ML17331B454
| ML17331B454 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 10/30/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shields S PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA |
| References | |
| NUDOCS 8101050209 | |
| Download: ML17331B454 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 799 ROOSEVELT ROAD GLEN ELLYN.ILLINOIS60137 gg 30 1880 gy-3)4, Those on Attached Address I,isting:
This IE Information Notice No. 80-38 is forwarded to provide a noti-fication of a potential source of 'degradation that might occur in a safety related component over long term operation.
No specific action or written response is required at this time. If you have any questions related to
,i this matter, please contact this office.
Sincerely, James G. Kep 1 r Director
Enclosure:
IE Information Notice No. 80-38 cc w/encl:
Mr. D.
W. Kane, Sargent
& Lundy Reproduction Unit NRC 20b t/0 IO5 o20$
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 SSINS No.:
6835 Accession No.:
8008220180 IN-80-38 October 30, 1980 IE Information Notice No. 80-38:
CRACKING IN CHARGING PUMP CASING CLADDING Descri tion of Circumstances:
In January 1980 Commonwealth Edison Company (CECo) reported to the NRC that a radiographic examination had revealed crack indications in the cladding on the suction end plate of the lA charging pump at Zion Unit 1.
This cen-trifugal charging pump lA is one of two pumps installed in Zion Unit 1 for high head safety injection of borated water to the reactor loops.
These pumps are additionally utilized as charging pumps during normal operation.
ASME Section XI inservice inspection rules referenced in the plant technical specification requires pump examination only once during the 10 year service interval and this pump had been in service about 7 years.
The pumps are 2-1/2 inch, 11 stage, Type IJ manufactured by the Pacific Pumps Division of Dresser Industries.
The pump casing end assembly in the area of
- interest, Figure 1, consists of a suction end plate of A515 grade 60 carbon steel plate welded to the casing barrel forging of A266 class 1 carbon steel using an Inconel weldment.
The entire inner surface is clad with type 308 stainless steel applied by submerged arc welding.
An in-situ ultrasonic examination conducted in late April confirmed clad cracki ng indications at the barrel case to. end plate inner radius for approximately 330 degrees around the circumference and that the cracking possibly extended into the pump base material in the bottom 180 degrees of the assembly.
A review of the original radiographs revealed crack like indications in the clad overlay,
- however, not to the extent observed during this examination.
Subsequently, the entire suction end of the pump was removed and cross sections metallographically examined to further evaluate the nature and extent of the cracking.
It was determined that initiation and propagation of the clad cracks probably resulted from stress concentration and dilution effects in the initial corner bead pass due to the difficult access and bead sequencing required by the fairly sharp corner geometry.
Extension of the cracks at the base metal-clad interface ranged to a depth of 1/16 inch maximum in the l-l/2 inch thick base material.
These crack tip areas were well blunted and slightly cavitated from corrosion effects due lengthy exposure to the localized boric acid attack.
Examination of the crack morphology revealed that the clad cracking essentially arrested at the base metal-clad interface and that base metal corrosion progres-sed at a relatively slow rate.
The 1A charging pump was replaced with a new pump provided with a casing con-structed entirely of stainless steel.
The licensee is currently developing improved NDE procedures for examination of the three remaining pumps at the next refueling outage.
- Further, the licensee and pump manufacturer are developing repair procedures in the event cracks are discovered in the remaining pumps.
IN-80-38 October 30, 1980 Page 2 of 2 A corrosion evaluation provided CECo by Westinghouse indicates the corrosion rate of carbon steel subject to environmental conditions typical of the installed pumps is on the order of 2-1/2 to 4 mi ls per month.
Additionally, a stress analysis of the pump casing by the manufacturer using ASME Section III, Subsec-tion NC rules, indicates that at design conditions a flaw with depth of 0.763 inches could be. tolerated.
Based on the available information no immediate safety concern is indicated.
However, the observed conditions reveal a potential source of pump degradation over long term operations.
Therefore, to assure maximum availability, it appears prudent to perform a nondestructive examination of this pump type at the earliest practical time during the first code required in-service inspection interval and if cracking is confirmed, take appropriate corrective actions per the rules of ASME Section XI BP8V Code.
This Information Notice is provided as a notificaton of a potential source of degradation of a safety related component that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facility.
No specific action or response is requested at this time.
If you have any questions regarding this matter, please contract the director of the appropriate NRC Regional Office.
