ML20132F438

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Summary of 961212 Meeting W/Utils Re Control Rod Insertion Issues.W/List of Attendees & Viewgraphs
ML20132F438
Person / Time
Issue date: 12/17/1996
From: Wang E
NRC (Affiliation Not Assigned)
To: Matthews D
NRC (Affiliation Not Assigned)
References
NUDOCS 9612240258
Download: ML20132F438 (64)
v • d • e


Text

.

December 17, 1996 i

4 MEMORANDUM T0:

David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:

Egan Y. Wang, Reactor System Engineer Original Signed By:

Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Re>_etor Regulation

SUBJECT:

MEETING

SUMMARY

OF DECEMBEP. 12, 1996, REG'ARDING CONTROL R0D INSERTION ISSUES On December 12, 1996, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC).

Participants of this meeting also include representatives from Texas Utility Electric Company (TU), Carolina Power and Light, and Wisconsin Public Service. The purpose of this meeting was to provide an opportunity for SPC representatives to review and discuss control rod insertion issues.

SPC representatives i

provided an introduction and a brief description on current activities with regard to the issues.

Representatives from TV presented data for both fuels from Siemens and Westinghouse.

Most of the meeting involved presentation of proprietary information. provides a list of meeting attendees. Attachment 2 is the non-proprietary version of the presentation material. Attachment 3 is the material presented by TV representative.

Attachments: As stated cc w/att: See next page DISTRIBUTION:

See attached page Document name: 961212MT. SUM g_

rsk 0FC PGEB C,.

SC:PGEBf\\,k

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C:PG NAME EWang:sw FAkstuNcz DMatthews DATE 12////96 12/\\b/96N 12/ h96 0FFICIAL RECORD COPY 9612240258 961217 PDR ORG NRRA PDR

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osa4 9kl UNITED STATES g, e g

j NUCLEAR REGULATORY COMMISSION 1

\\,,,,,l2 WASHINGTON, D.C. 2066H001 December 17, 1996 i

i MEMORANDUM TO:

David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:

Egan Y. Wang, Reactor System Engineer Generic Issues and Environmental 4

/

Projects Branch 7

O Division of Reactor Program Management Office of Nuclear Reactor Regulation 4

SUBJECT:

MEETING

SUMMARY

OF DECEMBER 12, 1996, REGARDING CONTROL R0D j

INSERTION ISSUES

\\

On December 12, 1996, representatives of Siemens Power Corporation (SPC) met with representatives of the Nuclear Regulatory Commission (NRC).

Participants of this meeting also include representatives from Texas Utility Electric Company (TV), Carolina Power and Light, and Wisconsin Public Service. The purpose of this meeting was to provide an opportunity for SPC representatives to review and discuss control rod insertion issues.

SPC representatives provided an introduction and a brief description on current activities with regard to the issues.

Representatives from TU presented data for both fuels from Siemens and Westir.ghouse.

Most of the meeting involved presentation of proprietary information.

4 Attachment I provides a list of meeting attendees. Attachment 2 is the non-proprietary version of the presentation material. Attachment 3 is the material presented by TU representative.

i i

i Attachments: As stated i

4 cc w/att:

see next page d

NRC/SIEMENS POWER CORPORATION MEETING ON CONTROL ROD INSERTION ISSUES LIST OF ATTENDEES Dec 12, 1996 N8 tie ORGANIZATION Hansen, Leo E.

Siemens Reparaz, Adolfo Siemens Perkins, Richard Siemens Copeland, R. A.

Siemens Woodlan, Don TV Electric Cheo, Whee TU Electric Wanner, Dave Wisconsin Public Service Davis, Dan Carolina Power & Light Weiss, Eric NRC/NRR/DSSA/SRXB Conrad, H. F.

NRC/NRR/DE/EMCB Grubelich, F. T.

NRC/NRR/DE/EMEB Chatterton, M.

NRC/NRR/DSSA/SRXB Rajan,J.

NRC/NRR/DE/EMEB Wang, Egan NRC/NRR/DRPM/PGEB ATTACHMENT 1

=_-

=.

