ML20009D731

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Advises That IE Info Notice 81-19, Lost Parts in Primary Coolant Sys, Was Forwarded to Listed Utils
ML20009D731
Person / Time
Site: Monticello, Dresden, Davis Besse, Palisades, Perry, Fermi, Kewaunee, Point Beach, Byron, Braidwood, Prairie Island, Callaway, Duane Arnold, Clinton, Cook, Quad Cities, La Crosse, Big Rock Point, Zion, Midland, LaSalle, Zimmer, Bailly, Marble Hill  Constellation icon.png
Issue date: 07/06/1981
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8107240306
Download: ML20009D731 (1)


Text

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-LI 1,Iffl American Electric Power Service Corporation D. C. Cook 1, 2 (50-315, 50-3.6)

Cincinnati Gas and Electric Company Zimmer (50-358)

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Perry 1, 2 (50-440, 50-441) f e

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Commonwealth Edison Company

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Byron 1, 2 (50-454, 50-455) g, Dresden 1, 2, 3 (50-10, 50-237, 50-249) 9 y

ff La Salle 1, 2 (50-373, 50-374)

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Quad-Cities 1, 2 (50-254, 50-265)

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Consumers Power Company Big Rock Point (50-155)

Palisades (50-255)

Midland 1, 2 (50-329, 50-330)

Dairyland Power Corporation LACBWR (50-409)

The Detroit Edison Company Fermi 2 (50-341)

Illinois Power Company Clinton 1, 2 (50-461, 50-462)

Iowa Electric Light and Power Company Duane Arnold (50-331)

Northern Indiana Public Service Company Ol Bailly (50-367) lO Northern States Power Company 3

j Monticello (50-263)

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Public Service of Indiana ADP*

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Marble Hill 1, 2 (50-546, 50-547) hg,W$

Toledo Edison Company Davis-Besse 1 (50-346)

Union Electric Company Callaway 1, 2 (40-483, 50-486)

Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)

Wisconsin Public Service Corporation Kewaunee (50-305) 8167240306 810706 7

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SSINS N2.:

6835 Accession No.:

8103300399 IN 81-19 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 July 6, 1981 IE Information Notice No. 81-19:

LOST PARTS IN PRIMARY COOLANT SYSTEM Description of Circumstances:

During an outage for turbine maintenance, Public Service Electric and Gas Company elected to drain the primary system at Salem Unit 1 to about the midplane of the hot leg nozzles and open two steam generators in an attempt to locate the source of an intermittent series of impacts that had been recorded on the Metal Impact Monitoring System (MIMS) during operation.

Not finding the source, an additional attempt to search the loops was made by floating a TV camera, suspended from a foam float, down the hot legs.

The camera was successfully retrieved from one steam generator, whose hot leg does not have a connection for residual heat removal (RHR) suction.

Retrieval from a second steam generator, whose hot leg does have a 3000 gpm RHR suction flow, proved impossible until the RHR flow was turned off temporarily.

Success-ful retrieval was further compounded by thermal wells protruding into the hot leg.

Upon retrieval of the camera float, the following parts were missing:

1) a five-inch long by one-inch diameter stainless steel tube containing lenses and a lens positioning motor; 2) a three-inch long plastic extension tube; 3) a three-inch length of 3/8-inch plastic tubing; 4) a short length of nylon line; and 5) a piece of float material.

Most of these parts were later found in the RHR heat exchanger and heat exchanger bypass valve, downstream of the RHR pump which was not damaged when it chopped the five-inch long stainless tube into two shorte-tubes.

While exhaustive efforts to resolve the cause of MIMS impacts are desirable and commendable, careful planning should precede placing any additional foreign material into the primary system.

A detailed inventory of all such material should be maintained, and special precautions should be taken to prevent the generation of loose parts in the system.

In the above example, a thorough analysis regarding effects of the RHR flow on the equipment could have prevented the potential safety problems that resulted from this event.

No written response to this information notice is required.

If you need additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.

Attachment:

Recently issued IE Information Notices

'b Attachment IN 81-19 July 6, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.

Subject Issue Issued to 81-18 Excessive Radiation 6/23/81 Specified licensees Exposures to the Fingers of holding Byproduct Three Individuals Incurred licenses During Cleaning and Wipe Testing of Radioactive Sealed Sources at a Sealed-Source Manufacturing Facility 81-16 Control Rod Drive System 4/23/81 All BWR facilities Malfunctions with an OL or CP i

81-15 Degradation of Abcomatic 4/22/81 All power reactor ECCS Actuation Capability facilities with an by Isolation of Instrument OL or CP Lines 81-14 Potential Overstress of 4/17/81 All power reactor Shafts on Fisher Series facilities with an 9200 Butterfly Valves OL with Expandable T Rings 81-13 Jammed Source Rack in a 4/14/81 Specified irradiator Gamma Irradiator licensees 81-12 Guidance on Order Issued 3/31/81 All BWR facilities January 9, 1981 Regarding with an OL or CP l

Automatic Control Rod Insertion on Low Control Air Pressure 81-11 Alternate Rod Insertion 3/30/81 All BWR facilities for 8WR Scram Represents with an OL or CP a Potential Path for Loss of Primary Coolant 81-10 Inadvertant Containment 3/25/81 All power reactor Spray Due to Personnel facilities with an Error OL or CP 81-09 Degrad6 tion of Residual 3/26/81 All power reactor Heat Removal (RHR) System facilities with an OL or CP l

OL = Operating Licenses CP = Construction Permits

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