ML20059G576

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Summary of 931209 Meeting W/Representatives of Util & Licensee Contractors to Discuss Planned Elimination of SG Hydraulic Snubbers at Plants.List of Attendees & Licensee Presentation Handout Encl
ML20059G576
Person / Time
Site: Wolf Creek, Callaway  Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 01/12/1994
From: William Reckley
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9401240280
Download: ML20059G576 (32)
v • d • e


Text

.

l January 12, 1994 Docket Nos. 50-482 and 50-483 LICENSEES:

Wolf Creek Nuclear Operating Corporation Union Electric Company FACILITIES: Wolf Creek Generating Station Callaway Plant

SUBJECT:

SUMMARY

OF MEETING HELD ON DECEMBER 9, 1993 TO DISCUSS THE STEAM GENERATOR SNUBBER ELIMINATION PROGRAMS AT WOLF CREEK AND CALLAWAY On December 9,1993, members of the NRC staff met with representatives of Wolf Creek Nuclear Operating Corporation, Union Electric Company, and licensee contractors to discuss the planned elimination of steam generator hydraulic snubbers at Wolf Creek and Callaway. A list of attendees is provided as The handout associated with the licensees' presentation is provided as Enclosure 2.

The licensees and contractors provided details regarding the removal of steam generator hydraulic snubbers and the prospective cost savings associated with the modification. The licensees plan to implement the program in Fall 1994, l

at Wolf Creek and Spring 1995, at Callaway. Some staff questions ~regarding:

I the design basis analyses associated with the replacement of the hydraulic snubbers were not addressed at the meeting. Due to the licensees' proposed l

schedule, the staff committed to provide specific questions to-the licensees i

as soon as possible.

Original Signed By William D. Reckley, Project Manager Project Directorate IV-2 Division of Rcactor Projects III/IV/V Office of Nuclear Reactor Regulation-

Enclosures:

. DISTRIBUTION, 1.

Attendance List Docket FileJ WReckley 2.

Handout NRC PDR EPeyton Local PDR OGC cc w/ enclosures:

PDIV-2 R/F EJordan l

See next page TMurley/FMiraglia ACRS (10)

LJCallan NRC Participants JRoe JMitchell EAdensam LYandell, RGN-IV

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JZwolinski EGreenman,.RGN-III OFFICE PDIV-2/LA PDIV-2/PM

[PDIII-3/PM PDIV-2/p s

NAME CP

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WReYkYey Marton SBlach DATE Q1/10/94 01/10/94 01//d/94 01//o/94

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OFFICIAL RECORD COPY / FILENAME: b:\\ SUM 129.AM EC HLE DETER COPY 9401240280 940112~

  1. BOO ADOCK O 482

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cc w/ enclosure:

Jay Silberg, Esq.

Mr. Otto Maynard Shaw, Pittman, Potts & Trowbridge Vice President, Plant Operations 2300 N Street, NW Wolf Creek Nuclear Operating Corporation Washington, D.C.

20037 P. O. Box 411 Burlington, Kansas 66839 Mr. C. John Renken Policy and Federal Department Regional Administrator, Region IV Missouri Public Service Commission U.S. Nuclear Regulatory Commission P. O. Box 360 611 Ryan. Plaza Drive, Suite 1000 Jefferson City, Missouri 65102 Arlington, Texas 76011 Regional Administrator, Region III Mr. Keven J. Moles U.S. Nuclear Regulatory Commission Manager Regulatory Services 799 Roosevelt Road Wolf Creek Nuclear Operating Corporation i

Glen Ellyn, Illinois 60137 P. O. Box 411 Burlington, Kansas 66839 Senior Resident Inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission P. O. Box 311 Resident Inspectors Office Burlington, Kansas 66839 8201 NRC Road Steedman, Missouri 65077-1302 Chief Engineer Utilities Division Mr. Neil S. Carns Kansas Corporation Commission President and Chief Executive Officer 1500 SW Arrowhead Road Wolf Creek Nuclear Operating Corporation Topeka, Kansas 66604-4027 Post Office Box 411 Burlington, Kansas 66839 Office of the Governor i

State of Kansas l

Topeka, Kansas 66612 Attorney General 1st Floor - The Statehouse Topeka, Kansas 66612 County Clerk Coffey County Courthouse Burlington, Kansas 66839 Mr. Gerald Allen Public Health Physicist Bureau of Environmental Health Services Division of Health Kansas Department of Health and Environment 109 SW Ninth Topeka, Kansas 66612 ll

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'Ei CC' i

Cermark Fletcher Associates Mr. Neil S. Carns 18225 Flower Hill Way #A President and Chief Gaithersburg, Maryland 20879-5334 Executive Officer Wolf Creek Nuclear Operating Gerald Charnoff, Esq.

