ML19242A805
| ML19242A805 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 07/17/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7908060362 | |
| Download: ML19242A805 (2) | |
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W UNITED ST ATES
/ssk* "8Gq 'g NUCLE AR REGULATORY COMMISSION
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JUL 111979 In Reply Refer To:
RII:JPO (50-338; 50-339' 50-404, 50-405 50 *480, 50-281 Virginia Eiretric and rover Company Atto:
W. L. Proffitt Senior Vice President, Power P. O. Box 26666 Richmond, Virginia 23261 Gentlemen:
fa This Information Notice is provided as an early notification oIt is expec lities. No possibly significant natter.
the inf on.stion f or possible applicability to their f aci be aware response is requested at this time bevever licensees shouldto operating i
that the NRC is evaluating the issuance of a Bullet n t
requesting information on previous inservice inspections of stagnan borated water systens and requesting inspection of systems w IULC Regional not been inspected recently.this matter, pleast contact the Director of Office.
Sincerely, e
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Director
Enclosure:
1.
IE Information Notice Ito. 79-19 Listing of IE Inf ormation 2.
Notices Issued in 1979 b?:fn f s t r ' ti < w
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JUL 171979 Virginia Electric and Power Company cc w/ encl:
W. R. Cartwright, !Ltation Manager Post Office Box 402 23117 Mineral, Virginia P. C. Perry ~
Senior Resident Engineer
/Jifice Box 38 Post 23117 Mine el, Virgiuis W. L. Stewart, Manager Post Office Box 315 23883 Surry, Virginia e
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EhTORCEMEh'I WASHINGTON,
D. C.
20555 July 17, 1979 IE Information Notice No. 79-19 PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT PWR PLANTS Description t,f Circumstances:
During the period of November 1974 to Ecbruary 1977 a number of cracking incidents have been experienced in safety-related stainless steel piping systems and portions of systems which contain oxygenated, stagnant or t.asentia hese cracks Metallurgical investigations revealed stagnant borated water.
of f ected zone of 8-inch to 10-inch t,pe 304 material occurred in the veld heat (schedule 10 and 40), initiating on the piping I.D. surf ace and propagating in either an intergranular or transgranular mode typical of Stress Corrosion Analysis indicated the probable corrodents to be chloride and oxygen Cracking.
Plants affected up to this t he were contamination in the affected systems.
Arkansas Nuclear Unit 1, R. E. Ginna, H.B. Robinson Unit 2, Crystal River Unit 3, 1, and Surry Units 1 and 2.
The NRC issued Circular 76-06 San Onofre Unit (copy attached) in view of the apparent generic nature of the problem.
I which began in February During the refueling outage of Three Mile Island Unit (5) through-vall cracks at velds of this year, visual inspections disclosed five in the spcnt fuel cooling system piping and one (1) at a veld in This initial identification of removal system.
tests.
up and later confirmed by liquid penetrant (LEP.) dated Wy 16, cracking was reported to the NRC in a Licensee Event Report A preliminary metallurgical analysis was performed by the licenew on a from the spent fuel cooling system.
1979.
section of cracked and leaking veld joint The conclusion of this analysis was that cracking was due to Intergranular Stress The cracking was Corrosion Cracking (IGSCC) originating on the pipe I.D.affected zone whe localized to the heat In addition to the main h during velding.
sensitized (precipitated carbides several locations in through-wall crack, incipient cracks were observed atfusion area where a siniscule the veld heat af fected zone including the veld rootThe stresses responsible for cra lack of fusion had occurred.
l d to be pr'marily residual velding stresses in as auch as the esiculated app ie There is no conclusive stressee oere found to be less than code design limits.this time to id Further analytical efforts in this area and on evidencr at e
promoted this ICSCC attack.
other system velds is being pursued.
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i July 17, 1979 IE Information Notice No. 79-19 Page 2 of 2 Based on the above anslysis and visual leaks, the lict nsee initiated a broad based ultrasonic examination of potentially af'.ected systems utilizin The systems exa=ined included.he spent fuel, decay special techniques. removal, makeup and purification, and reactor building spray heat which contain stagnant or internittently stagnant,These systems ran water storage tank suction), are type 304 stainless steeResults of these examinations wer ments.
to schedule 40 thickness respectively.as an update to the May 16, 1979 LEE.
30, 1979 reported to the NRC on June 10, 1979 has identified 206 velds out The ultrasonic inspection as of July king randomly of 946 inspected having UT indications characteristic of cracthe afo
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six of the crack indications distributed throughout It is important te note that i
lines were found in 21/2-inch diameter pipe of the high pressure inje of the above systems.
for check valves. All inside containment.
system except are nonisolable from the main coolant injection lines containing of the six cracks were found in two high pressureNo cracks were found in the h The ultrascsic stagnated borated water. lines which were o:casionally flushed during makeup o f the problem.
examination is continuing in order to delineate the extent o
Enclosures:
1.
List of Information Notices Issued in 1979
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i IE Information Notice No. 79-19 Page 1 of 2 July 17, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Date Issued To Information Subject Issued Notice No.
79-01 Bergen-Paterson Hydraulic 2/2/79 All power reactor facilities with an Shock and Sway Arrestor OL or a CP 2/2/79 All Fuel Facilities 79-02 Atte=pted Ixtortion -
Low Enriched Uranium Limitorque Valve Geared 2/9/79 All power reactor f acilities with an 79-03 Limit Switch Lubricant OL or a CP 2/16/79 All power reactor 7 9- 04 Degradation of facilities with an Engineered OL or a CP Safety Features Use of Improper Materials 3/21/79 All power reactor facilities with an 79-05 in Safety-Related Co=ponents OL or CP Stress Analysis of 3/23/79 All Bolders of Reactor OL or CP 79-06 Saf ety-Related Piping 79-07 Rupture of Radwaste Tanks 3/26/79 All power reactor facilities with an OL or CP 79-08 Interconnection of 3/28/79 All power reactor facilities with an Contaminated Systems with OL and Pu Processing Service Air Systeme Used fuel facilities As the Source of Breathing Air 3/30/79 All power reactor 79-09 Spill of Radioactively f acilities with an Contaminated Resin OL 79-10 Nonconforming Pipe 4/16/79 All power reactor facilitirs with a Support Struts CP Lower Reactor Vessel Head 5/7/79 All holders cf Reactor 79-11 OLs and cps ansulation Support Problem
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IE Infor.aation Notice No. 79-19 Page 2 of 2 July 17, 1979 LISTING OF IE INFORMATION NOTICES ISSUED IN 1979 Date Issued To Information Subject Issued Notice No.
79-12" Attempted Damage to New 5/11/79 All Fuel Facilities Research Reactors, Fuel Assemblies and Poner Reactors with r_. OL or CP 79-13 Indication of Low Water 5/29/79 All Holders of Reactor OLs and cps Level in the Oystur ', reek Reactor 79-14 NRC Position of Electrical 6/11/79 All Power Reactor Facilities with a Cable Support Systems CP 79-15 Deficient Procedures 6/7/79 All Holders of Reactor OLs and cps 79-16 Nuclear Incident at Three 6/22/79 All Research Reactors and Test Reactore Mile Island with OLs Source Holder Assembly Da:nage 6/20/79 All Holders of Reactor 79-17 Damage From Misfit Between OLs and cps Assembly and Reactor Upper Grid Plate 79-18 Skylab Reentry 7/5/79 All Holders of Reactor OLs N
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