ML20080C147
| ML20080C147 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/17/1983 |
| From: | Subramonian N, Le A Franklin Research Ctr, Franklin Institute |
| To: | Shaw H Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079L053 | List: |
| References | |
| CON-NRC-03-81-130, CON-NRC-3-81-130, TAC 07934 NUDOCS 8402070470, TER-C5506-418 | |
| Download: ML20080C147 (9) | |
Text
1 SUPPLEMENTARY TECHNICAL EVALUATION IlEPORT AUDIT FOR MARK l.. CONTAINMENT LONG-TERM PROGRAM - STRUCTURAL ANALY$1S FOR OP5 RATING REACTORS NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION NRC DOCKETNO. 50-298 FRC PROJECTC5506 NftCTACNO. 07934 FRCASSIGNMENT12 NRC CONTRACT NO. NRC-03-81-130 FRC TASK 418 MijGC4 % mk+;g:4}6f%%;yAfqq qQsgr,p:g,yg4yy4.s_v. w.
..m., s,p; 3.,4y Preparedby Franklin Research Center Author: N. Subramonian 20th and Race Streets Philadelphia, PA 19103 A. K. Le FRC Group Leader: N. Subramonian
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Preparedfor Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: H. Shaw
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Auguse 17, 1983 This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.
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SUPPLEMENTARY TECHNICAL EVALUATION REPORT AUDIT FOR. MARK I CONTAINMENT LONG-TERM P,ROGRAM - STRUCTURAL ANALYSIS FOR OPERATING REACTORS NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION NRC DOCKETNO. 50-298 FRC PROJECT C5506 NRCTAC NO. 07934 FRC ASSIGNMENT 12 NRC CONTRACT NO. NRC-03-81-130 FRC TASK 418 Prepared by Franklin Research Center Author: N. Subramonian 20th and Race Streets A. K. La Philadelphia, PA 19103 FRC Group Leader: N. Subramonian Prepared for Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: H. Shaw August 17, 1983 This repo, t was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or sesponsibility for any third party's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third party would not infringa privately owned rights.
4 Franklin Research Center 20th and Race Streets, Phila., Pa. 19103 (215) 448-1000
TER-C5506-418 CONTENTS Section Title Page 1
INTRODUCTION 1
2 FATIGUE ANALYSIS OF PIPING.
2 3
CONCLUSION.
3 4
REFERE!CES.
4 iii u00 er.nniin a ren coni.,
TER-C5506-418 FOREWORD This Technical Evaluation Report was prepared by Franklin Research Center under a contract with the U.S. Nuclear Regulatory Connaission (Office of Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NBC operating reactor licensing actions. The technical evaluation was conducted in accordance with criteria established by the NRC.
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TER-C5506-418 SUPPLEMENT TO FRANKLIN RESEARCH CENTER TECHNICAL EVALUATION REPORT TElt-C550 6-316 FOR COOPER NUCLEAR STATION (REFERENCE 1) 1.
INTRODUCTION From the audit of the Cooper Nuclear Station plant-unique analysis report
[2] and the Licensee's response [3] to the request for additional information (RAI), it was concluded earlier [1] that the Licensee's structural analysen with regard to major plant modifications and the torus-attached piping are in general conformance with the criteria requirements [4].. The Licensee's approach to fatigue analysis of piping indicated conformity with the approach recommended by a generic Mark I study documented in Reference 5.
The piping fatigue analysis is evaluated and reported in this supplementary TER.
The criteria for containment vacuum breaker evaluation were not addressed in Reference 4 and hence this item is considered to be outside the scope of this report. Thc Licensee's evaluation of. containment vacuum breakers [6] will still be reviewed by the NRC as a part of Mark I long-term program.
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TER-C5506-418 2.
FATIGUE ANALYSIS OF PIPING FRC and the NRC staff evaluated the generic Mark I approach to fatigue of ii P P ng as documented in Reference 5.
Based on a review of this report and clarification obtained on the total number of cycles due to operating basis earthquake considered in the analysis, the generic Mark I approach is found to be technicaliy adequate. Hence, the approach used by the Licensee for Cooper Nuclear Station piping fatigue meets the intent of the criteria [4].
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CONCLUSION
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Based on the present evaluations and the previously reported evaluations
[1] e it is concluded that the Cooper Nuclear Station plant-unique structural analyses with regard to major plant modifications and torus-attached piping are technically adequate and meet the intent of the criteria. The evaluation criteria of the containment vacuum breaker valves are not addressed in Reference 4 and are therefore outside the scope of this TER; however, this issue will still be examined as a part of the Mark I long-term program.
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TER-C5506-418 4.
REFERENCES i
1.
Technical Evaluation Report i
Audit for Mark I Containment Long-Term Program - Structural Analysis for Operating Reactors - Cooper Nuclear Station Franklin Research Center, Philadephia, PA January 1983, TER-C5506-316 2.
Cooper Nuclear Station Plant Unique Analysic Report, MarP. I Containment Program Nebraska Public Power District hevision 0, April 1982 3.
J. M. Pilant (Nebraska Public Power District)
Letter to D. B. Vassallo (NRC).
Subject:
. Mark I Containment Program -
Plant UnbrJe Analysis Report December 1, 1982
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" Mark I Containment Program Structural Acceptance Criteria Plant Unique Analysis Application Guide," General Electric Co., San Jose, CA October 1979 5.
MPR-751
" Mark I Containment Program Augmented Class 2/3 Fatique Evaluation Method and Results for Typical Torus Attached and SRV Piping Systems,"
MPR Associates, Washington, D.C.
November 1982 6.
J. M. Pilant (Nebraska Public Power District)
Letter (with attachment) to D. B. Vassallo (NRC).
Subject:
Mark I Containment Program - Plant Unique Analysis Report April 29,1983 i
1 i Franklin Research Center
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