ML18046A502
| ML18046A502 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/27/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8103160662 | |
| Download: ML18046A502 (7) | |
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Docket No. 50-255 Consumers Power Company ATTN:
Mr. R. B. DeWitt Vice President Nuclear Operations 212 West Michigan Avenue Jackson, MI 49201 cc w/encl:
D. P. Hoffman, Nuclear Licensing Administrator R. W. Montross, Manager Central Files AD/Licensing AD/Operating Reactors AEOD Resident Inspector, RIII PDR Local PDR
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Ronald Callen, Michigan Public Service Commission Myron M. Cherry
UNITED STATES NUCLEAR REGULATORY COMMISSION Gentlemen:
REGION Ill 799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137 February 27, 1981 This Information Notice No. 81-04 is provided as an early notification of a possibly significant matter and it is expected that recipients will review the information for possible applicability to their facilities.
No response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to further recommend or request specific licensee actions.
If you have questions regarding this matter, please contact this office.
Enclosure:
IE Information Notice No. 81-04 Sincerely,
~~~/~~-~-
t/James G. Keppler Director
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 February 27,1981 SSINS No.: 6835 Accession No.:
8011040265 IN 81-04 IE Information Notice No. 81-04:
CRACKING IN MAIN STEAM LINES Description of Circumstances:
The Virginia Electric Power Company promptly notified the NRC on February 23, 1981 that a radiography examination, during the ongoing steam generator replacement outage at Surry Unit 1, had revealed a lengthy crack indication in the 1.0. counterbore area of a weldment on the in-line 11T 11 fitting which connects the vertical run of 30-inch piping to the safety relief valve header and 30-inch main steam line of Steam Generator 11A 11
- This piping connection is located outside the containment penetration immediately upstream of the main steam isolation valve as shown in the attached sketch.
A visual and dye penetrant examination on the pipe I.D. surface of the weldment nearest the containment penetration established that the cracking extended about 120°F around the fitting counterbore between the 4 o'clock to 8 o'clock position.
Cracking was also observed in the weld counterbore at the opposite end of the T-fitting during visual examination of the piping interior.
Radio-graphic examination of 118 11 and 11C 11 main steam line T-fitting welds disclosed crack indications at similar locations.
Metallurgical specimens of the cracking were trepanned from the T-fitting of the "A 11 main steam line for analysis.
Controlled excavation and depth measurements of the crack at its mid-length indicated a crack depth of about 0.090 11 in this location.
The cause of cracking has not yet been established.
VEPCO has planned an ultrasonic examination of similar weldments in Surry Unit 2 main steam lines utilizing 11Hot Piping 11 ultrasonic techniques.
Preparations are also being made to ultrasonic examine similar weldments at North Anna Unit 1,
. currently in cold shutdown for refueling.
Recommendation to Licensees:
This information is provided as an early notificatiofi of a significant safety matter that is still under review by the NRC staff. It is expected that recipients will review the information for possible applicability'to their plants.
For those plants having similar main steam line configurations which are currently in a refueling or extended repair outage, it is recommended that a ultrasonic and/or radiographic examination of the three welds and counterbore areas of the T-fittings be performed before resumption of operations, unless some current basis for assurance of piping integrity is available.
IN 81-04 February 27, 1981 Page 2 of 2 No response to this notice is requested at this time.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Attachments:
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Sketch
- 2.
Recently issued IE Information Notices
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RECENTLY ISSUED IE INFORMATION NOTICES Information Notice No.
Subject 81-03 Checklist for Licensees Making Notifications of Significant Events in Accordance with 10 CFR 50.72 81-02 Transportation of Radiography Devices 81-01 Possible Failures of General Electric Type HFA Relays 80-45 Potential Failure of BWR Backup Manual Scram Capability 80-44 Actuation of ECCS in the Recirculation Mode While in Hot Shutdown 80-43 Failures of the Continuous Water Level Monitor for the Scram Discharge Volume at Dresden Unit No. 2 80-42 Effect of Radiation on Hydraulic Snubber Fluid 80-41 Failure of Swing Check Valve in the Decay Heat Removal System at Davis-Besse Unit No. 1 80-40 Excessive Nitrogen Supply Pressure Actuates Safety-Relief Valve Operation to Cause Reactor Depressur-ization OL =Operating Licenses CP = Construction Permits Date of Issue 2/12/81 1/23/81 1/16/81 12/17/80 12/16/80 12/5/80 11/24/80 11/10/80 11/10/80 e
IN 81-04 Issued to All power reactor facilityes with an OL A 11 Radiography licensees All power reactor facilities with OL or CP.
All PWR facilities with an OL or CP All PWR facilities with an OL or CP All power reactor facilities with OL or CP All power reactor facilities with OL or CP All power reactor facilities with an OL or CP All power reactor facilities with OL or CP
TO:
Regional Directors (Word P~ocessing Unit)
FROM:
Beth Matos ko:
IE: HQ The enclosed is a:ttachhment l to IE Informatfon Notice No. 81-04 to be issued today, 2/27/81.
CONT ACT :
H. J. Co 11 i n s 49-28181
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