ML19254E977
| ML19254E977 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 10/19/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 7911050205 | |
| Download: ML19254E977 (1) | |
Text
.
/p* **ouq'o, UNITED STATES NUCLEAR REGULATORY COMMISSION
~,
n
.E REGION 111 o,
[
799 ROOSEVELT ROAD d
GLEN ELLYN. lLLINOIS 60137 OCT 191979 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:
Enclosed is IE Circular No. 79-21, " Prevention of Unplanned Releases of Radioactivity," which provides information on inadvertent releases /on-site spills of radioattivity. Should you have any questions related to the enclosed suggested preventi'e measures, please contact this office.
Sincerely, w dd-
[/
ames G. Keppler V Director
Enclosures:
1.
IE Ciruclar No. 79-21 2.
List of IE Circulars Issued in the Last Six Months cc w/encls:
Mr. G. A. Reed, Plant Manager Central Files Director, NRR/DPM Director, NRR/ DOR C. M. Trammell, ORL/NRR PDR Local PDR NSIC TIC Sandra A. Bast, Lakeshore Citizens for Safe EnergyLJ 'Sc /F )L fl10 0 5 +) 205
4 Accession No.: 7908220128 SSINS: 6830 UNITED STATES ]D 3 NUCLEAR REGULATORY COMMISSION ,efaJ OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 October 19, 1979 IE Circular.No. 79-21 PREVENTION OF UNPLANKED RELEASES OF RADI0 ACTIVITY Numerous incidents of unplannti releases of radioactivity have been reported to the NRL within the past few months. These incidents of leaks, overflows and spills have resulted in contamination of avers outside of plant buildings. The attached table provides you with summary information on these events, their apparent causes, the radiological consequences and the corrective actions. We believe that a number of these incidents could have been avoided and prevln-tive actions for these types of unplanned releases,should be instituted by all reactor licensees. Based on the reported incidents, the following preventive measures can minimize the occurrence of such events. 1. Review of procedures for transfer of radioactive liquids. Errors in written procedures have led to mistakes in valve line-ups and tank overflows. Written procedures, including check lists for valve line-ups, should be denbped and followed for operations which could cause s'.iills of radioactivity. Management controls, including audits, should u9 employed to assure verbatim compliance with such procedures. 2. Review of "rs built" systems having the potential of inadvertent releases because of design or construction errors. Consider items such as: a. Tank overflows should be routed to liquid radwaste tanks. b. Storm drains should be located away from areas with a high potential for spills. c. Consideration should be given to drip pans under equipment, such as pumps and valves, from which leakage is expected. d. Cofferdams should be installed under doors to areas with a potential for radioactive spills. e. Preoperational testing should verify that crossconnects do not exist that would permit radioactivity to flow from operating unit (s) to unit (s) under construction. 3. Periodically functionally test and perform inspections to verify integrity of systems that could cause an inadvertent release. Excessive wear and corrosion degradation have occurred in valves, seals and piping systems to cause leaks. New permanent and temporary piping systems should be 128 130
IE Circular No. 79-21 October 19, 1979 Page 2 of 2 hydrostatically tested prior to first use. Underground piping should be periodically hydrostatically tested. Preventive maintenance programs should be implemented.nd identified problems, such as leaking equipment and plugged floor drains, should be promptly repaired. No written response to this Circular is required. If you require additional information regarding this subject,. contact the Director of the appcopriate NRC Regional Office
Enclosure:
Recent Events of Radioactive Contamination O a e 6 e ~
N p m I rm s L'7 w RECENT EVENTS OF RADI0 ACTIVE CONTAMINATION OUTSIDE BUILDINGS a e Plant Date Apparent cause Radiological Consequence ,'dcenseeFollowupAction 4 Turkey Point 3/4 6/11/70 Operator Error 900 gallons of water processed Total of 0.01 aci of Co-58 Procedure reviewed by radwasta system overflowed Co-60 released to storm with operator. from waste processing tank because drain of error in valve line-bp The f.ax. Bldg. floor drain backed up to the on site store drain. 'The drain system discharged to an on-site underground tile bed. ~ Palisades 6/9/79 Inadequate Procedures -5 Contaminated secondary system Resins activity at 10 The monitoring procedure spent powdered -esins were trans-pCf/cc; total release to determine 4tefouting i ferred to an outside storage bin about 10 pCi of Co-60 of the secondary ~ spent without monitoring. Rain storm resins has been replaced caused resins to overficw the by a procedure requiring storage bin and be washed to Lake all spent secondary systa Michigan via stars drain. resins to be handled and shipped as solid waste. Surry 2 5/21/79 Equipment Failure. Core spray pump isolation 5 gallons spilled; 2 gallons Leak repaired Three 55-valve leaked durirg RWST outside of bldg. gallon drums of con-transfer to Spent Fuel Pit. 0.02 pCi/cc, Co-58 taminated dirt removed' Water leaked to Safeguards 0.035 pCi/cc,11-3. BIdg. floor. Floor drain s plugged; resulted in water flow out of building. Enclosure IE Circular No. 79-21 Page 1 of 3
