summary of the november 15, 1999, meeting regarding ... · nuclear regulatory commission...

tA UNITED STATES NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

December 2, 1999

LICENSEE: Baltimore Gas and Electric Company

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

SUBJECT: SUMMARY OF THE NOVEMBER 15, 1999, MEETING REGARDING CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 RE: STEAM GENERATOR REPLACEMENT PROJECT (TAC NOS. MA6819 AND MA6820)

On November 15, 1999, the Nuclear Regulatory Commission (NRC), and Baltimore Gas and Electric Company (BGE/licensee) and their contractor, Steam Generator Team (SGT), held a meeting in One White Flint North, Rockville, Maryland to discuss the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 steam generator (SG) replacement project. Enclosure 1 is a list of attendees. Enclosure 2 is a copy of the viewgraphs distributed at the meeting.

The purpose of the meeting was for BGE to present the status of their Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 SG replacement project.

BGE presented the fabrication status, safety analysis status and replacement activities. The staff inquired about the fabrication method and BGE and the NRC staff discussed the licensing issues and methodology relating to the safety analysis.

BGE stated that a new containment pressure/temperature calculation for the postulated main steam line break accident has been done to support SG replacement. The new analysis was done using the RELAP MOD 2 and CONTEMPT 23 computer codes. BGE stated that no unreviewed safety question was identified. The peak pressure and temperatures are below the design values. The loss-of-coolant accident analysis for containment pressure and temperature, which remains unchanged, is bounding.

The staff suggested that in the next meeting regarding SG replacement BGE make a brief presentation on the results of the licensee's evaluation of Chapter 15 safety analyses in a tabular format. This presentation should address each of the events which are either not effected by the replacement SG or they are slightly effected but reanalyses are not needed.

R, COP

December 2, 1999

-2

The replacement SGs are scheduled to be installed in Unit 1 and 2 in year 2002 and 2003, respectively. BGE plans to update the staff on its SG replacement in future meetings.

Original signed by:

Alexander W. Dromerick, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Docket Nos. 50-317 and 50-318

Enclosures: 1. List of Attendees 2. Meeting Handouts

cc w/encls: See next page

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OFFICIAL RECORD COPY

December 2, 1999

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Original signed by:





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DATE 12/ •/99 12/-.1/99 12/ /99 ' ,...- 2/ /99

OFFICIAL RECORD COPY

-2






Calvert Cliffs Nuclear Power Plant Unit Nos. 1 and 2

President Calvert County Board of

Commissioners 175 Main Street Prince Frederick, MD 20678

James P. Bennett, Esquire Counsel ' Baltimore Gas and Electric Company P.O. Box 1475 Baltimore, MD 21203

Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge 2300 N Street, NW Washington, DC 20037

Mr. Bruce S. Montgomery, Director NRM Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685

Mr. Richard I. McLean, Manager Nuclear Programs

Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401

Regional Administrator, Region F U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

Mr. Joseph H. Walter, Chief Engineer Public Service Commission of

Maryland Engineering Division 6 St. Paul Centre Baltimore, MD 21202-6806

Kristen A. Burger, Esquire Maryland People's Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631

Patricia T. Birnie, Esquire Co-Director Maryland Safe Energy Coalition P.O. Box 33111 Baltimore, MD 21218

Mr. Loren F. Donatell NRC Technical Training Center 5700 Brainerd Road Chattanooga, TN 37411-4017

Mr. Charles H. Cruse Vice President, Nuclear Energy Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657

LIST OF ATTENDEES

BALTIMORE GAS AND ELECTRIC COMPANY

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

NOVEMBER 15, 1999

NAME Alexander Dromerick Scott Stewart Getachero Tesfaye Kenneth Romney Alan Thornton Tom Kenerth Kevin Connell Mary Beth Baker Mark Ceraldi Sheri Peterson David C. Jeng Cheryl Beardslee Mark Hartzman Richard Lobel Chu-yu Liang Christine Cave

