ML20132B097

Summary of 961113 Meeting W/Bg&E in Rockville,Md Re Plant, Unit 2 SG Insp Scope During Spring of 1997.List of Attendees & Matl Used in Presentation Encl

ML20132B097
Person / Time
Site:	Calvert Cliffs
Issue date:	12/11/1996
From:	Dromerick A NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9612170050
Download: ML20132B097 (24)

Text

._.- _._. _ _ . _ _ . _ _ . _ . _ _ _ . _ _ _ _ . _ . _ . _ _ _ . . . _ _ _ _

LICENSEE:. Baltimore Gas and Electric Company December 11, 1996

FACILITY

'Calvert Cliffs Nuclear Power Plant

SUMMARY

OF NOVEMBER 13, 1996, MEETING REGARDING CALVERT CLIFFS l UNIT 2 STEAM GENERATOR INSPECTION SCOPE DURING SPRING 0F 1997

.L On November 13, 1996? the NRC and the 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' proposed scope of steam generator tube inspections during the Calvert Cliffs-Unit'No. 2' refueling outage during the spring of 1997. A list

'of meeting attendees is_ included,as Enclosure 1. Enclosure 2 is a copy of the c .viewgraphsidistributed at the meeting.

v -

=, ,

The focus' bf the licen'see's presentat' ion during the meeting was a discussion L ,'of the steam. generator tube inspecti.on scope planned for the upcoming outage.

4

' In addition, the licensee presented in-situ pressure testing plans, results of z

l thermal-hydraulic analyses using the ATH0S computer code to establish the freespa'n plus po~ Int probe inspection scope, and plans for tube pulls. The NRC-staff requested the licensee outline the eddy current data analysis practices for rotating probe data ,in the upcoming and most recent inspection outages.

,Thelicensee stated that *in the spring 1995 refueling outage, eddy current

, data'analy'sts were required to review both the strip charts and the C-scan

.' - plots for the plus point 1 data. This practice would be continued in the outage scheduled fer spring 1997.

ThelicenseeindEatedthattheyintendtokeeptheNRCstaffinformed regarding any future plans:concerning steam generator tube inspections. )

l Sincerely,

/S/

Alexander W. Dromerick, Sr. Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1

Docket Nos. 50-317 and 50-318

Enclosures:

1. List of meeting attendees

2. Viewgraphs cc w/encls: See next page i

NRC FILE CENTER COPY DOCUMENT NAME: G:\CCl-2\111396.MTS

~

To receive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" - No copy OFFICE PMPCJ-J d ) lE LA P01-1 N l 0: POI 1 f[M l l l NAME $h@ i N rst >

$littlef J Stajwa /7 "

• A DATE %a j '/% -

12/ j ( /% 12/} /% 12/ /% 12/ /%

9612170050 961211 ~ficial Record Copy PDR ADOCK 05000317 P PDR

_. . _ , . .i - .. -. . - _ - _- -

1 M ato i

p  % UNITED STATES

, , s j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20eedL4001 l g i

%,*****p*,g December 11, 1996 l

l LICENSEE: Baltimore Gas and Electric Company i FACILITY: Calvert Cliffs Nuclear Power Plant I

SUBJECT:

SUMARY OF NOVEMBER 13, 1996, MEETING REGARDING CALVERT CLIFFS UNIT 2 STEAM GENERATOR INSPECTION SCOPE DURING SPRING OF 1997 i

l On November 13, 1996, the NRC and the 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 i to discuss the proposed scope of steam generator tube inspections during the Calvert Cliffs Unit No. 2 refueling outage during the spring of 1997. A list

of meeting attendees is included as Enclosure 1. Enclosure 2 is a copy of the i viewgraphs distributed at the meeting.

The focus of the licensee's presentation during the meeting was a discussion i of the steam generator tube inspection scope planned for the upcoming outage.