~ Plant Date Apparent Cause Radiological Consequence t.icensee Follow-up Action Oconee 3 S/16/79 Operational Error. 5/17/79 Normally closed valve left 2000 gallons overflowed; Procedure reviewed with. open during pumping of fuel 200-300 gallons out of operating personnel. Areas transfer canal water to BWST. building,4 outside of Aux. Bldg. decon-Water overflowed the BWST io 3.1 x 10 pCi/cc,1-131. taminated. C Aux. Bldg. penetration room, [ down a stairway to area outside Aux. 81de. to Farley 1/2 5/14/79 Design Error. N Decontamination drains 1860 gallons of contam-Review all drains from from Unit I routed to Unit inated water discharged Unit I and Unit 2. Six such 2 sump and released to to pond. Estimated max-drains were located and flush pond via tendon inum activity of 10 mci - plugged. access area. Those drains Co-58. Pond mud activity should have been routed < 500 pCi/Kg. No pond to Unit 1 floor drain water activity detected. system. Dyster Creek 4/17/79 Equipment. Failure. Leakage from a Drywell Water in pipe tunnel DEDT line repaired. Equipment Drain Tank (DEDT) 9 0.3 pCi/cc and soil Structure to enclose pipe line. in vicinity of penetra-from Rx. Bldg. to main tion to the reactor pipe tunnel to con-building were found to structed. be contaminated. Enclosure IE Circular No. 79-21 Page 2 of 3 j
e Plant Date Apparent Cause Radiological Consequence Licensee Follow-up Action Brunswick 1 5/8-9/79 Operator Error and Equipment Failure. Air mixing valve of RWCU Total release of 12 mci Tank transfer procedure " v backwash tank lef t open of corrosion product, reviewed. Caution tag C after liquid transfer. on valve installed. Dried tank residue released Loose access cover re-c., to building ventilation paired. w system via loose access cover. N Hatch 1/2 3/20/79 Construction Error.., Buried temporary line for Highest on-site gr und Temporary line broken 5 N tank in yard for feed-water of 3 x 10 pCf/1 - inside turbine building 7 water heaters was not capped H Highest qtr. avg. off-and capped. site outfal.1 of subsugface after tank removal. Rx steam released into ground from drainage was 1.8 x 10 buried line. pCi/1. North Anna 9/25/79 Construction Error Relief valve on the volume Airborne radioactivity Still under investigation control tank lifted thus trans-levels in the Auxiliary ferring reactor coolant to the Building reached 150 X high level waste drain tank and MPCs. Auxiliary Building releasing dissolved noble gases was evacuated. to the auxiliary building via the waste system vent. An incorrectly connected vent line allowed venting directly to the auxiliary building. I Enclosure IE Circular No. 79-21 Page 3 of.3 s 7
IE Circular No. 79-21 Enclosure October 19, 1979 Page 1 of 2 LISTING OF IE CIRCULARS ISSUED IN LAST SIX MONTHS 3 Circular Subject Date of Issued to No. Issue 79-07 Unexpected Speed Increase 5/2/79 All Holders of of Reactor Recirculation BWR OL's or CP's MG Set Resulted in Reactor Power Increase 79-08 Attempted Extortion - Low 5/18/79 All Fuel Facilities Enriched Uranium Licensed by NRC 79-09 Occurrences of Split or 6/22/79 All Materials Punctured Regulator Diaphragms Priority I, Fuel In Certain Self Contained Cycle and Operating Breathing Apparatus Reactor Licenseer 79-10 Pipefittings Manufactured 6/26/79 All Power Reactor from Unaccertable Material Licensees with a CP and/or OL 79-11 Design / Construction 6/27/79 All Applicants Interface Problem for, and Holders of Power Reactor cps 79-12 Potential Diesel Generator 6/28/79 All Power Reactors Turbocharger Problem Operating Facilities and all Utilities having a CP 79-13 Replacement of Diesel 7/10/79 All Power Reactor Fire Pump Starting , Operating Facilities Contactors and all Utilities having a CP 79-14 Unauthorized Procurement and 7/13/79 All Medical Licensees Distribution of XE-133 except Teletheraphy Medical Licensees and to all Radiopharmaceu-tical Suppliers 79-15 Bursting of High Pressure Hose 8/8/79 All Materials Priority I, andMalfunctionofjRelief Fuel. Cycle and Operating Valve "0" Ring in Eertain Self-Power Reactor Licensees ContainedBreathidgApparatus ./ 12f5 135
IE Circular No. 79-21 Enclosure Octcber 19, 1979 Page 2 of 2 LISTING OF IE CIRCULARS ISSUED IN LAST SIX MONTHS tircular Subject Date of Issued tn No. Issued 79-16 Excessive Radiation Exposures 8/16/79 All Radiography To Members Of The General Public Licensees And A Radiographer 79-17 Contact Problem in 58-12 8/14/79 All Power Reactor Switches on General Electric Licensees with a CP Company Metalclad Circuit and/or OL Breakers 79-18 Proper Installation of 9/10/79 All Holders of a Target Rock Safety-Relief Power Reactor OL Valves or CP 79-19 tcose Locking Devices on 9/13/79 All Power Reactor Ingersoll-Rand Pumps Operating facilities and all utilities having a CP 79-20 Failure Of GTE Sylvania Relay 9/24/79 All utilities having a Type PH Bulletin 7305, Catalog CP SU12-11-AC With A 120V AC Coil 12f7 136 e e e [}}