Enclosure:
Figure 1
RECENTLY ISSUED IE INFORMATION NOTICES IN 80-38 October 30, 1980 n ormatson Notice No.
80-37 80-36 Sub ect Containment cooler leaks and reactor cavity flooding at Indian Point Unit 2 Failure of Steam Generator Support Bolting Date of Issue 10/24/80 10/10/80 Issued to All nuclear powe~
facilities holding power reactor OLs or CPs All nuclear power reactor facilities holding power reactor OLs or CPs 80-35 Leaking and dislodged Iodine-124 implant seeds 10/10/80 All categories G and Gl medical licensees 80-34 80-33 Boron dilution of reactor 9/26/80 coolant during steam generator decontamination Determination of tel etherapy 9/15/80 timer accuracy All pressurized water reactor facilities holding power reactor OLs All teletherapy (G3) licensees 80-32 Clarification of certain requirements for Exclu-sive-use shipments of radioactive materials 8/12/80 All NRC and agreement state licensees 80-31 Maloperation of Gould-Brown Boveri Type 480 volt type K-600S and K-DON 600S circuit breakers 8/27/80 All light water reactor facilities holding OLs or CPs 80-30 Potential for unaccept-ab1 e interacti on between the control rod drive scram function and non-essential control air at certain GE BMR facilities 8/19/80 All boiling water reactor facilities holding power reactor OLs or CPs.
80-29 Broken studs on Terry turbine steam inlet flange 8/7/80 All light water reactor facilities holding power reactor OLs or CPs"
" Operating Licenses or Construction Permits
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RIII's CORPORATE ADDRES FOR OPERATING LICENSEES AND C TRUCTION PERMIT HOLDERS (BWR's and PWR's)
Docket No. 50-263 Docket No. 50-282 Docket No. 50-306 Northern States Power Company ATTN:
Mr. Dennis E. Gilberts Vice President Power Production and System Operation 414 Nicollet Mall Minneapolis, MN 55401 cc w/encl:
Mr.
W. A. Shamla, Plant Manager Mr. F.
PE Tierney, Jr.,
Plant Manager Central Files
- Director, NRR/DPM
Nuclear Engineer, MPCA Docket No. 50-546 Docket No. 50-547 Public Service of Indiana ATTN:
Mr. S.
W. Shields Senior Vice President Nuclear Division Post Office Box 190 New Washington, IN 47162 cc w/encl:
Mr. Steve J. Brewer, Nuclear
~
~
S ety and Licensing Supervisor ral Files
- Director, NRR/DPM
- LeBoeuf, Lamb, Leiby 6 MacRae Mr. Dave Martin, Office of the Attorney General Mr. John R. Galloway, Staff Director, Environment, Energy and Natural Resources Subcommittee
RIIIis CORPORATE ADDRE~ FOR OPERATING LICENSEES AND TRVCTION PERMIT HOLDERS (BWR's and PWR's)
Docket No. 50-346 Toledo Edison Company ATTN:
Mr. Richard P.
Grouse Vice President Nuclear Edison Plaza 300 Madison Avenue
- Toledo, OH 436&2 cc w/encl:
Mr. T. Murray, Station Superintendent Central Files
- Director, NRR/DPM
- Director, NRR/DOR AEOD Resident Inspector, RIII PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission Helen W. Evans, State of Ohio Docket No. 50-483 Docket No. 50-486 Union Electric Company ATTN:
Mr. John K. Bryan Vice President - Nuclear P.
O.
Box 149 St. Louis, MO 63166 cc w/encl:
Mr. W. H. Weber,
- Manager, Nuclear Construction Central Files
- Director, NRR/DPM
- Director, NRR/DOR PDR Local PDR NSIC TIC Region I 6 IV Ms. K. Drey Mr. Ronald Fluegge, Utility Division, Missouri Public Service Commission
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 799 ROOSEVELT ROAD GLEN ELLYN.ILLINOIS60137
~30 1980 Those on Attached Address Listing:
This IE Information Notice No. 80-38 is forwarded to provide a noti-fication of a potential source of degradation that might occur in a safety related component over long term operation.
No specific action or written response is required at this time. If you have any questions related to this matter, please contact this office.
Sincerely, James G. Kep 1 r Director
Enclosure:
IE Information Notice No. 80-38 cc w/encl:
Hr. D.
W. Kane, Sargent 6 Lundy Reproduction Unit NRC 20b
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