ML19340C824
| ML19340C824 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/26/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Crouse R TOLEDO EDISON CO. |
| References | |
| NUDOCS 8012170525 | |
| Download: ML19340C824 (2) | |
Text
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'o UNITED STATES E
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NUCLEAR REGULATORY COMMISSION REGION lil o,
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799 ROOSEVELT ROAD b>
g' GLEN ELLYN, ILLINOls 60137 November 26, 1980 Those on Attached List:
This IE Information Notice No. 80-29 (Supplement No. 1) is provided as an early notification of a possible significant matter.
It is expected that recipients will review the information fer possible applicability to their facilities. No specific action or response is requested at this time.
If further hTC 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 this office.
Sincerely, na-t M
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< / James -
Keppler Direc tor Enclosurm:
IE Information Notice No. 80-29, Supplement No. 1 l
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Docket No. 50-346 b ':h ty -
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Mr. Richard P. Crouse Vice President Egy 21 Nuclear
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2 300 Madison Avenue Toledo, OH 43652 cc w/ encl:
T. D. Murray, Station Superintendent Central Files AD/ Licensing AD/ Operating Reactors AEOD Resident Inspector, RIII PDR Local PDR NSI gg##
T4W Hart 1d v. Kohn, Power Siting Commission Helen W. Evans, State of Ohio
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SSINS No.:
6835 Accession No.:
UNITED STATES 8006190028 NUCLEAR REGULATORY COMMISSION IN 80-29 0FFICE OF INSPECTION AND ENFORCEMENT Supplement No. 1 WASHINGTON, D.C.
20555 November 26, 1980 IE Information Notice No. 80-29 (Supplement No. 1):
BROKEN STUDS ON TERRY TURBINE STEAM INLET FLANGE Description of Circumstances:
In the original Information Notice the failed Terry Turbine steam inlet flange studs were identified as probably manufactured from ASTM-A193-Grade B7 steel.
Subsequently, the vendor has informed the NRC that the bolting material used at ANO-1 was AISI C-1117 steel.
Independent laboratory analyses by the NRC and' Arkansas Power and Light have verified that the bolting material was a re-sulphurized, re phosphorized cold drawn carbon steel.
From the analysis performed, the failure was caused by high overload which resulted in a primarily brittle transgranular fracture (cleavage) in probably less than 10 cycles.
This is consistent with the operating experience (water slugging) and the inherent low toughness of the bolting material used.
Licensees are encouraged to review the materials selected for safety-related bolting applications considering especially those situations where impact loadings could occur.
The use of low toughness carbon steel (re-sulphurized free machining plain carbon steel) for bolting is discouraged by the NRC; particularly in situations where possible high loading conditions could be anticipated.
l 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.
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o IN 80-20 Supplement No. 1 November 26, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 80-42 Effect of Radiation on 12/20/80 All power reactor Hydraulic Snubber fluid facilities with OL or CP 80-41 Failure of Swing Check 11/10/80 All power reac',r Valve in the Decay Heat facilities with an OL Removal System at Davis-or CP Besse Unit No. 1 80-6 Failure of Swing Check 11/10/80 All power facilities Valve in the Decay Heat with and OL or CP Remova' System at Davis-Besse Unit No. 1 80-39 Malfunctions of Solenoid 10/31/80 All light water reactor Valves Manufactured by facilities holding Valcor Engineering Corporation power reactor OLs or cps 80-38 Cracking in Charging Pump 10/30/80 All PWR facilities Casing Cladding with an OL or CP 80-37 Containment Cooler Leaks 10/24/80 All nuclear power and Reactor Cavity facilities holding Flooding at Indian Point power reactor OLs Unit 2 or cps I
80-36 Failure of Steam 10/10/80 All nuclear power l
Generator Support Bolting reactor facilities I
holding power reactor l
OLs or cps 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 Radioactive Materials l
- Operating Licenses or Construction Permits l