malfunctions

+ Resolution necessary (October 31,1997) for outage execution '

NRC Presentation September 3,1997, Srde 3

Service WaterHeat Exchangers Replacement Unreviewed Safety Question ,-

t _

Outline f

i +1ntroduction P. G. Chabot i 0

+ Modification Overview B. H. Scott

+USQ B. H. Scott .

+ October Response R. P. Heibel ]

+ Summary P. G. Chabot i

i NRC Presentation September 3,1997 Slide 4 l

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An Overview of the Modification and  :

Unreviewed Safety Question e

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! B. H. Scott l Sr. Engineer, Mechanical Engineering l

I Unit j

i NRC Presentation September 3,1997. Slide 5 i

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Service WaterHeat Excilangers Replacement Unreviewed Safety Question .' !

l ["x l , *y Outline of Presentation L ..

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+ Reason for the Activity '

+ Description of the Existing Systems j 2

+ Description of Modifications to the Systems

+ Review of the Safety Evaluation ji

+!dentification and Discussion of the I

i Unreviewed Safety Question 1

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l Service Water Heat Fxchangers Replacement Unreviewed Safety Question j ~

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,,x Reason y

for the Activity v

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+ Baseline thermal performance tests, in response to Generic Letter 89-13, indicated

! that the available heat duty was less than j expected due to higher levels of fouling l > Requires close monitoring and maintenance l > Challenges Operations during the summer

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> Completed extensive system modeling to validate design basis ,

+ Existing tubes are susceptible to erosion corrosion at inlet end l

l l NRC Presentation September 3,1997, S5de 7 l . .- . .

Service Water Heat Exchangers Replacement Unteviewed Safety Question .\

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Proposed Activity

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l + Replace the service water heat exchangers j with Plate and Frame Heat Exchangers to l

increase the thermal margin l +1nstall self-cleaning strainers upstream of the l Plate and Frame Heat Exchangers

! +1nstall the necessary valves piping and , ,

! controls

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NRC Presentation September 3.1997, Slide 8 t

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' Service Water System

's Ebnctions

\f + Provide cooling to: .

> Containment Air Coolers

> Diesel Generator No.1B

> Spent Fuel Pool Cooler (Isolates on Engineered Safety Feature Actuation Signal)

> Steam Generator Blowdown Heat Exchanger (Isolates on Engineered Safety Feature Actuation Signal)

> Turbine Building Loads (Isolates on Engineered Safety Feature Actuation Signal)

NRC Presentation September 3,1997, Slide 10

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) Service WaterHeat Exchangers Replacement Unreviewed Safety Question '

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, .l a" Service Water System - Summary

of Proposed Modification j

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"'%if+ Each service water subsystem will have 2 parallel Plate and Frame Heat Exchangers with manual isolation valves

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+ Service Water System will be conceptually unchanged l +1mpact on flow is negligible t' l + Service Water System functions will be l unaffected by the modification

! + Either service water subsystem remains j capable of performing the design accident j functions NRC Presentation September 3,1997 STtde 11

i Service WaterHeat Exchangers Replacement Unreviewed Safety Question

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,e/4 Saltwater System - Diagram of

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+ Provide cooling water from Chesapeake Bay

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> Service Water Heat Exchangers j > Component Cooling Heat Exchangers

> Emergency Core Cooling System Pump Room Air

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Coolers

+ Chesapeake Bay is the ultimate heat sink i

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l NRC Presentation September 3.1997, Slide 13 1

Service Water Heat Exchangers Replacement Unreviewed Safety Question

  • A j~' Saltwater System - Diagram of fMedified System o

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NRc Presentation September 3,1997. Stide 16

1 Service Water Heat Fxchangers Replacement Unreviewed Safety Question .

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Modified Saltwater System -

\ Dbscription of Operation

\ft L

+ Normal Operation j > All four Plate and Frame Heat Exchangers in operation j I

+ Accident Operation

> Either pair of Plate and Frame Heat Exchangers and the l associated Saltwater and service water subsystems can remove the full accident heat load at Bay temperatures up

! to 90 F i

l 1

NRC Presentatbn September 3,1997, Sucle 17 .

