ML19275A209

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Forwards IE Circular 79-19, Loose Locking Devices on Ingersoll-Rand Pump Impellers. No Action Required
ML19275A209
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 09/13/1979
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Millen C
PUBLIC SERVICE CO. OF COLORADO
References
NUDOCS 7910030321
Download: ML19275A209 (1)


Text

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%,.'.N :",o ARLINGTON, TEXAS 7G012 September 13, 1979 Docket Eo. 50-267 Public Service Company of Colorado ATTN:

Mr. C. K. Millen Senior Vice President P. O. Box 840 Denver, Colorado 80201 Gentlemen:

The enclosed IE Circular No. 79-19, is forwacded to you for information.

No written response is required.

Should you have any questions related to your understanding of this matter, please contact thin office.

Sincerely,

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Karl V. Seyfrit '

Director

Enclosures:

1.

IE Circular No. 79-19 2.

List of IE Circulars Issued in the Lact 6 Months cc:

D. W. Warembourg, Nuclear Production Manager Fort St. Vrain Nuclear Station P. O. Box 368 Platteville, Colorado 80651 L. Brcy, Manager, Quality Assurance 1C,214b 191o ooo 3m P

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.

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IE Circular No. 79-19 Date: September 13, 1979 Page 1 of 2 LOOSE LOCKING DEVICES ON INGERSOLL-RAND PUMP IMPELLERS Description of Circumstances:

Three reports have been submitted to the NRC regarding the loosening of locking devices or the impellers of pumps manufactured by the Ingersoll-Rand Company.

The first report was submitted as a significant deficiency (10 CFR 50.55(e))

by Arkansas Power and Light Company in letters of March 17, 1978, and May 9, 1975. The licensee reported excessive noise and vibrations in both Low P_ essure Safety Injection (LPSI) pumps during the preoperational test program on Unit 2 of Arkansas Nuclear One (ANO).

It was di:: covered that the washers, jam nut and cap nut used to retain the impellers were missing on both pumps (Ingersoll-Rand Type 8X20WD).

The licensee's corrective action involved the installation of a tab washer. This corrective action was, also, taken on the containment spray pumps (Ingersoll-Rand Type 6X23WD) becausa of similarity of design.

The second report was submitted by Duke Power Company in a licensee event report (LER 50-287/78-23) dated January 24, 1979. The symptoms were similar to those observed at ANO Unit 2 in that high vibration was detected in a reactor building spray pump (Ingersoll-Rand Type 4X11A) for Oconee Unit No. 3.

The licensee found that the impeller had worked loose. The corrective action included a revision to the maintenance procedure to specify torque requirements.

The third report was 10 CFR 21 Report No. 79-01 submitted by Portland General Electric Co. on April 16, 1979.

This report identified a deficiency that may exist in the Trojan Nuclear Plant containment spray pumps (Ingersoll-Rand Type 6X23WD) in that there is a potential for the impeller lock nut to loosen. The potential deficiency was identified because of the similarity of the containment spray pumps design to the residual heat removal (RHR) pumps (Ingersoll-Rand Type 8X20WD) and the discovery of a loose lock nut on an EHR pump during pump maintenance. The corrective action was to provide a positive mechanical lock on the impeller nut.

Westinghouse Nuclear Service Division has issued a Technical Bulletin to Westing-house plant owners on loose lock nuts on Ingersoll-Rand Types V, WD, and WDF pumps. Execepts from that Technical ullpt' arf inJ nclosure No. 1.

Combustion Engineering, Inc. has, also, informe sare problem in a letter dated March DUPLICATE DOCUMENT Enclosure No. 2.

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