DISTRIBUTION: Mtg. Summary of December 12 Meeting with Siemens Power Corporation Dated December 17, 1996 HARD COPY Central File Public PGEB r/f R. Cooper, RI i

E. Merschoff, RII W. Alexion, RIII J. Dyer, RIV E. Wang OGC j

ACRS E-MAIL F. Miraglia A. Thadani i

R. Zimmerman T. Martin E. Jordan D. Matthews F. Akstulewicz E. Weiss H. F. Conrad M. Chatterton j

J. Rajan 3

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SIEMENS L

I NRC Meeting on Control Rod Insertion i

Siemens Power Corporation December 12,1996 l

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RAC:90-079-12/96

1 SIEMENS Meeting

Purpose:

Describe SPC Guide Tube

~

Design Process and Recent RCCA Issue I

. Demonstrates no operational guidelines needed on SPC fuel i

. SPC wants to identify the NRC issues and respond with l

generic submittal

. SPC design addresses guide tube growth, buckling, and

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mechanical compatibility with core structure

. Review of information available on recent RCCA insertion delays and SPC operational experience:

j

. shows the SPC designs maintain adequate clearance for unrestrained RCCA insertion

. conservative relative to assemblies where delays seen ucm orsum

SIEMENS Agenda i

i

. Introduction--RA Copeland

. Description of SPC Design Process--A Reparaz i

. SPC Design Validation--A Reparaz l

t

. Conclusions--A Reparaz

. Utility Activities / Reviews--Utilities Follow-on Activities--All f

SIEMENS i

Siemens Presentation on RCCA Insertion i

Compatibility for Westinghouse Reactors 3

A. Rep 6raz, Manager

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Product Mechanical Engineering Siemens Power Corporation - Nuclear Division i

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-- l

SIEMENS Outline of SPC Presentation on RCCA Insertability l

Problem Statement i

. SPC Expenence l

. SPC Design Considerations

. Manufacturing Controls I

. SPC Growth Data

. Operating Considerations

. Drop / Drag Measurement Data I

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SIEMENS Root Cause Conclusions

. The incomplete RCCA insertions observed at Wolf Creek have been caused by

[

excessive compressive loads on the fuel assembly guide thimble tubes leading f

to excessive thimble tube distortion.

. For Wolf Creek, the increased compressive load was caused by unusual fuel f

assembly growth over and above what would normally be expected as a result

(

of irradiation exposure.

j The unusual growth component is a combination of growth due to oxide accumulation and accelerated growth, both of which are temperature sensitive.

j

. The unusual growth is observed only in high temperature plants on those high burnup fuel assemblies that have certain types of power histories.

t

  • Note: This page taken from the Westinghouse presentation on the " Root Cause f

of incomplete Control Rod Insertions at Westinghouse Reactors," Sumit Ray, Westinghouse Commercial Nuclear Fuel Division I

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SIEMENS l

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SPC Experience i

. No indication of slow or incomplete RCCA insertion has ever been reported in any SPC fuel

. SPC fuel assembly exposure experience in controlled positions:

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SPC Fuel Assembly Design Considerations j

1 Assembly design assessments include:

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Detail of Upper Tie Plate Design h

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SIEMENS Detail of Upper Core Interface

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SIEMENS Typical SPC Fuel Assembly Growth Allowances

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Core Structure Compatibility

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SIEMENS Potential Interference Points

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SIEMENS Typical Westinghouse Guide Tube Dimensions GT SPC has more c!earance CR and slightly more cross-sectional area and s

buckling strength.

s Typical guide tube s

dimensions follow.

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Item Westinghouse Value SPC Value SPC Delta o

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SIEMENS Typical 15x15 Guide Tube Dimensions ltem Westinghouse Value SPC Value Delta wrt SPC I

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Typical 17x17 Guide Tube Dimensions Item Westinghouse Value* SPC Value Delta wrt SPC t

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SIEMENS SPC Design Considerations 3

4 Factors that affect straightness of guide tube during irradiation:

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SIEMENS SPC Design Considerations (cont.?

Parameters which affect the growth of guide tubes:

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SIEMENS SPC Design Considerations (cont.?