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Service Water Heat Fxchangers Replacement Unreviewed Safety Question .

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l ' Modified Saltwater System -

l 7s sy Niaintenance N

+1solate one subsystem (Limiting Condition for j Operation) - Similar to current system

! operation '

! +1solate one Plate and Frame Heat Exchanger

for maintenance leaving remainder of j saltwater and service water subsystem 1

operable l > Requires isolating one containment air cooler (Limiting l Condition for Operation)

> Leaves diesel generator in operation

> Leaves Emergency Core Cooling System in operation

> Reduced overall risk and unavailability t

l NRC Presentation September 3,1997, STide 18 l

Service WaterHeat Exchangers Replacement Unreviewed Safety Question .!

n

! Summary of Proposed l N galtwater Modification l 'sy?'

l + Each saltwater subsystem will cool two

! parallel Plate and Frame Heat Exchangers

+ Heat exchangers have significantly increased thermal capacity i + Strainers are installed immediately upstream

! of each Plate and Frame Heat Exchanger to

reduce macrofouling l + Bypass line is installed to allow efficient

, pump operation 4

NRC Presentation September 3,1997. Slide 19 i

i Service Water Heat Exchangers Replacement Unreviewed Safety Question '

.i i

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  • Summary of Proposed l

! 's%d Khltwater Modification Ry#

j + Alternate saltwater discharge path will be j retained c

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+Added alarms and indications 1 + Concurrent refurbishment / replacement of j

saltwater chemical addition system

+All system design functions are still provided

+ Either saltwater subsystem is capable of i

performing the design accident functions l

i NRC Presentation September 3,1997, Shde 20 l

Service Water Heat Exchangers Replacement Unreviewed Safety Question '

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10 CFR 50.59 Safety Evaluation and identification of an j Unreviewed Safety Question I

i-NRC Presentation September 3,1997, Slide 21

Service WaterHeat Exchangers Replacement Unreviewed Safety Question .

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i 50.59 Safety Evaluation

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+The new design and components are consistent with the applicable codes and standards governing the original structures, i

4 systems, and components i

' +Most of the new components are within the existing licensing basis and do not involve an Unreviewed Safety Question i

> Heat exchangers i

> Piping l > Valve design i

NRC Presentation September 3,1997, Slide 22 i

Service WaterHeat Exchangers Replacement Unreviewed Safety Question .

4 50.59 Safety Evaluation g/

  1. r Either saltwater and service water subsystem can remove the full required accident heat load

> No single failure will remove both subsystems from operation ,

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Service Water Heat Exchangers Replacement Unreviewed Safety Question -

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i kh' 5.0.59 Safety Evaluation y#' .

+ Modification provides an overall gain in '

nuclear safety by:

> Increasing heat exchanger thermal capacity

> Reducing fouling

> Providing additional flexibility to the operator

> Reducing maintenance requirements  !

I i

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NRC Presentation September 3,1997, Slide 24 i

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Service Water Heat Exchangers Replacement Unreviewed Safety Question

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,,,k gnreviewed Safety Question

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+The addition of active components introduced l the potential for new equipment malfunctions l and was determined to be a Unreviewed l Safety Question

+Specifically, the Unreviewed Safety Question 1 is focused on: j

> Auto Flushing Strainers

> Active control valves i

= Heat exchanger saltwater throttle valves

= Saltwater bypass control valves  !

i NRC Presentation September 3,1997, Slide 25 1

Service Water Heat Exchangers Replacement Unreviewed Safety Question

~

4

'Unreviewed Safety Question -

% pUto Flushing Strainers

+ A strainer will be installed at the saltwater ~

inlet of each Plate and Frame Heat Exchanger

]

+The selected strainers are conceptually similar in operation to safety-related strainers

( used in raw water systems at other nuclear ,

i facilities  !

I I

NRC Presentation September 3,1997, Slide 26

Service Water Heat Exchangers Replacement Unreviewed Safety Question -

^ _

""Unreviewed Safety Question -

~

\% ,/ $Uto Flushing Strainers

+ Potential-strainer malfunctions j > Failure of the flushing valve

> Failure of the diverter valve

> Clogging of the strainer I

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' i NRC Presentation September 3,1997, Slide 27

Service WaterHeat Exchangers Replacement Unreviewed Safety Question -

s . _ . .