ORGANIZATION NRR/DLPM Region I BGE BGE BGE BGE SGT FTI SGT NRR/DLPM NRR/EMEB NRR/EMCB NRR/EMCB NRR/SPLB NRR/SRXB McGrew-Hill

Enclosure 1

CAL VERT CLIFFS NUCLEAR POWER PLANT UNITS 1 & 2 STEAM GENERATOR REPLACEMENT

REPLACEMENT STEAM GENERA TOR SAFETY EVALUATION REVIEW AND

PROJECT STATUS

PRESENTA TION TO THE NRC

NOVEMBER 15, 1999

Baltimore Gas and Electric Company

Fnr1nr iirn

Calvedt Cliffs Nuclear Power Plant Steam Generator Replacement Project

Baltimore Gas and Electric Company Attendees

Name A. R. Thornton K. M. Romney G. Tesfaye ---E. S. Broczkows K. J. Connell ---M. D. Ceraldi -M. B. Baker -----

T. L. Konerth----.

ki ----------mmm

ki ----------......-------

NRC Presentation November 15, 1999, Slide 2

kI. P

Title BGE Project Manager BGE Project Engineer BGE Senior Licensing Engineer BGE Senior Mechanical Engineer SGT RSG Engineering Manager SGT Lead Licensing Engineer FTI Senior Licensing Engineer BGE Senior Engineer

Calvert Cliffs Nuclear Power Plant Steam Generator Replacement Project

-. 0'

NHU P-resentation November 15, 1999, ~Slide 3

I-

Meeting Objectives

*** Present to the NRC staff an Overview of Replacement SG Safety Evaluation

S:-Update SG Fabrication Status

. °•A A-


N Agenda is •-en

** Introduction o** RSG Safety Evaluation o** NRC Submittals

oe* Fabrication Status

*.*Open Discussion *+*Closing Remarks

A. R. Thornton

K. J. Connell

G. Tesfaye

K. M. Romney

All Attendees

A. R. Thornton


a


N,!p Functional Relationships

NRC Presentation November 15, 1999, Slide. 5

Calved Cliffs Nuclear Power Plant Steam Generator Replacement Project

"RSG Safety Evaluation Overview

"• Draft Licensing Report (complete)

"* Final Licensing Report

*. *RSG 50.59

**. Updated Licensing Report (Unit 1)

*. Updated Licensing Report (Unit 2)


July 1999

May 2000

Jan 2001

April 2002

April 2003

'I'A

AP AN


IOCFR50.59 Scope


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Review Process

o. Review each accident and identify: > the acceptance criteria

> the critical parameters that affect the approach to the acceptance criteria

o:o Compare the OSG and RSG characteristics

o* Could use of the RSG adversely affect the approach to an acceptance criterion?

> No.. .UFSAR remains bounding > Yes.. .Additional evaluation required

*o Are all acceptance criteria met? > Yes.. .Document evaluation in UFSAR

> No...USQ ** All documents reviewed I approved by SGT & BGE


N

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Steam Generator Comparison y Original Vs Replacement

o*. RSG Design >Tubing will be Alloy 690 with reduced wall

thickness

>UA within 4% of current SG >RCS volume decrease of 26 ft3 (0.25%) >Secondary-side inventory within 2% at

normal operating level

>Small weight and center of gravity changes


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N?,,..,Steam Generator Comparison •/ Original Vs. Replacement

•o RSG Design >RCS operating temperatures unchanged >RSG has 1.9 ft2 integral flow restrictor >RCS flow resistance will decrease slightly Alncrease secondary side design pressure

to be equal to the steam piping

HGENRC Presentation November 15, 1999, Slide 10NRC

Presentation

November

15, 1999, Slide

10

i *l ,, im


Comparisons of SGRPs

* Millstone - 2

l3 St. Lucie

E D. C. Cook- 2

l D. C. Cook- 1i

a Salem

D Ginna o '-oGuire/Catawba

I Byron/Braidwood

* Calvert Cliffs

-20.0% -10.0% 0.0% 10.0% 20.0% 30.0% 40.0%

% Change From Original

NRC Presentation November 15, 1999, Slide 11AMPAP:CAw

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Replacement Steam Generator Safety Analysis

