ML17296B125
| ML17296B125 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/26/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8012160127 | |
| Download: ML17296B125 (6) | |
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p0~i UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 202, WALNUTCREEK PLA2A WALNUTCREEK, CALIFORNIA94596 November 26, 1980 Docket Nos.
50-528, 50-529, 50-530 Arizona Public Service Company P. 0.
Box 21666
- Phoenix, Arizona 85036 Attention:
Mr.
E.
E.
Van Brunt, Jr.
Vice President, Nuclear Projects Gentlemen:
This Information Notice is provided as an early notification of a possible significant matter.
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 recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, R.
H. Engelken Director
Enclosures:
l.
IE Information Notice No. 80-29 Supplement No..
1 2.
List of Recently Issued IE Information Notices cc w/enclosures:
F.
M. Hartley, APS
'80123 $0 i
I E)
UNITED STATES NUCLEAR REGULATORY COMMISS ION OFFICE OF INSPECTION AND ENFORCEMEHT l!ASHIHGTON, D.C.
20555 SSINS No.:
6835 Accession No.:
8006190028 IN 80-29 Supplement No.
1 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 AHO-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 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 tougnness carbon steel (re-sulphurized free machining plain carbon steel)
=or bolting is discouraged by the NRC; particularly in situations where possible high loading conditions could be anticipated.
This Information Hotice is provided as an early notification of a possibly significant matter that is still under review by the HRC 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.
i
RECENTLY ISSUED IE INFORMATION NOTICES IN 80-20 Supplement No.
1 November 26, 1980 Informati on Notice No.
80-42 80-41 Sub'ect Effeet of Radi ati on on Hydraulic Snubber Fluid Failure of Swing Check Valve in the Decay Heat Removal System at Davis-Besse Unit No.
1 Date of Issue Issued to 12/20/80 All power reactor facilities with OL or CP 11/10/80 All power reactor facilities with an OL or CP 80-40 Failure of Swing Check 11/10/80 All power facilities Valve in the Decay Heat wi th and OL or CP Removal System at Davi s-Besse Unit No.
1 80-39 Mal functions of Solenoid 10/31/80 Valves Manufactured by Valcor Engineering Corporation All light water reactor facilities holding power reactor OLs or CPs 80-38 80-37 80-36 80-35 Cracking in Charging Pump Casing Cladding Containment Cooler Leaks and Reactor Cavity Flooding at Indian Point Unit 2 Failure of Steam Generator Support Bolting Leaking and Dislodged Iodine-124 Implant Seeds 10/30/80 10/24/80 10/10/80 10/10/80 All PMR facilities with an OL or CP All nuclear power faci 1 ities hol ding power reactor OLs or CPs All nuclear power reactor facilities holding power reactor OLs or CPs All categories G. and G1 medical licensees 80-34 80-33 Boron Dilution of Reactor 9/26/80 Coolant During Steam Generator Decontamination Determination of Tel etherapy 9/15/80 Timer Accuracy All pressurized water reactor facilities holding power reactor OLs All teletherapy (G3) licensees 80-32 Clarification of Certain Requirements for Exclu-sive-use Shipments of Radioactive Materials 8/12/80 All NRC and agreement state licensees
- Opera ti ng Licenses or Cons tructi on Permi ts
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