ML19350B315
| ML19350B315 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/16/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Crouse R TOLEDO EDISON CO. |
| References | |
| NUDOCS 8103200255 | |
| Download: ML19350B315 (2) | |
Text
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. Docket No. 50-346
-Toledo Edison. Company ATTN: - Mr. Richard P. Crouse
- Vice President Nuclear Edison Plaza 300 Madison Avenue
--Toledo, OH 43652
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T..D. Murray,cStation
-Superintendent-Central Files
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7, NUCLEAR REGULATORY COMMISSION 5
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- GLEN ELLYN, ILLINOIS 60137 s
March 16, 1981 Gentlemen:
This IE Information Notice No. 81-07 is provided as an early notifi-cation 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 this office.
Sincerely, i
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Auk 4A James G. Keppler Direr: tor
Enclosure:
IE Information Notice No. 81-07 t
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SSINS No.: 6835 Accession No.:
8011040267 o
IN 81-07 UNITED STATES O
f I-NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT WASHINGION, 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 Description of Circumstances:
Recent experiences with water-soluble purge darr. materials at several nuclear construction sites have shown the need to develop welding procedures that address the potential for thermally decompoi;ing the purge 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 failute 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 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 solubie in commonly used laboratory solvents.
The inde-pendent testing laboratory (FRC) therefore concludes that the Mono-Sol poly-vinyl alcohol film will not disso1ve during aqueous flushing of the system
.if the material.has been heated to temperatures in excess of 300 F.
Recommended Actions'for Holders of Operating Licenses and Construction Permits:
It is recommended'that all wel. ding 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 decs not reach'300 F.
~
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.
>Attachmenti Recently. issued IE Information Notices t
i
+
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 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 Radiography Devices licensees.
81-01 Possible Failures of 1/16/81 All power reactor General Electric Type facilities with an HFA Relays OL or CP.
80-45 Potential Failure'of
-12/17/80 All PWR facilities BWR' Backup 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 J
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
-0L or CP 10L.= Operating Licenses
-CP = Construction Permits