ML20041F283
| ML20041F283 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, Humboldt Bay, 05000000 |
| Issue date: | 03/12/1982 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Vanbrunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| Shared Package | |
| ML20041F261 | List: |
| References | |
| NUDOCS 8203160359 | |
| Download: ML20041F283 (1) | |
Text
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SSINS No.:
6835 Accession No.
3242040130' IN 82-06 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 12, 1982 IE INFORMATION NOTICE N0. 82-06:
FAILURE OF STEAM GENERATOR PRIMARY SIDE MANWAY CLOSURE STUDS Description of Circumstances:
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The Nuclear Regulatory Comission (NRC) was' notified by Maine Yankee Atomic Power Company and by Combustion Engineering (CE) that during routine disas-sembly of a steam generator primary side manway at. Maine Yankee, 6 of the 20 manway closure studs failed and'another 5 were found by. ultrasonic testing to
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be cracked. These are lh x 10 inch studs of SA 540 grade B 24 alloy steel.
The studs had been exposed to boric acid from a small primary coolant leak and to Furmanite sealing compound (primary grade) applied in an attempt to seal this leak. The studs exhibited evidence of surface corrosion attack possibly as a result of an interaction associated with stud preload, lubricant, Furmanite and primary coolant leakage environment.
A metallurgical analysis to determine the failure mechanism is currently underway at CE.
The entire set of studs on the affected steam generater (SG #2) have been replaced and an ultrasonic examination of all primary manway studs on steam generator units 2 and 3 is being performed.
Further corrective actions are pending stud failure analysis and its applicability to other primary boundary closures.
In the last few years there have been a significant number of incidents of failed or severely degraded bolts and studs.
Examples of the latter; primary coolant pump stud-bolts (Calvert Cliffs and Ft. Calhoun) and steam generator primary manway closures studs (0conee and ANO-1).
The failures described were attributed to stress corrosion cracking and corrosion wastage of high strength studs that are difficult to detect.
The NRC has contacted the CE Regulatory Response Group and requested a review of the problem.
This IE information notice is provided as an early notification of a potentially significant matter that is still under review by the NRC staff.
If NRC evalua-tion so indicates, further licensee action may be requested.
In the interim, we expect that licensees will review this information for applicability to their facilities.
No written response to this information notice is requested.
If you need addi-tional information, please contact the Regional Administrator of the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices 8203160359 820312 PDR ADOCK 05000133 G
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Attachment IN 82-06 March 12, 1982 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of
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Notice No.
Subject Issue Issued to 82-05 Increasing. Frequency of 03/10/82 All power reactor Drug-Related Incidents facilities holding an OL or CP 82-04 Potential Deficiency of 03/10/82 All power reactor Certain AGASTAT E-7000 facilities holding Series Time-Delay Relays an OL or CP 82-03 Environmental Tests of-03/04/82 All power reactor Electrical Terminal Blocks facilities holding an OL or CP 82-01 Auxiliary Feedwater Pump 02/26/82 All power reactor Rev. 1 Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuitry Modification 80-32 Clarification of Certain 02/26/82 All facility, Rev. 1 Requirements for Exlusive-materials and Use Shipements of Radio-Part 50 licensees active Materials 82-02 Westinghouse NBFD Relay 01/27/82 All power reactor Failures in Reactor facilities holJing Protection Systems at an OL or CP Certain Nuclear Power Plants 82-01 Auxiliary Feedwater Pump 01/22/82 All power reactor Lockout Resulting from facilities holding Westinghouse W-2 Switch an OL or CP Circuit Modification 4
81-39 EPA Crosscheck Program -
12/23/81 All power reactor Low Level Radiciodine in facilities holding Water Test Program an OL or CP 81-38 Potentially Significant 12/16/81 All power reactor Equipment Failures Resulting facilities holding from Contamination of Air-an OL or CP Operated Systems i
OL = Operating License CP = Construction Permit
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Q f7 March 12, 1982 Docket rios. 50-E28, 50-529, 50-530
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Arizona Public Service Company FtECEIVED P. O. Box 21666 MARL'51982n;-4 Phoenix, Arizona 85036 0F 3,
Attention: Mr. E. E. Van Brunt, Jr.
6 Vice President, Nuclear Projects g
d' Gentlemen:
y The enclosed infonnation notice provides early notification of an incident that may have safety significance.
It is expected that re-cipients will review the infonnation notice for possible applicability to their facilities.
If you have any questions regarding this matter, please contact this office.
Sincerely.
Original signed by T. W. Bishop for R. H. Engelken Regional Administrator
Enclosure:
Infonnation Notice No. 82-06 cc w/ enclosure:
F. W. Hartley, APS G. C. Andognini, APS f
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