ML19350B649

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Forwards IE Info Notice 81-07, Potential Problem W/Water-Soluble Purge Dam Matls Used During Inert Gas Welding. No Response Required
ML19350B649
Person / Time
Site: Waterford 
Issue date: 03/16/1981
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Aswell D
LOUISIANA POWER & LIGHT CO.
Shared Package
ML19350B650 List:
References
NUDOCS 8103230186
Download: ML19350B649 (1)


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UNITED STATES

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NUCLEAR REGULATORY COMMISSION t.-

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REGION IV

[J 611 RYAN Pt,AZA DRIVE. SUITE 1000 ARUNGTON, TEXAS M011 PDR POR Occket No.

50-382 March 16, 1981 MC NSIC CENTRAL FILES'

/4 Louisiana Power and Lignt Co.

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ATTN: Mr. D. L. Aswell Vice President of Pcwer Production LG 4

142 Delarende Street 8_. IM R.Z g 00 N 2 P

New Orleans, Louisiana 70174 O 3-Lk uW% &

Gentlemen:

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a h ificaticn of a This IE Informatien Notice is crovided as possibly significant matter.

It is excected that recipients will review the information for possible apolicability to their facility. No s:ecific action or resocnse is recuested at this time.

If further NRC evaluatiens so incicate, an IE Circular or Sulletin will be issued to recemend or recuest s:ecific licensee actions.

If you have questions regarding this matter, please c:ntact the Director of the acprocriate NRC Regional Office.

Sincerely,_

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j_p u, f ' A L 'fKarl V. Seyfrit / '/

Director

Enclosures:

1.

IE Information Notice No. 31-07 2.

List of Recently Issuec IE Information Notices

8103230 &

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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 IE Information Notice No. 81-07 March 16, 1981 Page 1 of 2 POTENTIAL PROBLEM WITH WATER-SOLUBLE PURGE OAM MATERIALS USED OURING INERT GAS WELDING Description of Circumstanceg:

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 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 t.aterial in water rapidly approaghes zero if the material is heated and held at temperatures in excess of 300 F; (2) the purge dam material hardens agd becomeg difficult to break if subject to tegperatures 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-vinylalcoholfilmwillnotdissolveduringaqueousflushingofghesystem if the material has been heated to temperatures in excess of 300 F.

Reconmended Actions for Holders of Ocerating Licenses and Const:uction Permits:

It is recommended that all welding operations involving polyvinyl alcohoi purge dam materials be governed by procedures that require the material to be located in areas that are sufficiently remoged frcm heat so that the temperature of tre material does not reach 300 F.

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,i IN 81-07 March 16, 1981 j

Page 2 of 2 i

4 No written response to this information notice is required.

If you require F

additional informttien with regard to this subject, please contact the appropriate NRC Regional Office.

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IE Information Notice No. 81-07 March 16, 1981 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.

Issued 80-44 Actuation of ECCS in the 12/16/80 All power reactor Recirculation Mode While facilities with an in Hot Shutdown Operating License (OL) or Construction Permit (CP) 80-45 Potential Failure of 12/17/80 All pressurized water BWR Backup Manual Scram reactor facilities with Capability an Operating License (OL)

Construction Permit (CP) 81-01 Possible Failures of 1/16/81 All power reactor facilities General Electric Type with an Operating License HFA Relays (OL) Construction Permit (CP) 81-02 Transportation of 1/23/81 All Radiography licensees Radiography Devices 81-03 Checklist for Licensees 2/12/81 All power reactor Making Notifications of facilities with an Significant Events in Operating License (0L) and Accordance with Near-term Applicants 10 CFR Part 50.72 81-04 Cracking in Main Steam 2/27/81 All power reactor facilities Lines with an Operating License (0L) or Construction Permit (CP) 81-06 Failure of ITE Model 3/11/81 All power reactor facilities K-600 Circuit Breaker with an Operating License (OL) or Construction Permit (CP) 81-05 Degraded DC System at 3/13/81 All power reactor facilities Palisades with an_0perating License (0L) or Construction Permit (CP)

Enclosure