U

~ Unreviewed Safety Question -

Gibntrol Valve Malfunctions

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+Three active control valves are installed on .

each subsystem:

> Plate and Frame Heat Exchanger saltwater throttle valves

> Plate and Frame Heat Exchanger saltwater bypass valve

' + Valves are identical in design to those currently installed in saltwater system; controllers are similar to those used in other safety-related applications i

NRC Presentation September 3,1997, Slide 28 i

^

, Service Water Heat Exchangers Replacement Unreviewed Safety Question A i i

'Unreviewed Safety Question -  ;

Gbntrol Valve Malfunctions f,:

+*+ Control valves are designed to fail in the

! " safe" position on loss of power or air

> Saltwater bypass valve fails shut to ensure full flow to Plate and Frame Heat Exchanger

> Plate and Frame Heat Exchanger saltwater throttle valve fails open to ensure continued flow to heat exchanger

+ Potential single failures- I

> Saltwater bypass valve fails shut

> One Plate and Frame Heat Exchanger saltwater throttle valve fails open '

NRC Presentation September 3,1997, Slide 29 i

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Service Water Heat Exchangers Replacement Unreviewed Safety Question

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  • 1Unreviewed Safety Q uestion -

%es  ?

4,Gbntrol Valve Malfunctions

+ Worst case: all three control valves on one l

J train fail simultaneously '

> Both Plate and Frame Heat Exchanger saltwater throttle  !'

valves fail open l > Saltwater bypass valve fails shut i

1 i

l NRC Presentation Sep* ember 3,1997, Slide 30

  • Service Water Heat Exchangers Replacement Unreviewed Safety Question '.'

s

. J *Significant Hazards adonsiderations l f .

L +The proposed amendment will not: ,

> involve a significant increase in the probability or consequence of an accident previously evaluated *

> create the possibility of new or different kind of accident from those previously evaluated

) involve a significant reduction in margin of safety i

+Therefore, we have concluded that this

! . proposed license amendment involves no significant hazards considerations t NRC Presentation September 3,1997, Slide 31 l .

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Service Watar H:at Exchangers Replacement Unreviewed Safety Question ~

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1998 Outage Preparation
R. P. Heibel Manager, Project Management Department NRC Presentation September 3,1997, Slide 32

Service Water Heat Exchangers Replacement Unreviewed Safety Question '

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  1. e S^1998 Refueling Outage Timeline Q.

i C U C C l

v v v v v C i , O ,!

4SS 5/96 12/96 v v v 1S7 A97 gegy 9/1ST 10/5/97 ALL MAJOR PRELtMINARY ALL DETAtLED WORK ALL MODIFICATIONS OUTAGE PROJECT ENGtNEERING SAFE INITIAL SELECTED-

, PACKAGES MODIFICATIONS SHUTDOWN SCHEDULE PLANS AND SCOPE DOC's TNITIATED. INTEGRATE DESIGN SCHEDULE OUTAGE ISSUED. ESTIMATES 4 COMPLETE. JrJ ^ COMPLETE. d

, REVIEW APPR M D SCHEDULE J l BEGINS. ISSUED.

1

" Plan the work, then work the plan."

NRC Presentation September 3,1997, Slide 33

A I . .

Service Water Heat Exchangers Replacement Unreviewed Safety Question '

m 8

f,A% Service Water Heat Exchanger

&% ^

7 project Timeline DETAILED DESIGN ANALYSIS SAFETY 4

DETA! LED EVALUADOR '"

DETAILED MANAGEMENT ENGR. BEGINS MJUOR --

REPLACEMENT DE1AtLED WORK  %^-

SCOPE. REVfEW OF MAJOR EQUIPMENT l PKG Pt.ANNING.

WIPLATE AND PROJECT PRE-OUTAGE PROJECT PLAN EQUIPMENT B1D -- --

SAFE SHUTDOWN SRW HX FRAME S'ONS F+AN AND AND FULL WORK STARTS.