**.Impact of RSG on Safety Analysis >Overall, RSG is very similar to current SG

>No significant impact on safety analysis



",••Replacement Steam Generator New Analysis

**oMSLB Containment Response )Reanalyzed MSLB containment Response

>Current licensing basis is DEG break with 20% moisture carry-over

>New analysis incorporates integral flow restrictor (1.9ft2)

>No credit taken for moisture carry-over



"Replacement Steam Generator New Analysis

**oMSLB Containment Response (cont.) >Methodologies have been approved for

PWR use

>Peak Pressures & Temperatures Below Design

>No USQ identified



••Replacement Steam Generator New Analysis

*.** Loss of Electric Load

>Reanalyzed LOEL for peak secondary pressure response

AIncrease to the SG design pressure from 1000 psia to 1015 psia

>Secondary pressure upset limit is 110% of design pressure

>Peak secondary side pressure is below upset limit

>Not USQ


9


- Activities Requiring NRC Review and Approval

:.*Technical Specification Revisions

o*oASME Code Relief Requests

**.No USQs are Anticipated

-**All Submittals will be made at least I year prior to replacement outage


S9


Technical Specification Revision

o**SG Level References > Current SG levels are referenced with respect to

the feed ring elevation

> SG level set points are not expected to change relative to % span

>Since feed ring elevation is lower, editorial change is needed

o* SG Repair Options.



,ASME Code Relief Requests

* :.Code Case N-20-4 ** *Code Case 2142-1

• **Code Case 2143-1*:*Other Code Cases as Required


P


Fabrication Status

:**Steam Generators ,oTubing *.*Audits and Assessments



RSG Fabrication Schedule

'qN3GE - Calvert Cliffs Replacement Steam Generators - FarticatOn Schedule Sumrbmary

Bgabcock & Wilcox Canada201•

82 0

y - 9 A

72 I

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p

.. p P.4�a

I732


achining Divider Plate for RSG 3


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--Divider Plate Welded into RSG 2


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Machining of Cone Handholes and Inspection "Ports in RSG I


, , . •


achining of Cone Handhole in RSG 1


a0

a AP

p :4JI AP :CA,10


\.team Generator Base Support Pieces


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"Lifting Lugs inside Secondary Cone

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II *LJ


4 Primary Head Loading in Seattle


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mitomo Tube Manufacturing Process

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L NOT WRIOG- I

COLD ROLLIG TUES


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I ,,,,EA ,,,• TRAMN I ,,, .USTL CODOWN, MYRSAI TEST" I="' FINAL '''brL'PI

AP

JAND -&


Audits and Assessments

o*. Non-Conformance Control - August 1999 > No findings, five recommendations, one observation

**ooNUPIC - QA Program - September 1999 (draft) > Two Findings

+** Procurement Control - November 1999 4.°2000 Preliminary Audit Plan:

> Vendor Control

> Process Control, Clean Room Activities, Foreign Material Control

> Detrimental Materials Control


I U


ATBGE-NRC Meeting Schedule

*.*Project overview meeting (July 29,1998) o* SG Fabrication QA/QC review and project

status meeting (April 28, 1999) .** Replacement SG safety evaluation review

.meeting (November 15, 1999) o*o Pre-installation meeting Unit I (Spring 2002) *.*Post installation meeting Unit 1(Fall 2002) **oPre-installation meeting Unit 2 (Spring 2003) +. Post Installation meeting Unit 2 (Fall 2003) ***Other meetings as needed


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