ML20003E340
| ML20003E340 | |
| Person / Time | |
|---|---|
| Issue date: | 03/12/1981 |
| From: | Engelken R, Seyfreit K, Sniezek J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Grier B, James Keppler, James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8104020938 | |
| Download: ML20003E340 (2) | |
Text
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M (jAf/,gi March 12, 1981 MEMORANDUM FOR:
B. H. Grier, Director, Region I
/g J. P. O'Reilly, Director, Region II r.
J. G. Keppler, Director, Region III b
K. V. Seyfrit, Director, Region IV gdg}
R. H..Engelken, Director, Region V FROM:
James H. Sniezek, Director, Division of Resident and Regional Reactor Inspection, IE
SUBJECT:
IE INFORMATION NOTICE NO. 81-07:
POTENTIAL PROBLEM WITH WATER-SOLUBLE PURGE DAM MATERIALS USED DURING INERT GAS WELDING The subject information notice is transmitted for issuance March 16, 1981.
The information notice should be issued to all nuclear power reactor facilities holding power reactor Operating Licenses or Construction Permits. Also enclosed is a draft copy of the transmittal letter for this purpose.
v\\
James H. Sniezek, Director Division of Resident and Regional Reactor Inspection, IE
Enclosures:
1.
Draft transmittal letter 2.
CONTACT:
G. B. Georgiev, IE 49-27551 i
WPU:JD RRRI:IE RRRI:IE' DD:RRRI:IE D:RRRI:IE 3/12/81 GBGeorgiev RWWoodruff ELJordan JHSniezek INFOR4(M) 3/ /81 3/ /81 3/ /81 3/ /81 8104020 W
(Draft letter to all nuclear power reactor facilities holding an Operating License or Construction Permit)
IE Information Notice No. 81-07:
POTENTIAL PROBLEM WITH WATER-SOLUBLE PURGE DAM MATERIALS USED DURING.'NERT GAS WELDING s
Addressee:
This information notice is provided as an early notification of a possibly 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, Signature (Regional Director)
Enclosures:
IE Information Notice No. 81-07 l
l b
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 s
IE Information Notice No. 81-07:
POTENTIAL PROBLEM WITH WATER-SOLUBLE PURGE DAM MATERIALS USED DURING INERT GAS WELDING DescriptionofCircumsf.ances:
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 purge dam material during inert gas' welding or post-weld heat treatment operations.
Specifically, polyvinyl alcohol film manufac.tured by Chris-Craft Industries was the purge da::: 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.
i Specimens of polyvinyl alcohol film were recently obtained from the P.9no-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 Lecomes 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 300?F; (2) the purge dam material hardens and becomes difficult to break if subject to temperatures in the range of 300?F to 400?F, and becomes brittle if heated to 450?F; 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 temperattres in excess of 300?F.
Recommended Actions for Holders of Operating Licenses and Construction Permits:
It is recommended that all welding operations involving polyvinyl alcohol purge dam materials be governed by procedures that require the material to be located in areas that are sufficiently removed from heat so that the temperature of the material does not reach 300?F.
No written response to this information notice is required.
If you require additional information with regard to this subject, please cantact the appropriate NRC Regional Office.
Attachment:
Recently issued IE Information Notices h
Attachment IN 81-07 March 16, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 81-06 Failure of ITE Model 3/11/81 All power reactor K-600 Circuit Breaker facilities with an OL or CP i
81-05 Degraded DC System at 3/13/81 All power reactor Palisades facilities with an OL or CP 81-04 Cracking in Main Steam 2/27/81 All power reactor Lines facilities with an OL 81-03 Checklist for Licensees 2/12/81 All power reactor Making Notifications of facilities with an Significant Events in OL Accordance with 10 CFR 50.72 81-02 Transportation of 1/23/81 All Radiography y
Radiography Devices licensees 81-01 Possible Failures of 1/16/81 All power reactor General Electric Type facilities with an HFA Re;ays OL or CP.
80-45 Potential Failure of 1c/17/80 All PWR facilities BWR 8ackup Manual Scram with an OL or CP Capability 80-44 Actuation of ECCS in the 12/16/80 All PWR facilities Recirculation Mode While with an OL or CP in Hot Shutdown 80-43 Failures of the Continuous 12/5/80 All power reactor Water Level Monitor for facilities with an the Scram Discharge Volume OL or CP at Dresden Unit No. 2 80-42 Effect of Radiation on 11/24/80 All power reactor Hydraulic' Snubber Fluid facilities with an OL or CP OL = Operating Licenses CP = Construction Permits L