) In addition, the licensee presented in-situ pressure testing plans, results of

thermal-hydraulic analyses using the ATH0S computer code to establish the

. freespan plus point probe inspection scope, and plans for tube pulls. The NRC

! staff requested the licensee outline the eddy current data analysis practices

for rotating probe data in the upcoming and most recent inspection outages.

l The licensee stated that in the spring 1995 refueling outage, eddy current data analysts were required to review both the strip charts and the C-scan plots for the plus point data. This practice would be continued in the outage j scheduled for spring 1997.

, The licensee indicated that they intend to keep the NRC staff informed

] regarding any future plans concerning steam generator tube inspections.

I Sincerely, s

Ab(AA'.h lexan r W. Dromerick, Sr. Project Mahager Project Directorate I-1 1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosures:

1. List of meeting attendees

2. Viewgraphs cc w/encls: See next page l

i

4, p, ,

.,-j

_ l t) >

> c '

~!j .

j ,

. . .. .s v

-- Meetina Summary Memorandum. ,

HARD COPY w/all enclosures

~

Docket. File

. PUBLIC' r PDI-1 R/F- I 4

OGC ACRS E-MAIL w/ enclosure 1 ,

. F. Miraglia/A. Thadani (A) J

! R. Zimmerman  ;

i S. Varga l J. Zwolinski  !

S. Bajwa A. Dromerick S. Little l E. Jordan (JKR) 1 W. Dean L. Doerflein P. Rush E. Sullivan J. Tsao S. Coffin M. Modes, Region I ,

l 1

1 1

s 1/ $

i g, , . \

j. * ~

q &

• ' e' y kt F

"}'

} . $

5 L ,e*

160059

A V

l

+

Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. I and 2 cc: i

! President Mr. Joseph H. Walter, Chief Engineer

! Calvert County Board of Public Service Commission of i Commissioners Maryland

, 175 Main Street Engineering Division

! Prince Frederick, Md 20678 6 St. Paul Centre Baltimore, MD 21202-6806 j D. A. Brune, Esquire General Counsel Kristen A. Burger, Esquire l Ba.timore Gas and Electric Company Maryland People's Counsel i P.O. Box 1475 6 St. Paul Centre i Baltimore, MD 21203 Suite 2101 Baltimore, MD 21202-1631

! Jay E. Silberg, Esquire Shaw, Pittman, Potts and Trowbridge Patricia T. Birnie, Esquire j 2300 N Street, NW Co-Director ,

i Washington, DC 20037 Maryland Safe Energy Coalition j

P.O. Box 33111 Mr. Terrence J. Camilleri, Director, Baltimore, MD 21218 NRM j Calvert Cliffs Nuclear Power Plant Mr. Larry Bell j 1650 Calvert Cliffs Parkway NRC Technical Training Center i

Lusby, MD 20657-4702 5700 Brainerd Road j Chattanooga, TN 37411-4017  !

i Resident Inspector I

! c/o U.S. Nuclear Regulatory Mr. Charles H. Cruse

! Commission Vice President - Nuclear Energy j P.O. Box 287 Baltimore Gas and Electric Company 4 St. Leonard, MD 20685 Calvert Cliffs Nuclear Power Plant l 1650 Calvert Cliffs Parkway i Mr. Richard I. McLean Lusby, MD 20657-4702 l Administrator - Radioecology >

i Department of Natural Resources

! 580 Taylor Avenue i Tawes State Office Building, B3 j Annapolis, MD 21401 Regional Administrator, Region I U.S. huclear Regulatory Commission j 475 Allendale Road King of Prussia, PA 19406 l

l l

l I

1 l

LIST OF ATTENDEES l l

MEETING WITH REPRSENTATIVEl_QE l BALTIM0RE GAS AND ELECTRIC COMPANY CONCERNING STEAM GENERATOR TUBE INSPECTION FOLLOWUP l l

CALVERT CLIFFS NUCLEAR POWER PLANT NOVEMBER 13. 1996 l

)

' NAME ORGANIZATION Alexander W. Dromerick NRR/PDI-1 Alan Thornton BGE S/G Project Craig Sly BCE Licensing Anthony Soccarino BGE NDE

, Michael E. Dobson Rockridge/FTI l Brain A. Jones Rockridge/FTI Robert F. Cole Rockridge/FTI

Craig Smith BGE/S/G PROJ. i Boyd Radford BGE/S/G PROJ. l Phillip Rush NRR/EMCB l 4

Edmund Sullivan NRR/EMCB John Tsao NRRIEMCB l i Michael Modes NRR/ Region I I

Stephanie Coffin NRR/EMCB l

d

! I Enclosure 1

Edcl65dk/ k l-l l

l i  !

