ML18085A133
| ML18085A133 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/10/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8010280223 | |
| Download: ML18085A133 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
- REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-272 50-311 October 10, 1980 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Plaza - 15A Newark, New Jersey 07101 Gentlemen:
The enclosed IE Information Notice No. 80-36, 11Failure of Steam Generator Support Bolting," is forwarded to you for information.
No written response is r.equired.
If you desire additional information regarding this matter, please contact this office.
Enclosures:
- 1.
IE Information Notice No. 80-36 Sincerely, a--~.cl.~
/ ~
H. Grier Director
- 2.
List of Recently Issued IE Information Notices CONTACT:
E. G. Greenman (215-337-5267) cc w/encls:
F. P. Librizzi; General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station R. A. Uderitz, General Manager - Fuel Supply Department Q
- ~
__J
~~======;;:==========--*----.....__
=""""""'==~====-..... -----==~-
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 October 10, 1980 SSlNS No.:
6835 Accession No.:
8006190085 IN 80-36 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 1 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 1 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 reyealed cracks in three of the 48 steam generator support bolts.
The licensee attempted to remove the cracked bolts from the steam generator supports.
Two cracked bolts were successfully removed while the third falled during removal.
Two bolts that were judged as defect free by the ultrasonic examinat_ion 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 possibly 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.
r Information Notice No. 80-35 80-34 80-33 80-32 80-31 80-30 80-29 Supplement to 80-06 80-28 80-36 RECENTLY ISSUED IE INFORMATION NOTICES Subject Date Issued Leaking and Dislodged 10/10/80 Iodine-125 Implant Seeds Boron Dilution of 9/26/80 Reactor Coolant During Steam Generator Decontamination Determination of 9/15/80 Teletherapy Timer Accuracy Clarification of 9/12/80 Certain Requirements for Exclusive-use Shipments of Radioactive Materials Maloperation of Gould-8/27/80 Brown Boveri 480V-Type K-600S and K-Don GOOS Circuit Breakers Potential for Unaccept-8/27/80 able Interaction Between the Control Rod Drive Scram Function and Non-essential Control Air at Certain BWR Facilities Broken Studs on 8/7/80 Terry Turbine Steam Inlet Flange Notification of 7/29/80 Significant Events at Operating Power Reactor Facilities Prompt Reporting 6/13/80 of Required Information To NRC Issued to All holders of a Category G or Gl Medical License All holders of a PWR Power Reactor OL All holders of a teletherapy license All holders of an NRC or Agreement State License All holders of a power reactor OL or CP All holders of a BWR power reactor OL or CP All holders of a power reactor OL or CP All holders of a power reactor OL and near term OL applicants All app 1 i cants for and holders of a power reactor construction permit