ML20080P604

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RO 83-032:on 830930,thermal & Seismic Stress Criteria on Instrument Tubes Not Met.Fatigue Characteristics Revealed Allowable Number of Cycles Exceeds Actual Number of Heatup & Cooldown Cycles Experienced
ML20080P604
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 10/03/1983
From: Toole R
GENERAL PUBLIC UTILITIES CORP.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
5211-83-285, RO-83-032, RO-83-32, NUDOCS 8310070263
Download: ML20080P604 (2)


Text

e DESIGNATED ORIGINAL

.Cirtified By M[ -

GPU Nuclear Corporation ggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 o191: i

. 717 944 7621

TELEX 84 2386 Writer's Direct Dial Number: ,

October 3, 1983

- , 5211-83-285 Dr. -Thomas E. Murley Region I, Regional Administrator U. S. Nuclear Regulatory Comission 631 Park Avenue King of . Prussia, PA 19406

Dear Sir:

Three Mile Island Nuclear Statlon Unit 1-(TMI-l)

Operating License No. DPR-50 Docket No. 50-289 LER 83-032 This is to confirm the ccnversation between Mr. F. Young, Region:I, NRC

.and Mr. M. A. ' Nelson, Supervisor Unit 1 Review Program, at 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> on

. September 30, 1983.

. As a follow-up to an internal Material Non-Conformance Report (MNCR) concerning :

- instrument tube sloping both themal and seismic stress on instrument tubes were reevaluated. The portion of the tubing evaluated was primarily from '

the main piping to which the tubing is attached to the first tubing anchor.

Movement resulting from thermal expansion of the main piping was also included

. in the analysis. The criteria.used in the evaluation are that calculated  !

stresses caused by seismic and thermal effects shall not exceed the stress.

l-_ limits in the USAS B31.1 Code of Pressure Piping. For a number of .instru-ment lines, stress criteria for one or both of these loading criteria are

- not met. This condition is considered reportable under Technical Specifica-tion 6.9.2.A.9. '

,. Even though the USAS B31.1 Code Stress Criteria were not met, the evaluation results reveal that the stresses resulting from thermal loads are belowi the ASME III operability stress criteria of two times the materials yield strength. Furthermore, a check of the fatigue characteristics of the tubing revealed that the allowable number of cycles permitted exceeds the actual number of hestup and cooldoe cycles that have been experienced

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8310070263 831003 .

PDR ADOCK 05000289 I

S PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation EO Y

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Dr. Thomas E. Murley 5211-83-285 at TMI-l. Consequently this LER does not constitute a safety. issue but i; only a non-conformance of the applicable (USAS B31.1) code cited in the

' The details of this finding will be provided in the 14 day followup report.

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il h J. Toole I rations and Maintenances '

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