ML19345D583
| ML19345D583 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay, Diablo Canyon |
| Issue date: | 11/26/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane P PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8012160124 | |
| Download: ML19345D583 (1) | |
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o, UNITED STATES
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SUITE 202. WALNUT CREEK PLAZA 3,.
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Docket Nos. 50-133, 50-275, 50-323 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention:
Mr. Philip A. Crane, Jr.
Assistant General Counsel Gentlemen:
This Information Notice is provided as an early notification of a possible significant natter.
It is expected 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 reco:=ena or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, I
s,
$, [L-C-N, -
'L R. H. Engelken Director
Enclosures:
l.
IE Information Notice
- 30. 00-29 Supplement No. 1 2.
List of Recently Issued IE Information Notices l
cc w/ enclosures:
J. D. Shiffer W. Raymond, PG&E P,. C. Thornberry, Plant Manager E. '.leeks, PG;E, Humboldt Bay E. B. Langley, Jr., PG&E 1
l
SSINS No.:
6835 Accession No.:
UNITED STATES 8006190023 tiUCLEAR REGULATORY COMMISSION IN 80-29 0FFICE OF INSPECTION AND ENFORCEMENT Supplement No. 1 WASHINGTON, D.C.
20555 November 26, 1930 IE Infornation Notice No. 80-29 (Supplement No.1):
BROKEN STUDS ON TERRY TURBINE STEAM INLET 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.
Subseouently, the vendor has informed the NRC that the boiting 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-ohosphorized cold drawn carDon steel.
From the analysis cerformed, 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 nachining plain carbon steel) for bolting is discouraged by the NRC; particularly in situations where possible high loading conditions could be anticipated.
This Information Notice is provided as an early notification of a possibly significant natter 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 appropric;e NRC Regional Office.
IN 80-20 Supplement No. 1 November 26, 1980 RECENTLY ISSUED IE INFORi'ATION NOTICES Informa ti on Cate 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 7emaval Systen a c Davis-or CP Besse Unit No. 1 80-40 Failure of Swinn Check 11/10/SO All power facilities "alve in tne Decay Heat with and OL or CP Removal System at Davis-Besse Uni: lo. 1 80-39 Malfunctions of Solenoid 10/31/80 All light water reactor "alves Manufactureo oy facilities holding Valcor Engineering Corporation power reactor OLs or cps 80-38 Cracking in Charging Pump 10/30/80 All PUR facilities Ca: 10 Clauding with an OL or CP 80-37 Lon!'.innent Cooier teaks 10/24/80 All nuclear power and ~_2ctor Cavi ty facilities holding Flooding at Indian Point power reactor OLs Uni: 2 or cps 80-36 Failure of Steam 10/10/80 nll 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-121 Implant Seeds G1 medical licensees 80-34 Coron Dilution of Peactor 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 Tiner Accuracy (G3) licensees 80-32 Clarification of Certain 8/12/80 All NRC and agreement Requirenents for Exclu-state licensees sive-use Shipments of Radioactive Materials
- Operating Licenses or Construction Permits i