ML20003E312
| ML20003E312 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/16/1981 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8104020860 | |
| Download: ML20003E312 (1) | |
Text
1 ObittL. Pk/A o
UNITiiD STATES
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NUCLEAR REGULATORY COMMISSION y,, ( 3 '.#k, oE REGION V o,.
1990 N. CALIFORNIA BOULEVARD g
e'4 SUITE 202, WALNUT CREEK PLAZA m,,,,
WALNUT CREE K, CALIFORNIA 94596 March 16, 1981 Docket No. 50-344 t-2 Portland General Electric Company 121 S. W. Salmon Street
%. g4'g2 Portland, Oregon 97204 9:
3
/887 gi; Attention: Mr. Bart D. Withers n
Vice President Nuclear
~^
Gentlemen:
4
'd' This information notice is provided as an early notific d 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 recomend or request specific licensee actions.
If you have questions regarding this matter,' please contact the Director of the appropriate NRC Regional Office.
Sin erely, i
I krector
Enclosure:
IE Information Notice No. '81-07 cc w/ enclosure:
C. P. Yundt, PGE J. W. Durham, Esq., PGE not/&2A(kc
SSINS No.: 6835 Accession No.:
8011040267
' i-IN 81-07
~
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 March 16, 1981 7IE Information Notice No. 81-07:
POTENTIAL PROBLEM WITH WATER-S0LUBLE PURGE DAM MATERIALS USED DURING INERT GAS WELDING Description-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 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 failure of this material to ccmpletely 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 materialcbecomes in~ soluble in water. The results of this test program
. indicate that (1) the solubility of the purge dam material in water rapidly
- approaches 1zero~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-cvinyl alcohol. film willL 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 Operating Licenses and Construction Permits _:
lit?is recommended that all wclding' operations involving: polyvinyl alcohol purge dam materials _be. governed by procedures that require the material to be: located Lin areas;that-are sufficiently removed from heat so' that the temperature of Lthe material does not reach '300F.
No: written response to this Jinformationinotice is required.
If you require
! additional finfoEmation with. regard t'o this subject, please contact the:
appropriate NRCfRegional Office.
Attachment:
'Recently issued IE;Information Notices m.
5__'-
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 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 Radiograohy 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 Capabili ty 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 0L = Operating Licenses-CP = Construction Permits
.