ENGR SPEC. EVALUATIONS DETAILED CRITERIA AND , INTEGRATED MOD FICATION DtSTINCT FST: MATE FUNDING DEVELOPMENT AND DESIGN CONTINGENCY REQUESTED. ADVANTAGES. COMPLETED APPROVAL PCPJTAGE AND REVIEWS CONTRACTING ISSUED Eo ASUSHED

{J4G (CONT.).

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i NRC Presentation September 3,1997, Slide 34 '

6

Service WaterHeat Exchangers Replacement Unreviewed Safety Question '

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! / '1998 Refueling Outage - Service Water 1

bibat Exchanger Project Timeline

/

OPERATING AND MAINTENANCE PRE-OUTAGE WORK PROCEDURE DEVELOPMENT AND CONTINUES. REVIEW OF MAJOR EQUIPMENT SAFE SHUTDOWN RECEIPT INSPECTION. TESTING PROCEDURES CONTINGENCY PLANS AND ACCEPTANCE TESTING AND REVIEWED AND APPROVED. COMPLETE ALL TEMP. ALT. ENGINEERING DES!GN CRITERIA VERIFICATION OF OPERATOR TRAINING. PRE-OUTAGE FINALIZED. ENGINEERED SUBCOMPONENTS MATERIAL STAGING. WORK.

> < i < i < i 10/27/97 11/10/97 12/15/97 2/21/98 4/3/93 ,

OPERATIONS SAFE OUTAGE SCHEDULE S4 COMPLETED BY INDEPENDENT SRO REFUEL SHUTDOWN

SUMMARY

TAGGING REVIEW. OPERATIONS. REVIEWOF SCHEDULE OUTAGE SCHEDULE (S4) REVIEW. BEGIN RESOURCE OUTAGE SCHEDULE COMPLETE. STARTS.

MAINTENANCE WORK LEVELIZATION. LOGIC NOW COMPLETE. LOGIC REVIEWS GROUP REVIEWS. COMPLETE.

RESOURCE LEVELIZATION COMPLETE.

BEGIN LEAD CRAFT REVIEW AND FULL SITE FAMILIARIZATION.

" Outage safety and discipline must be balanced against service water i safety gains." .

NRC Presentation September 3,1997, Slide 35

Service Water Heat Exchangers Replacement Unteviewed Safety Question '

A g

/ h* Integrated Safety Review 3

t psrOCOSS '

  • INTEGRATED FINAL SCHEDULE
INITIAL SCHEDULE SCHEDULE LOGIC ISSUED

~

REVIEWS =

i FEEDBACK Integrated Reviews by: i Job Path Managers Operations > Safe Shutdown Schedulers > Summary Schedule .

Responsible Maintenance Groups t

Planners

, System Engineers Project Engineers NRc Presentation September 3,1997, Slide 36

\

o Service Water Heat Exchangers Replacement Unreviewed Safety Question N\

l;

% l pre-October 1997 Options

+*+

Continue with Plate and Frame Heat

Exchanger Project j

+Retube with Low Fin Tubes l

Both options will improve thermal margm.

However, the plate and frame heat exchanger is the best option for installation in 1998.

l I

l NRC Presentation September 3,1997, Slide 37

~ ~

Service WaterHeat Exchangers Replacement Unreviewed Safety Question ~

,Q

, \,j?gpnclusions '

+ Outage safety and discipline must be -

balanced against service water safety gains

+A decision is needed by October 31,1997 to support Baltimore Gas and Electric Company's proper safe shutdown planning l + Dual-path planning is not realistic i

NRC Presentation September 3,1997, Slide 38

Service Water Heat Exchangers Replacement Unreviewed Safety Question X ,

, Summary i ~%

4 f

+ Baltimore Gas and Electric Company wants Plate and

[

Frame Heat Exchangers i PHEs)  !

> Current limited margin is a safety matter j > Best long-term fix  !

+ Current planning supports Unit 1 Outage (April-May,98)

+ Unreviewed Safety Question identified and submitted in May 1997 '

> USQ of limited scope i = Auto Flushing Saltwater Stramer j

= Saltwater Control Valve Malfunctions

> PHEs, Piping, Valves, Within Licensing Bases

+ PHEs a significant nuclear safety improvement l

, NRC Presentation September 3,1997, Slide 39 I

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