I '

l i

l CAINICRT CIJFFS  !

l CKIT 2 l

1997 l

S/G OLTAGE

)

i SCOPE l

! 1 l l

! l 1

1 i

NRC PRESENTATION l I

WHITE FLINT, MARYLAND l 13 NOVEMBER 1996 i

i

Enclosure 2

\': .

STEAM GENERATOR

\

i INSPECTION TEAM

! Al Thornton S/G Project Manager l Craig Smith senior Engineer 4

l Boyd Radford senior Engineer l Anthony Saccavino NDEEngineer  !

1 Craig Sly Nuclear Regulatory Matters j Rick Coe s/o Engineer (FTI) i i

Mike Dobson NDE LevelIII(FTI)

Brian Jones s/o Task Manager (FTI)

Bob Cole site S/G Project Manager (FTI)

- - 7 f"

i .

~

i

NRC MEETING AGENDA

! i Wednesday , November 13th

! 10:00am - 12:00am i

i i

I. Introduction A.Thomton 5 min i

l ll.1997 RFO B. Radford 10 min i

i l A. S/G work scope B. Eddy current scope C. Inspection Technology M. Dobson 5 min Ill. Inspection Plan Influences B. Radford 10 min i

! A. Unit 1 1996 experience l' B. Evaluations /Modeling R.Coe 10 min C. Industry Experiences IV. Inspection Plan B. Radford 15 min A. Inspection Strategy B. Expansions Strategy C. Bounding Strategy D. Repair Strategy IV. NRC Interactions C. Smith Smin

-- ~-~ -'

a .

e

~

i Calvert Cliffs S/G's i

i Background -

i i

t CE Model 67 l - 8519 tubes per l steam generator

! - tube OD .75"

,.048 wall

! thickness

- tube material alloy

600 HT/MA t

j - recirculatingtype t 14.6 EFPY (effective full power years) t Tuor 594F (since Start up)

i l

1997RFO S/G workscope i

l Work Scope Objectives l

i j t Ensure S/G tube integrity is maintained j between inspections.

l t Operate full cycle between inspections l M.aintain a proactive approach to the j inspection plan and implementation

! t Meet NRC/ Regulatory requirements and commitments.

t Address site and industry concerns and j issues.

i t Maximize S/G performance for the next cycle.

i ~

i l

4 1

3 4

l .

1997RFO S/G workscope i

! Primary Side:

! t Eddy current examina: ion l

t Insitu pressure testing

! t Tube remova.

i j z Tube 31ugging/re3 air 1

l 1

1 i L

! Secondary Side:

t Secondary side visualins 3ection j t S/G feed-ring UT inspection.

t Steam separation system cleaning.

l. -

l 1997RFO S/G eddy current base scope l

l W

! t 100% bobbin fu111ength t 100% H/L,TTS (+ point probe) j t 20% C/L ,TTS (+ point probe)

I l t 20% U-bend (R 1&2)(+ point probe)

I t 20% Steam blanket (R 7-13)(+ point probe) l t 20% Dented support intersections

j. >5v (+ point probe)

[

! t 20% Free Span (+ point probe)

- Arc region

- Stay-dome region r-- , - - g

l l ~

, 1997RFO

\ S/GInspection Technology I

l t Probe types l

l t Pri/Sec Analysis t Pri/Sec Data Mgt l

t Remote analysis t Remote acquisition 1

l i

1 i

b . . _ .

i i

S/G Insvection Plan Influences CCNPP Unit 11996 experience c

l Free span Cracking l

j Axial indications were found in the free l span regions in both #11 and #12 steam generators. There were two distinct

] areas where the free span indications j were found; the ARC regio & the j Stay-Dome region.

l 20 % of these regions will be inspected l in #21 and #22 S/G's in the upcoming l outage.

b i

i I

l

~

l-l S/G Insoection Plan Influences

. i l CCNPP Unit 11996 experience l

l l

Drilled Support Plate l Tube Cracking l I Axial and circumferential indications were detected in the 9th solid support dented '

l intersectionsin both #11 and # 12 steam i generators.

i No crack-like indications were detected in the other solid support (10th) or any of the egg crate supports.