Corporation Thomas A. Baxter, Esq.

P. O. Box 411 Shaw, Pittman, Potts & Trowbridge Burlington, Kansas 66839 2300 N. Street, N.W.

Washington, D.C.

20037 Mr. Dan I. Bolef, President Kay Drey, Representative Mr. S. E. Sampson Board of Directors Coalition Supervising Engineer, for.the Environment Site Licensing 6267 Delmar Bopulevard Union Electric Company University City, Missouri 65130 Post Office Box.620 Fulton, Missouri 65251 Mr. Donald F. Schnell Senior Vice President - Nuclear U.S. Nuclear Regulatory Commission Union Electric Company Resident Inspectors Office Post Office Box 149 RR #1 St. Louis, Missouri 63166 Steedman, Missouri 65077 Mr. Alan C. Passwater, Manager Licensing and fuels Union Electric Company Post Office Box 360 St. Louis, Missouri 63166 Manager - Electric Department Missouri Public Service Commission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60523-4351 Mr. Ronald A. Kucera, Deputy Director

.i Department of Natural Resources P. O. Box 176 Jefferson City, Missouri 65102 L

  • T ENCLOSURE I LIST OF ATTENDEES MEETING WITH WOLF CREEK NUCLEAR OPERATING CORPORATION AND UNION ELECTRIC COMPANY REGARDING STEAM GENERATOR SNUBBER ELIMINATION PROGRAM DECEMBER 9, 1993 Wolf Creek Nuclear Operatina Corporation Forrest Rhodes Steve Wideman Bill Eales K. Parthasarathy Union Electric Company Dennis Bettenhausen David Shafer Westinohouse T. H. Liu Rajni Patel Christopher Stirzel Seth Swamy Brad Maurer Altran Ken Chang R. L. Cloud & Assoc.

Jim Leung NRC Suzanne Black William Reckley Ray Wharton Terence Chan Arnold Lee

I Wolf Creek & Callaway i

Steam Generator Snubber Elimination Program Presented to the Nuclear Regulatory Commission

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Agenda SG Snuaaer Elimination

. Introduction

. Background

. Snubber Elimination Program

. Plan

. Status e Results e implementation

. Conclusion e--,

Introduction Purpose o" Meeting Discuss Benefits of SG Snubber Elimination Present SG Snubber Elimination Program Provide Status of Program Define implementation Plans s

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SG Upper Support Modification RPV Side Snubbers Removed and Backside Side Snubbers Converted i

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Background===

Steam Generator Snubbers 4 Large Bore Hydraulic Snubbers Per Loop e Total 16 snubbers per plant

= 1300 kip capacity

  • Passive device for thermal e Active dynamic restraint

. Testing Requirements Per Tech Spec (3/4.7.8)

  • -10% testing method
  • At least 2 of 16 tested each refueling outage
  • Activation & bleed rate tested l

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===.

Background===

SG Snubbers (continued)

Snubber Testing Requires e Polar crane e Scaffolding Individual Plant Experience e Hydraulic fluid replaced after test

. Each reservior (4) checked for contamination l

  • Callaway replaced all fluid in RF3 & RF5
  • Wolf Creek replaced all fluid in RF5-l ALARA l

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e Reduce demand on outage resources (polar crane,

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SG Snubber Costs Snubber O&M Costs Are Large S25,000 Vendor Testing (for 2 snubbers)

S50,000 Craft Labor S10,000 Engineering Support S25,000 Scaffolding S15.000 Material (seals & fluid for 1 reservoir)

S125,000 Per plant:per refueling outage-ALARA cost are not included One snubber test failure - S322,000 Cost Every third outage reservoir flush.& fill -

