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81M3M02 Z I c'D 004 Q IN 81-21 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 July 21, 1981 IE INFORMATION NOTICE NO. 81-21:
POTENTIAL LOSS OF DIRECT ACCESS TO ULTIMATE HEAT SINK Description of Circumstances:
IE Bulletin 81-03, issued April 10, 1981, requested licensees to take certain actions to prevent and detect flow blockage caused by Asiatic clams and mussels.
Since then, one event at San Onofre Unit 1 and two events at the Brunswick Station have indicated that situations not explicity discussed in Bulletin 81-03 may occur and result in a loss of direct access to the ultinate heat sink.
These l
situations are:
l 1.
Debris from shell fish other than Asiatic clams and mussels may cause flow blockage problems essentially identical to those described in the bulletin.
2.
Flow blockage in heat exchangers can cause high pressure drops that, in turn, deform baffles, allowing bypass flow and reducing the pressure drop to near normal values. Once this occurs, heat exchanger flow blockage may not be detectable by pressure drop measurements.
3.
Change in operating conditions.
(A lengthy outage with no flow through seawater systems appears to have permitted a buildup of mussels in systems where previous periodic inspections over more than a ten year period showed no appreciable prcblem.)
We are currently reviewing these events and the responses of the licensees to IEB 81-03. We expect 'icensees are performing the actions specified in IEB 81-03 such that cooling water flow blockage from any shell fish is prevented or minimized, and is detected before safety components become inoperable.
On June 9, 1981, San Onofre Nuclear Generating Station Unit No. I reported that as a result of a low saltwater coolant flow rate indication and an apparent neeJ for valve maintenance, a piping elbow on the saltwater discharge line from component cooling heat exchanger E-20A was removed by the licnsee just upstream of butterfly valve 12"-50-415 to permit visual inspection.
An examination revealed growth of some form of sea mollusk such that the cross-sectional diameter of the piping was reduced.
The movement of the butterfly valve was impaired and some blockage of the heat exchanger tube sheet ~had occurred.
Evaluation of the event at San Onofre is continuing.
However, the prolonged (since April 1980) reactor shutdown for refueling and steam generator repair is believed to have caused the prcblem since previous routine inspections conducted since 1968 at 19 month intervals had not revealed mollusks during normal periods of operation.
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IN 81-21 July 21, 1981 Page 2 of 3 Two events at Brunswick involved service water flow blockage and inoperability of redundant residual heat removal (RHR) heat exchangers, priniarily due to oyster shells blocking the service water flow through the heat exchanger tubes.
On April 25, 1981, at Brunswick Unit 1, while in cold shutdown during a maintenance outage, the normal decay heat removal system was lost when the single RHR heat exchanger in service failed.
The failure occurred when the starting of a second RHR service water pump caused the failure of a baffle in the waterbox of the RHR heat exchanger, allowing cooling water to bypass the tube bundle. The heat exchanger is U-tube type, with the service water inlet and outlet separated by a baffle.
The copper-nickel baffle which was welded to the copper-nickel tubesheet deflected and failed when increased pressure was produced by starting the second service water pump.
The redundant heat exchanger was inoperable due to maintenance in progress to repair its baffle which had previously deflected (LER 3-81-32, dated May 19, 1981).
The licensee pro Qtly established an alternate heat removal alignment using the spent fuel pool pumps and heat exchangers.
As a result of the problems discovered with Unit 1 RHR heat exchangers, a special inspection of the Unit 2 RHR heat exchangers was performed while Unit 2 was at power.
Examination of RHR heat exchanger 2A using ultrasonic techniques indicated no baffle displacement but flow testing indicated an excessive pressure drop across the heat exchanger.
This heat exchanger was declared inoperable.
Examination of the 2B RHR heat exchanger using ultrasonic and differential pressure measurements indicated that the baffle plate was damaged. The licensee initiated a shutdown using the 2A RHR heat exchanger at reduced capacity (LER 2-81-49, dated May 20, 1981).
The failure of the baffle was attributed to excessive differential pressure caused by blockage of the heat exchanger tubes. The blockage was caused by the shells of oysters with minor amounts of other types of shells which were swept into the heads of the heat exchangers since they are the low point in the serlice water system.
