ML20010B892
| ML20010B892 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Cooper, Arkansas Nuclear, River Bend, Waterford, South Texas, Comanche Peak, Fort Calhoun, Fort Saint Vrain  |
| Issue date: | 07/06/1981 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | ARKANSAS POWER & LIGHT CO., GULF STATES UTILITIES CO., HOUSTON LIGHTING & POWER CO., KANSAS GAS & ELECTRIC CO., LOUISIANA POWER & LIGHT CO., NEBRASKA PUBLIC POWER DISTRICT, OMAHA PUBLIC POWER DISTRICT, PUBLIC SERVICE CO. OF COLORADO, TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 8108180442 | |
| Download: ML20010B892 (2) | |
Text
.-
p p nogh UNITED STATES
[}
q j
NUCLEAR REGULATORY COMMISSION aEcion iv 611 RYAN PLAZA DRIVE, SulTE 1000 o~
g k
e*
ARLINGTON, TEXAS 76011 July 6, 1981 N "os j'g\\ * \\aECBflg.,J i
b, ~NuWme II981L YI c,.
\\
/
to Gentlemen:
e The enclosed IE Information Notice is provided as an early notification of a pessibly significant matter.
It is expected that recipients will review l
the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so f
indicate, an IE Circular or Bulletin will be issued to recommend or request l
specific licensee actions.
If you have questions regarding this matter, please contact this office.
Sincerely,
./
.m
(
.J
.?
..:. \\
-l f G-Karl V. Seyfrit
./ -
Director
'/
Enclosures :
1.
IE Infonnation Notice No. 81-19 2.
List of Recently Issued IE Information Notices f)):h'*
Y i
sM fo69 4.(
l l
8108180442 810706 PDR ADOCK 05000267 0
t IE INFORMATION NOTICE 81-19 SENT TO THE FOLLOWING LISTED LICENSEES Licensee Facility / Docket Number Arkansas Power and light Conpany Arkansas Nuclear One, Unit 1 & 2 Little Rock, Arkansas 50-313; 50-368 Nebraska Public Power District Cooper Nuclear Station Columbus, Nebraska 50-298 Omaha Public Power District Fort Calhoun Station Omaha, Nebraska 50-285
(
Public Service Company of Colorado Fort St. Vrain Generating Station Denver, Colorado 50-267 Gulf States Utilities River Bend Beaumont, Texas 50-458; 50-459 Houston Lighting & Power Company South Texas Project Houston, Texas 50-498; 50-499 Kansas Gas & Electric Company Wolf Creek Wichita, Kansas STN 50-482 Louisiana Power & Light Company Waterford-3 New Orleans, Louisiana 50-382 Texas Utilities Generating Company Comanche Peak Steam Electric Station
' Dallas, Texas 50-445; 50-446 i
i i
i
SSINS No.:
6835 Accession No.-
8103300399 IN 81-19 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 81-19 July 6, 1981 Page 1 of 1 LOST ~ PARTS IN PRIMARY COOLANT SYSTEM Descriotion of Circumstances:
Ouring 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 lag 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 sourca, an additional attemot 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 l
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 mi: sing:
- 1) a five-inch long by one-inch diameter stainless steel tube containing lenses and a lens positioning motor; 2) a three ach long plastic extension tuce; 3) a three-inch length of 3/8-inch plastic tu' ing; 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 tae RHR pumo 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 desiracle and cos lencable, 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 tne 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.
1 f
s
/ t
IE Information Notice No. 81-19 July 6, 1981 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 81-08 Repetitive Failures of 3/20/81 All power reactor Limitorque Operator SMB-4 facilities with an Operating Motor-to-Shaft Key License (0L) or Construction Permit (CP) 81-10 Inadvertent Containment 3/25/81 All power reactor facilities Spray Due to Personnel with an Operating License Error (OL) or Construction Permit (CP) 81-09 Degradation of Residual 3/26/81 All power reactor facilities Heat Removal (RHR) System with an Operating License (0L) or Construction Permit (CP) 81-11 Alternate Rod Insertion 3/30/81 All BWR facilities for BWR Scram Represents with an Operating License a Potentia? Path for Loss (OL) or Construction Permit of Primary Coolant (CP) 81-12 Guidance on Order Issued 3/31/31 All BWR facilities January 9, 1981 Regarding with an Operating License Automatic Control Rod (OL) or Construction Insertion on Low Control Permit (CP)
Air Pressure 31-13 Jammed Source Rack in a 4/14/81 Specified Irradiator Gamma Irradiator licensees 81-14 Potential Overstress of 4/17/31 All pcwer reactor Shafts on Fisher Series facilities with an 9200 Butterfly Valves Operating License (OL) with Expandable 7 Rings 81-15 Degradation of Automatic 4/22/81 All power reactor ECCS Actuation Capability facilities with an by Isolation of Instrument Operating License (0L)
Lines or Construction Permit (CP) 81-16 Control Rod Drive System 4/23/81 All cower reactor Malfunctions facilities with an Operating License (OL) or Construction Permit (CP)
Enclosure