SPC fuel design features that affect guide tube growth and straightness

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SIEMENS Guide Tube Buckling Calculations

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SIEMENS SPC Drag Test Using a Simulated RCCA and Typical 17x17 i

Cage Assembly (Test #1, Spacers and IFMs Bracketed)

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SIEMENS SPC Drag Test Using Simulated RCCA and Typical 17x17 Cage Assembly (Test #2, HTP Spacer Bracketed Only)

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SIEMENS Typical 17x17 Holddown Spring Force and i

Guide Tube Strength Characteristics

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Assembly Growth

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SPC Growth Model Development (cont.)

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Measured CE Design Fuel Assembly Growth

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SIEMENS Measured Westinghouse Design Fuel Assembly Growth

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RCCA Drop Time and Drag Results

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RCCA Drop Times 14x14 SPC Fuel Assemblies i

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RCCA Drop Times 15x15 SPC Fuel Assemblies

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SIEMENS Conclusion

. SPC utilizes appropriate methodology and allows l

adequate design margins for control rod insertion as demonstrated by the in-reactor validation data.

. SPC designs are compatible with RCCAs at all burnups.

No burnup restrictions or additional data collection are required for SPC fuel in control positions in l

Westinghouse design reactors.

500

SIEMENS Follow-on Activities I

. SPC will submit a letter:

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. Describing designs and design bases that preclude RCCA insertion problems l

. Showing operation is within SPC experience

. Providing reactor RCCA testing to support SPC conclusions l

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. NRC Actions

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TU Electric - Comanch NRC Presentation on 12-y

/

SPC Control Rod Insertion Issues

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WM j

WELECTRC

W2Y CPSES Current Status i

= UNIT 1 i

- Highest burnup fuel in rodded locations to date:

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. SPC fuel ~ 45 GWD/MTU (@EOC 5) j

. Westinghouse fuel ~ 42 GWD/MTU (@EOC 4) 1

- Cycle 6 (current cycle) projected maximum burnups in

,1 rodded locations:

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. SPC fuel @EOC 6 ~ 50 GWD/MTU

. Westinghouse @EOC 6 ~ 38 GWD/MTU

s Page 3 Y

CPSES Current Status (cont.)

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= UNIT 2 i

- Highest burnup fuel in rodded locations to date:

. SPC fuel - None currently l

. Westinghouse fuel ~ 34 GWD/MTU (EOC 2)

- Cycle 3 (current cycle) projected maximum burnups in i

rodded locations:

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. SPC fuel - None @EOC 3

. Westinghouse fuel ~ 46 GWD/MTU @EOC 3

Page 4 '

Y CPSES Current Status (cont.)

= There have been no indications to date of any control rod insertion problems in any fuel assemblies at CPSES.

- All rod drop measurements were as expected and within acceptable limits.

- All control rod drag measurements were as expected and within acceptable limits.

M i

- All control rods have fully inserted when tripped.

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page s -

i EOC Control Rod Drag Data A.

i

= U1-EOC5 and U2-EOC2 dashpot drag values well below the 100 lb. criteria as shown in attached Figure 1 with no evidence of any upward trend to date.

1

= U1-EOC5 dashpot drag vs. upper guide tube drag shows SPC and Westinghouse fuel well within lower left quadrant of graph as shown in attached Figure 2.

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V SPC Fuel Design Comparison I

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= SPC fresh fuel assembly clearance allowance to the upper core plate is greater than Westinghouse V5H and OFA fuel.

= SPC assembly growth allowances accounts for

" accelerated growth" and is consistent with Wolf Creek 's measured accelerated growth.

s W

FIGURE 1 - W & SPC RCCA Dashpot Drag vs. Bumup CPSES - Measured During Unlatching Process 100 80 l

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Fl50RE 2 - Unit 1 RCCA Drag - (upper gUidelube vs.Ta~slipoi) ~~

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During UNLATCHING Process @EOC5 180 140 120 E

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0 50 100 150 200 250 Deshpot Drag (Ibs)

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1 cc:

Mr. H. D. Curet, Manager Product Licensing Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, WA 99352-0130

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