ML18139B164
| ML18139B164 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 02/27/1981 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8103160713 | |
| Download: ML18139B164 (5) | |
Text
In Reply Refer To:
RII: JPO 50-338 50-339 50-404
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e UNITED STATES e
NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 FEB 2 / 1001 Virginia Electric and Power Company Attn:
J. H. Ferguson Executive Vice President-Power P. 0. Box 26666 Richmond, VA 23261 Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter and it is expected that recipients will review the informa-tion for possible appli-cability 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 the Director of the appro-priate NRC Regional Office.
Sincerely,
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Enclosures:
1
- 1.
IE Information Notice No.* 8-~)
- 2.
Recently Issued IE Information Notices cc w/encl:
W. R. Cartwright, Station Manager P. G. Perry, Senior Resident Engineer J. L. Wilson, Manager
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 February -27,1981 ss** No.: 6835 Ac sion 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 I. D. counterbore area of a we 1 dment on the i n-1 i ne 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° around the fitting counterbore between the 4 0 1clock to 8 0 1clock 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 11A 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 11 Hot Piping" 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 notification 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.
I
IN.04 Feb y ry 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:
- 1.
Sketch
- 2.
Recently issued IE Information Notices
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RECENTLY ISSUED IE INFORMATION NOTICES Information Notice No. 81-03 81-02 81-01 80-45 80-44 80-43 80-42 80-41 80-40 Subject Checklist for Licensees Making Notifications of Significant Events in Accordance with 10 CFR 50.72 Transportation of Radiography Devices Possible Failures of General Electric Type HFA Relays Potential Failure of BWR Backup Manual Scram Capability Actuation of ECCS in the Recirculation Mode While in Hot Shutdown Failures of the Continuous Water Level Monitor for the Scram Discharge*Volume at Dresden Unit No. 2 Effect of Radiation on Hydraulic Snubber Fluid Failure of Swing Check Valve in the Decay Heat Removal System at Davis-Besse Unit No. 1 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 IN 81-04 Issued to All power reactor facilityes with an OL A 11 Radiography licensees All power r~actor 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