ML17296B315
| ML17296B315 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/16/1981 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| NUDOCS 8104020855 | |
| Download: ML17296B315 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1990 N. CALIFORNIABOULEVARD SUITE 202, WALNUTCREEK PLAZA WALNUTCREEK, CALIFORNIA94596 Harch 16, 1981 Docket Nos.
50-528, 50-529, 50-530 Arizona Public Service Company P.
0.
Box 21666
- Phoenix, Arizona 85036 Attention:
Hr.
E.
E.
Van Brunt, Jr.
Vice President, Nuclear Projects Gentlemen:
This information notice is provided as an early notification of a possibly significant matter.
It is expected that recipients'ill 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,
)
H.
nel en irector
Enclosure:
IE Information Notice No. 81-07 cc w/enclosure:
F.
M. Hartley, APS
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SSINS No.:
6835 Accession No.:
8011040267 IN 81-07 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 16, 1981 IE Information Notice No. 81-07:
POTENTIAL PROBLEM WITH WATER-SOLUBLE PURGE DAM MATERIALS USED DURING INERT GAS WELDING Descri tion of Circumstances:
Recent experiences with water-soluble purge dam materials at several nuclear construction sites have shown the need to develop welding procedures that address the potential for thermally decomposing the pur ge dam material during inert gas welding or post-weld heat treatment operations.
Specifically, polyvinyl alcohol film manufactured by Chris-Craft Industries was the purge dam material used at these construction sites.
The decomposition of this purge dam material at elevated temperatures causes the material to lose its solubility in water.
As a result, the purge dam material cannot be completely dissolved during subsequent piping system flushing and cleaning operations.
The failure of this material to completely dissolve could cause significant problems during reactor plant operation.
Specimens of polyvinyl alcohol film were recently obtained from the Mono-Sol Division of Chris-Craft Industries and tested at Franklin Research Center (FRC) to determine, among other things, the threshold temperature at which the material becomes insoluble in water.
The results of this test program indicate that (1) the solubility of the purge dam material in water rapidly approaches zero if the material is heated and held at temperatures in excess of 300F; (2) the purge dam material hardens and becomes difficult to break if subjected to temperatures in the range of 300F to 400F, and becomes brittle if heated to 450F; and (3) purge dam material heated above its threshold temperature is not soluble in commonly used laboratory solvents.
The inde-pendent testing laboratory (FRC) therefore concludes that the Mono-Sol poly-vinyl alcohol film will not dissolve during aqueous flushing of the system if the material has been heated to temperatures in excess of 300F.
Recommended Actions for Holders of 0 eratin Licenses and Construction Permits:
It is recommended that all welding operations involving polyvinyl alcohol purge dam materials be governed by procedures that require the mater~al to be located in areas that are sufficiently removed from heat so that the temperature of the material does not reach 300F.
No written response to this information notice is required.
If you require additional information with regard to this subject, please contact the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices
RECENTLY ISSUED I E INFORMATION NOTICES Attachment IN 81-07 March 16, 1981.
Informati on Notice No.
81-06 81-05 81-04 81-03 81-02 81-01 80-45 80-44 Sub 'ect Failure of ITE.Model K-600 Circuit Breaker Degraded DC System at Palisades Cracking in Hain Steam Lines Checklist for Licensees Making Notifications of Significant Events in Accordance with 10 CFR 50.72 Transportation of Radiography Devices Possible Failures of General Electric Type HFA Relays Potential Failure of BWR Backup Manual Scram Capabi lity Actuation of ECCS in the Recirculation Hode While in Hot Shutdown Date of Issue 3/11/81 3/13/81 2/27/81 2/12/81 1/23/81, 1/16/81, 12/17/80 12/16/80
'ssued'o'll power reactor facilities with an OL or CP All power reactor faci,ities with an OL or CP All power reactor faciliti,es with an OL All power reactor facili.ties with an OL All Radiography licensees All power reactor faciliti,es with an OL or CP.
All. PWR facili.ties qi,th an OL or CP All pWR facilities with an.OL or CP 80-43 Failures of the Continuous 12/5/80, Water Level Monitor for the Scram Discharge Volume at Dresden Unit No.
2 All power 'reactor foci 1 ities with. an Ol, or CP 80-42 Effect of Radiation on Hydraulic Snubber Fluid 11/24/80 All power reactor faci,lities with an OL or CP OL = Operating Licenses CP
= Construction Permits
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