ML20009C242
| ML20009C242 | |
| 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, 05000283, Zimmer, Bailly, Marble Hill  |
| Issue date: | 07/07/1981 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8107200402 | |
| Download: ML20009C242 (2) | |
Text
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o, UNITED STATES o
NUCLEAR REGULATORY COMMISSION g
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7M ROOSEVELT ROAD e
GLEN ELLYN, ILLINOIS 60137 JUL 7 1981 e
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JUL 1e 198F g1 Illinois Department of lp 7 Nuclear Safety ATTN:
Mr. Gary N. Wright
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Deputy Director
- r)N 1035 Outer Park Drive 4..
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Springfield, IL 62704
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Gentlemen:
The enclosed IE Information Notice No. 81-19 titled " Lost Parts in Primary Coolant System" was sent to the licensees listed belcw on July 6, 1981:
American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 504 316)
Cincinnati Gas and Electric Company Zimmer (50-358)
Clevelan ' Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457) byron 1, 2 (50-454, 50-455)
Dresden.1; 2, 3 (50-10, 50-237, 50-249)
LaSalle 1, 2 (50-373, 50-374)
Quad Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
Palisades (50-255)
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Midland 1, 2 (50-329, 50-330)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company S
g@p Fermi 2 (50-341) oi
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Illinois Department of Nuclear Safety Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Iowa Electric Light & Power Company Duane Arnold (50-331)
Northern Indiana PL'olic Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547) i Toledo Edison Company l
Davis-Besse 1 (50-346)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Visconsin Public Service Corporation Kewaunee (50-305)
Sincerely, Dorothy E. Carroll, Chief Word Processing and Document Control Section
Enclosure:
IE Information Notice No. 81-19 cc w/ encl:
Mr. D. W. Kane, Sargent & Lundy DMB/ Document Control Desk (RIDS)
J. G. Keppler, RIII Acting Division Directors, RIII P. R. Wohld, RIII RI
/so 7/6/81
s SSINS No.:
6835 Accession No.:
8103300399 g
IN 81-19 UNITED STATES NUCLEAR REGULATORY C041 MISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 July 6, 1981 IE Information Notict No. 81-19:
LOST PARTS IN PRIMARY COOLANT SYSTEM Description of Circumstancy :
During an outage for turbine maintenance, Public Service Electric dnd 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, susper.ded from a foam float, down the hot legs.
The camera was successfully retrieved from one steam generator, those 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 te.nporarily.
Success-ful retrieval was further compounded by thermal wells protrJding into the hot leg.
Upon retrieval of the camera float, the following parts were missing:
- 1) a five-inch long ry 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 ler.gth of nylon line; and 5) a piece of float material.
Most of these parts were later found in the RHR heat c langer 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 shorter tubes.
While exhaustive efforts to resolve the cause of MIMS impacts are desirable i
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 info m atior, regarding this matter, contact the Director of the appropriate NRC Regional Office.
i
Attachment:
Recently issued IE Information Notfr.es i
Attachr.,ent 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 81-15 Degradation of Automatic 4/22/81 All power reactor ECCS Actuatien Capability facilities with an by Isolation of Instrumer.!
OL or CP Lines 81-1 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 Automatic Control Rod Insertion on Low Control Air Pressure l
81-11 Alternate Rod Insertion 3/30/81 All BWR facilities for BWR Scram Represents with an OL or CP a Potential Path for loss of Primary Coolant 81-10 Inadvertam Containment 3/25/81 All power reactor Spray Due to Personnal facilities with an Error OL or CP l
81 09 Degradation of Residual 3/26/81 All power reactor Heat Removal (RHR) System facilities with an OL or CP i
i OL = Operating Licenses CP = Construction Permits I
.