The shells resulted from an infestatic, of oysters growing primarily in the 30" header from the intake structure to the reactor building.
As the oysters died their upper snells detached and were swept into the RHR heat exchangers where they collected.
Small amounts of shelis were found in other heat exchangers cooled by service water. Most of the operating BWRs use U-tube heat exchangers in the RHR system.
(The heat exchangers used at Brunswick were manufactured by Perflex Corooration and are identified as type CEO, size 52-8-144.)
The observed failures raise a question on the adequacy of the baffle design to withstand differential pressures that could reasonably be expected during long term post accident operation. However, it s50uld be noted that since the oaffles at Brunswick are solid copper-nickel as are the tubesheets and the water boxes are copper nickel clad, the :,trength of the baffles and the baffle welds is somewhat less than similar heat exchangers made from carbon steel.
Therefore, heat exchangers in other BWR's may be able to tolerate higher differential pressure than that at Brunswick without baffle deflection.
(Brunswick opted for copper-nickel due to its high corrosion and fouling resistance in a salt water environment.)
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IN 81-21 July 21,1981 Page 3 of 3 The use of differential pressure (dp) sensing between inlet and outlet to determine heat exchanger operability should consider that baffle failure could give an acceptable dp and flow indications and thereby mask incapability for heat removal.
However, it is noted that shell blockage in a single pass, straight-through heat exchanger can readily be detected by flow and dp measurement.
Evaluation of the events at Brunswick is still continuing.
Under conditions of an inoperable RHR system, heat rejection to the ultimate heat sink is typically through the main condenser or through the spent fuel pool coolers.
This latter path consists of the spent fuel pool pumps and heat exchanger with the reactor building closed cooling water system as an intermediate system which transfers the heat to the service water sy3 tem via a single pass heat exchanger. These two means (i.e., main condenser or spent fuel pool) are not considered to be reliable long term system alignments under accident conditions.
This information is provided as a notification of a possibly cignificant matter that is still under review by the NRC staff.
The evert', at Brunswick and San Onofre emphasize the need for licensees to initiato appropriate actions as requested by IEB 81-03 for any credible type of shell fish or other marine organisms; e.g., fresh water sponges, (not only asiatic clams and mussels).
In case the continuing NRC review finds that specific licensee actions would be appropriate, a supplement to IEB Bulletin 81-03 may be issued.
In the interim, we expect that licensees will review this information for applicability to their facilities.
f I
No written response to this information is required.
If you need additional information regarding this matter, please contact the Director of the appro-priate NRC Regional Office.
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Attachment:
Recently issued IE Information Notices i
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Attachment IN 81-21 July 21,1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 81-20 Test Failures of Electrical 7/13/81 All power reactor Penetration Assemblies facilities with an OL or CP 81-19 Lost Parts in Primary 7/6/81 All power reactor Coolant System facilities with an OL or CP 81-18 Excessive Radiation 6/23/81 Specified licensees Exposures to the Fingers of holding Byproduct Three Individuals Incurred licenses During Cleaning and Wipe i
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 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 ALtomatic Control Rod Insertion on Low Control Air Pressure 81-11 Alternate Rod Insertion 3/30/81 All BWR facilities for BWR Scram Represents with an OL or CP a Potential P-th for Loss of Primary Coolant OL = Operating Licenses CP = Construction Permits
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Cincinnati Gas and Electric Company Zimmer (50-358)
The Cleveland Electric Illuminating Company Periy 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
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Dresden 1, 2, 3 (50-10, 50-237, 50-249) g i
La Salle 1, 2 (50-373, 50-374)
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Zion 1, 2 (50-295, 50-304)
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Consumers Power Company
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Big Rock Point (50-155)
Palisades (50-255)
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Midland 1, 2 (50-329, 50-330)
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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 Bailly (50-367)
Northern States Pc._r Company 0l Monticello (50-263) t 0 Prairie Icland 1, 2 (50-282, 50-306)
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Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
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Toledo Edison Company
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Davis-Besse 1 (50-346)
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Union Electric Company Callaway 1, 2 (40-483, 50-486)
Wiscotisin Electric Power Company Point Beach 1, 2 (~0-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305)
Illinois Department of Nuclear Safety Gary N. Wright, Deputy Director
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