ML19275A184

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Forwards IE Circular 79-19, Loose Locking Devices on Ingersoll-Rand Pump Impellers. No Action Required
ML19275A184
Person / Time
Site: Point Beach  
Issue date: 09/13/1979
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Burstein S
WISCONSIN ELECTRIC POWER CO.
References
NUDOCS 7910030283
Download: ML19275A184 (1)


Text

an arouq'o, UNITED STATES t 8"

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NUCLEAR REGULATORY COMMISSION n

E REGION 111 a #

%S 799 ROOSEVELT ROAD o

GLEN ELLYN. ILLINOIS 60137 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:

Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 Gentlemen:

The enclosed IE Cir:ular No. 79-19, is forwarded to you for information.

No written response is required. Sheuld you have any questions related to your understanding of this matter, please contact this office.

Sincerely, Qbg-- On

(/ James G. Keppler Director

Enclosures:

1.

IE Circular No. 79-19 2.

List of IE Circulars Issued in the Last 6 Months cc w/ enc 1:

Mr. G. A. Reed, Plant Manager Central Files Director, NRR/DPM Director, NRR/ DOR C. M. Trammell, ORB /NRR PDR Local PDR NSIC TIC Sandra A. Bast, Lakeshore Citizens for Safe Energy iE.,2 069 1

i.,

273 70100so 4-

i SSINS:

6830 Accession No: 7908220111 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.

20555 September 13, 1979 IE Circular No. 79-19 LOOSE LOCKING DEVICES ON INGERSOLL-RAND PUMP IMPELLERS Description of Circumstances:

Three reports have been submitted to the NRC regarding the locsening of locking devices on 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, 1978. The licensee reported excessive noise and vibrations in both Low Pressure Safety Injection (LPSI) pumps during the preoperational test program on Unit 2 of Arkansas Nuclear One (ANO).

It was discovered 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) because of similarity of design.

The second report was submitted by Duke Power Company in a licensee event report (LER 50-287/78-23) dated Ja.nuary 24, 1979.

The symptoms were similar to those observed et AND 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 mainteinance 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 RHR 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 W, WD, and WDF pumps.

Excerpts from that Technical Bulletin are in Enclosure No. 1.

Combustion ~

Engineering, Inc. has, also, informed the NRC of,their t

3 t4 d.n..t same problem in a letter dated March 1

,q Enclosure No. 2.

DUPLICATE DOCUMENT

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