S100,000 Cost m

SG Snubber Elimination Cost / Benefit Analysis l

Avoided O&M Costs l

Millions of Dollars L

$7.2 M L

8-SG Snubber O&M Costs Over Plant Life 6

SG Snubber 4

. Elimination Costs 2

0 6-8 10

'12 14 16 18 20L 22 24 126-Refueling Outage Number -

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I SG Snubber Elimination Programs Power

% Snubbers Snubbers Program

' Station Eliminated Removed Completed Surry 71 %

60 1986 Beaver Valley 83 %

60 1987/1989 Vogtie 75 %

24 1987/1990 Kewaunee 75 %

6 1988

. Comanche Peak 75 %

24 1989/1992 North Anna 67 %

48 1989 Ginna 75 %

12 1989 ASCO 60 %

18 1993 Summer 60 %

9 1993-Callaway 100 %

16-In-Progress -

Wolf Creek 100 %

16 In-Progress 17 Power Stations 75 %

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I SG Snubber Elimination Made Possible Through Advancements in Computer Technology Workstations Enhanced software Reduction in design basis loadings Elimination of pipe break effects

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= AIB Time history seismic analysis Use of component reserve design margin m.

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e SG Snubber Elimination Program Plan Phase 1 - Feasibility Study t

Phase 2 - Complete Analysis & Qualification Implementation Schedule

. Wolf Creek RF07 September 1994

. Callaway RF07 March 1995

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SG Snubber Elimination Phase 1 - Feasibility Study Structural System Analyses

  • Coupled building / loop model e Non-linear seismic time history analyses e One-way acting compression struts RCL Piping LBB e Leak rate.

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SG Snubber Elimination Phase 1 - Feasibility Study (continued) l Elimination of MSL AIB l

Consideration of FW Nozzle Break Critical Component Review

. Loop piping & elbows-

  • SG internals e Component supports Mainsteam & Feedwater Piping Design of Replacement Hardware-l 9

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Phase 1 - Feasibility Study (continued)

RCL Piping LBB

. Critical Location - RPV Outlet Nozzle

. Loadings

. Results

  • 10 GPM Leak Rate, Flaw Size 3.34 inches e Satisfied the recommended margin on the leak rate -

factor of 10.

. Satisfied the recommended margin on the flaw size -

factor of 2.

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RCL Pipe and Elbow Stress Assessment Critical Loading Stress Allowable Location Condition (ksi)

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SG Inlet Level D 51.00 56.70 Elbow SG Inlet-Level B*

27.25 28.35 Elbow 3

't SAssumed OBE =.0.9 SSE

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SG Snubber Elimination Phase 1 - Feasibility Study (continued)

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SG Internals Review e Non-linear seismic time history analysis e Results for limiting components e tube stress intensity. (at TSP, U-bend), Membrane plus Bending =:26.0.ksi <. 75.5 ksi e tube deformation / area reduction (at TSP),

acceptable by comparison

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Seismic Margin Assessment Seismic Margin = Code Allowable / Actual Support Seismic Margin Seismic Margin Component Existing Modified t

RPV Horizontal 5.9 8.7 RPV Vertical 4.6 13.8 RCP Columns 2.5 7.8 RCP. Tie Rods 5.7 10.8

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Mainsteam & Feedwater Piping Assessment High Stress Stress Allowable Location (ksi)

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MS - Eq. (9) 17.3 21.0 Upset

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.Eq. (9) 27.8 42.0 Faulted MS Pipe Break 37.1 37.8 FW - Eq..(9) 10.0 18.0 Upset

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SG Snubber Elimination Phase 2 - Analysis &

i Qualification Efforts Complete Analyses Not Addressed in Phase 1 i

. LOCA effect from auxiliary nozzle breaks j

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. RCL displacement effect on auxiliary piping MS & FW lines snubber optimization Complete Design Basis: Stress Qualification Procure Replacement Hardware Prepare Plant Modification Package s

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SG Snubber Elimination Implementation Plan Begin Phase 2 January 1994 Install Hardware

. Wolf Creek RF07 September 1994 Callaway RF07 March 1995 m

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3 SG Snubber Elimination Conclusions

. Phase 1 Demonstrates Program is Feasible

. Use of Replacement Hardware is Required

. Adequate Margins Will Be Maintained

. Phase 2 Effort Will Proceed

. Implementation Schedule Will Be Maintained

. Implement Through 10CFR50.59 Evaluation l

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