ML19345D581
| ML19345D581 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/26/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8012160121 | |
| Download: ML19345D581 (1) | |
Text
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1990 N. CALIFORNIA BOULEVARD
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Itovember 26, 1980 ij 3
Q Docket ?!o. 50-344 Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention:
Mr. Bart D. Withers Vice President fluclear Gentlemen:
This Information ilotice is provided as an early notification of a possible significant matter.
It is expected thLt recipients will review the information for possible applicability to their facilities.
ilo specific action or response is requested at this time.
If further IIRC evaluations so indicate, an IE Circular or Bulletin will be issued to reco=ena or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate 1RC Regional Office.
Sincerely,
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R. H. Engelken Director
Enclosures:
1.
IE Information Ilotice
- o. 80-29 Supplement flo.1 2.
List of Recently Issued IE Information flotices cc w/ enclosures:
C. P. Yundt, PGE J. W. Durham, Esq.
Senior Vice President and Corporate Counsel 8012160 @
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SSINS No.: 6835 Accession No.:
UNITED STATES 8006190028 NUCLEAR REGULATORY C0t! MISSION IN 80-29 0FFICE OF INSPECTION AND ENFORCEMENT Supplement No.1 WASHINGTON, D.C.
20555 November 26. 1980 IE Inforration Notice No. 80-29 (Suoolement No.1): BROKEN STUDS ON TERRY TURBINE STEAM IflLET FLANGE Descriotion 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.
Subsecuently, the vendor has informed the NRC that the bolting material used at ANO-1 was AISI C-1117 steel.
Indecencent laboratory analyses by the NRC and Arkansas Power and Light have verified that the bolting material was a re-sulphurized, re-onospnorized 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 tougnness 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 aiscouraged by tne NRC; particularly in situations where possible hign loading conditions could be anticipated.
This Information Notice is.proviced as an early notification of a possibly significant natter that is still under review by the tiRC staff.
It is expected that recioients will review the information for possible applicability to their facility.
"o specific action or response is requested at this time.
If you have any questions regarding this matter, please contact the Director of the aporopriate NRC Regional Office.
IN 80-20 Supplcment No. 1 Movcmber 26, 1983 RECEMTLY 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 reactor Valve in the Decay Heat facilities with an OL Pemoval System at Davis-or CP Besse Unit No.1 80-40 Failure of 5 wing Check 11/10/80 All power facilities Valve in the Decay Heat with and OL or CP Removai Systen at Davis-Besse Unit No. 1 80-39 Malfunctions of Solenoid 10/31/80 All light water reactor
'!alves Manufactured by facilities holding Valcor Engineering Corporation power reactor OLs or cps 80-38 Cracking in Charging Pump 10/30/80 All PWR facilities Casir; Cladding with an OL or CP 20-37 Containment Cooler Leaks 10/24/80 All nuclear power and Reactor Cavity facilities holding ricading at Indian Point power reactor OLs Unit 2 or cps 80-36 Failure of Stean 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding power reactor 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 Peactor 9/26/80 All pressurized water Coolant Durina Steam reactor facilities l
Generator Decontamination holding power reactor OLs 80-33 Determination of Teletherapy 9/15/80 All teletherapy Tiner Accuracy (G3) licensees 80-32 Clarification of Certain 8/12/80 All MRC and agreement l
Requirements for Exclu-state licensees sive-use Shipments of Radioactive Materials
- Operating Licenses or Construction Permits
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