ML19338G308
| ML19338G308 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/10/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mcdonald R ALABAMA POWER CO. |
| References | |
| NUDOCS 8010290043 | |
| Download: ML19338G308 (1) | |
Text
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UNITED STATES o
!" 3 NUCLEAR REGULATORY COMMISSION
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n eE REGION il e[
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101 MARIETTA sT., N.W., sulTE 3100
%.....o ATLANTA, G EORGI A 30303 In Reply Refer To:
RI 48 Alabama Power Company ATTN:
R. P. Mcdonald Vice President-Nuclear Generation P. O. Box 2641 Birmingham, AL 35291 Gentlemen:
This Information Notice is p:..vided as an early notification of a possible significant matter. It is expc;ted that recipients will review the information for possible applicability to their facilities. No specific action or response is requested at this time. If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate h7C Regional Office.
Sincerely, C[
h James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 80-36 2.
List of Recently Issued IE Information Notices cc w/ encl:
W. O. Whitt, Executive Vice President F. L. Clayton, Jr., Senior Vice President H. O. Thrash, Manager-Nuclear Generation O. D. Kingsley, Jr., Manager, Nuclear Engineering and Technical Services J. W. McGowan, Manager-Operations Quality Assurance W. G. Hairston, III, Plant Manager W. C. Petty, Manager-Quality Assurance (Design and Construction)
R. E. Hollands, Jr., QA Supervisor
- 8010290043
l SSINS No.:
6835 Accession No.
8006190085 1
l UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 October 10, 1980 IE Information Notice No. 80-36: FAILURE OF STEAM GENERATOR SUPPORT BOLTING Description of Circumstances:
On September 4,1980, the NRC staff was informed by the Northern States Power Company that extensive cracking of the bolting for the supports attached to bottom of the steam generators on Prairie Island Unit I had occurred. The licensee initially discovered the bolting problem when two bolts failed during detensioning. The licensee was attempting to remove the pre-load on the bolting (specified at 1400 ft-lbs) to minimize the potential for stress corrosion cracking of the high strength 1-1/2 in. dia. 250 ksi maraging steel bolting (Vascomax 250).
Ultrasonic examination of the support bolting revealed cracks or breaks in 47 of 48 support bolts for the two steam generators at the Prairie Island Unit I facility. The licensee subsequently shut down the Prairie Island Unit 2 facility and performed ultrasonic examinations of the same steam generator support bolting, that failed on Unit 1.
The results of the UT examinations revealed cracks in three of the 48 steam generator support bolts. The licensee attempted to remove the cracked bctts from the steam generator supports. Two cracked bolts were successfuily removed while the third failed during removal.
Two bolts that were judged as defect free by the ultrasonic examination were also removed. Magnetic particle examinations confirmed the results of the ultrasonic examinations on the bolts which were removed. As part of the short term corrective actions taken, the licensee has unloaded and retensioned the bolting at approximately 50 to 100 ft.-lbs.
Inservice ultrasonic examination of the affected bolting had been performed previously.
In the case of Unit 1 a significant number of the bolts were examined at the last refueling outage 14 months ago. No cracks were found at that time.
The susceptibility for stress corrosion cracking was identified in NUREG-0577 (for comment). The NUREG identifies those facilities which have utilized maraging steels for reactor coolant pump and steam generator support bolting.
Further the NUREG recommends augmented inspections for the facilities included in Group I.
Licensees are encouraged to review the bolting materials used at their respective facilities and consider inspection of maraging steel bolting that are either pre-loaded or significantly loaded during operation.
This Information Notice is provided as an early notification of a possible significant matter that is still under review by the NRC staff. It is expected that recipients will review the information for possible applicability to their facility. No specific action or response is requested at this time. If you have any questions regarding this matter, please contact the Director of the_ appropriate NRC Regional Office.
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IN 80-36 October 10, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to'-
80-36 Failure of Steam Generator 10/10/80 All nuclear power reactor Support Folting facilities with an OL or CP i
80-35 Leaking and dislodged 10/10/80 All categories G and Iodine-124 implant seeds G1 medical licensees 80-34 Boron dilution of reactor 9/26/80 All pressurized water coolant during steam reactor facilities generator decontamination holding power reactor OLs 80-33 Determination of teletherapy 9/15/80 All teletherapy timer accuracy (G3) licensees 80-32 Clarification of certain 8/12/80 All NRC and agreement requirements for Exclu-state licensees sive-use shipments of 4
radioactive materials 80-31 Maloperation of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding OLs volt type K-600S and or cps K-DON 600S circuit breakers 80-30 Potential for unaccept-8/19/80 All boiling water reactor able interaction between facilities holding power the control rod drive scram reactor OLs or cps.
function and non-essential 4
control air at certain GE BWR facilities 80-29 Broken studs on Terry 8/7/80 All light water reactor turbine steam inlet facilities holding flange power reactor OLs or cps
- Supplement to Notification of 7/29/80 All holders of reactor 80-06 s snificant events at and near-term OL operating power reactor applicants facilities 80-28
?:ompt reporting of 6/13/80 All applicants for and required information holders of nuclear power to NRC reactor cps 80-27 Degradation of reactor 6/11/80 All pressurized water coolant pump studs reactor facilities holding power reactor OLs or cps
- Operating Licenses or Construction Permits
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