20% of the dented intersections will be inspected on both #21 and #22 steam generators.

4 )

l. -

l j~ S/G Inspection Plan Influences j CCNPP Unit 11996 experience i

Insitu Pressure Tests i

j Pressure testing ofindications was a valuable piece of data that demonstrated the tubing i met the structural integrity requirements

! of NRC REG. Guide 1.121.

j Insitu pressure testing will be conducted on 5-10 of the most limiting flaws l l

l I

i .

l

S/G Insvection Plan Influences

^ "

. i CCNPP Unit 11996 experience l

l l

l

[ Tube Pulls I l

l Tube pull analysis provided valuable data on l indication morphology, NDE l measurements, and the structural condition of the flaws.

1 l

1 l

l Three tubes will be removed from a S/G l and analyzed to determine the i structural condition of the detected i

flaws

.______-_-_________________-__j

S/G Inspection Plan Influences

~

l Evaluations and Modeling i

I ATHOS

?

l

- Modeled upper bundle to look for i deposit regions j - Unit 2 specific temp, press, and j plugging percent j - Results essentially as Unit 1 j Eddy Current Review

) - Reviewed Unit 2 bobbin free span j

results in low frequency range to look j for deposits e

) - Significantly fewer deposit regions

! noted for Unit 2 l

i

- Some deposits noted in low row numbers in 05H to 06H elevation

W l.

l i . ) S/G Insvection Plan Influences

^ "

l l Industry Experiences l

l Cold Leg Top Of Tube Sheet l Indications I

Other C.E. utilities have detected crack like indications at the TTS of their cold legs.

20% of the cold leg TTS will be inspected in both #21 and #22 steam generators.

l l

l

l

~

S/G Insvection Plan Influences _ .

l ' ' Industry Experiences I l l l

i l Drilled Support Plate l Tube Cracking I

l Many Westinghouse utilities have l experienced drilled support plate tube j cracking.

l 20% of the dented intersections will be l inspected on both #21 and # 22 steam l generators.

Additional intersections will be inspected during the course of the free span inspection.

-- -. . , * .m--my- -..,.y-m-

i.

i i-l . S/G Inspection Plan l Inspection Strategy I

l t Perform the 20% free span j sample of the Stay-dome and  !

l ARC regions first. This will

provide data that will define the l critical regions ofinterest. I i

i e Bobbin examinations will be .

j conducted in parallel with i

MRPC.

l.

1-S/G Inspection Plan 1

Expansion / Bounding Strategy l

l t Establish a critical area based on the initial sample results.

i t Examine 100% of critical areas i ifindications are detected.

l t Ensure allindications are bound by 5 defect free tubes.

l i

l N

l.'-

l.

l gS/G Inspection Plan l

Repair Strategy 1 l t Rolled plugs will be installed in l

all defective tubes. l

! t Welded plugs will be installed in all pulled tube locations.

t Wire roae stabilizers will be l installed in all tubes containing j circumferential l indications / defects.

i .

O

. S/G Licensing Activities i

I i

l t RCS Flo'w Recuction Submittal in January 1997 i i Needed to support Unit 2 RFO t S .eeving i Westinghouse LWS - approved (3/96) 1 ABB/CE TIG - resubmitting RAIs (11/96) l FTI Electrosleeve - submitted (8/96) i l

! t Alternate Reaair Criteria

( 1 j Free span axial-owners group task (Fall l

i 97) l TTS circumferential-follow industry l

4

-- - - - .-