ML19225C533
| ML19225C533 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/11/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 7907310337 | |
| Download: ML19225C533 (1) | |
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UNITED STATES 4
E ')
' '7, NUCLEAR REGULATORY COMMISSION PDR E
REGION lli
'o,.y @ [ f' 799 ROOSEVELT ROAD s, v GLEN ELLYN, ILLINOls 60137
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Docket No. 50-461 Docket No. 50-462 Illinois Power Company ATTN:
Mr. W. C. Gerstner Executive Vice President 500 South 27th Street Decatur, IL 52525 Gentlemen:
The enclosed IE Bulletin No. 79-15 is forwarded to you for action.
A written response is required.
If you desire additional iaformation regarding this matter, please contact this office.
Sincerely, f<Y~JamesG.Keppler
()
Director
Enclosures:
1.
Listing of IE Bulletins Issued in Last 12 Months cc w/ encl:
Central Files Director, NRR/DPM Director, NPJt/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General
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790 6 0337 4,y 7 7
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENTORCEMENT REGION III July 1.., 1979 IE Eulletin No. 79-15 DEEP DRAFT PUMP DEFICIENCIES
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Description of Circumstances:
On October 20, 1978, Com=onwealth Edison Company reported that manufacturing deficiencies had been identified in new high pressure core spray, low pressure core spray, and residual neat removal pumps manufactured by Ingersoll-Rand (I-R)
Company, Cameron Pu=p Division.
Each of these pu=ps is a vertical turbine pe=p with impellers located in bowls
-in a sump or a self contained barrel. The motor (prime mover) is located at the highest pu=p elevation to take into account maximum flooding at the site
.or space considerations. The suction is at the lower end of the pu=p while the discharge head is just below the driver. Bearings supporting the vertical shaft seg=ents (usually 5 to 10 segments) are either self lubricated, force fed (lubricated by fluid being pu= ped), or oil lubricated and maintained within their own isolated system. These pumps are designated as " Deep Draft".
Figures 1&2 show typical outlines of such pumps.
The internal deficiencies, identified through dimensional and visual inspections were as follows:
Low Pressure Core Spray Pu=ps (I-R Model No. 29APKD-5) (Date of Manufacture -
Feburary 1973)
Loose impeller bolts and bolts i= properly staked Loose key - keyway fit Excessive runout on pump shcft Bearing showed wear Bearing clearance exceeded recommended tolerance Coupling thread galled Wear ring clearance out-of-specification I=peller-to-shaft clearance out of specification Cracks found in second-and-third-stage impellers Stuffing box bushings were severely galled High Pressure Core Spray Pu=ps (I-R Model No.12X20KD) (Date of Manufacture -
September 1972)
Bearing clearance exceeded reco= mended toleranet Wear ring clearance out-of-opecification Bearings showed wear 1000'7180125 h d. ci onC
&c)
IE Bulletin No. 79-15 July 11,1979 Bearing loose in casing
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Excessive runout on pump shaft
.. Wear ring lock screws missing on eighth stage Shrink fit bearing ca=e out of casing during pump shaft removal -
casing sleeve socket found to be egg shaped Residual Heat Removal Pu=ps (I-R Model No.
December 1972) 29APKD-3) (Date of Manufacture -
Loose impeller bolts and bolts not properly staked Excessive runout on pu=p shaft Bearing found cracked Bearing clearance out-of-specification Couplings cut because galling prevented disassembly Wear ring clearance out-of-specification The above deficiencies were identified at a facility under construction 1978, similar deficiencies in deep draf t In pumps were identified at three other facilities (North Anna 1 & 2, Surry 1 & 2, Beaver Valley 1).
these pumps involved design and workmanship deficiencies which required exte Problems with sive inspection, replacement of parts and major redesign.
n-The manufacturers involved in these cases were Ingersoll-Rand, Bingham-Willamette and Byron Jackson.
locations included:Some of the measures taian to assure pu=p operability at these 1.
Pu=p shaft bearing redesign 2.
Colu=n redesign (stiffening) to i= prove vibration response 3.
Upgraded pu=p align =ent procedures 4.
Pu=p fluid inlet condition reevaluation and redesign S.
Extensive testing The observed deficiencies spanning the past 1 1/2 years indicate that pumps of this class may not be sufficiently reliable particularly when utilized in ECCS and RER applications where long term cooling capability is required following a lOCA or similar event.
Action to be Taken by Licensees and Permir Holders:
All holders of reactor operating licenses and construction permits shall provide the following information within 60 days of this letter.
1.
The number of deep draf t pumps similar to those shown in Figures 1 and 2 utilized in safety related applications in each facility.
2.
Manufacturer, model, capacity and plant application.
442 2:?0
IE Bulletin No. 79-15 July 11, 1979 3.
Overall dimensions of pu=ps.
4.
Su= mary of startup, testing and routine mata.tenance history.
5.
Operational problems and major repair efforts.
6.
The longest interval thct each pu=p has been available for operation
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without corrective maintenance.
Identify the number of cycles of opera-tion during this interval, the duratien of each cycle and the operating mode (s) (recirculation, rated flow, etc.).
Identify the longest con-tinuous operation at or near rated flow conditions for each pu=p and the status of the pump operability at the end of the run.
In addition licensees shall accumulate and make available for inspection at the licensees plant site the following infor=ation on the above identified pumps.
1.
Drawings, sectional asse=blies and parts l'.st.
2.
Detailed history of pu=p maintenance (alignment, parts replacerent, etc) including bearing wear data, replacement frequency and a comparison with the manufacturers rated life for wearing surfaces.
3.
Quality assurance and reliability testing requirements.
4.
Design specifications 5.
Results of tests perfor=ed durirs operation or prior to licensing.
6.
Details of the procedures used to align the pu=p column.
For those cases where the maintenance or cperating history of a particular pump indicates that the design specifications are not being met, initiate appropriate actions that will demonstrate conformance to design requirements.
Provide a description of planned actions within 60 days including a schedule for implementation of any actions that will not be completed within 120 dsys.
In addition describe any planned or completed tests involving long term opera-tion of prototypes or pumps of similar design, which demonstrate the long term operability of such deep draf t pu=ps at your facility.
Approved by GAO, B180225 (R0072), clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.
Enclosure:
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IE Bulletin No. 79-15 Enclosure July 11,1979 Page 1 of 4 LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
79-14 Seismic Analyses for 6/2/79 All Power Reactor As-Built Safety-Related facilities with an Piping System OL or a CP 79-13 Cracking In Feedwater 6/25/79 All FWRs with an System Piping OL for action. All BWRs with a CP for infor=ation.
79-02 Pipe Support Base Plate 6/21/79 All Power Re4u*or (Rev. 1)
Designs Using Cr rete Fat-111 ties with an Expansion Anchor Bolts 91 or a CP 79-12 Short Period Scrams at 5/31/79 All GE BWR Facilities BWR Facilities with an OL 79-11 Faulty overcurrent Trip 5/22/79 All Power Reactor Devite in Circuit Breakers Facilities with an for Engineered Safety OL or a CP Syste=s 79-10 Requalification Training 5/11/79 All Power Reactor Program Statistics Facilities with an OL 79-09 Frilures of GE Type AK-2 4/17/79 All Power Reactor Circuit Breaker in Safety Facilities with an Related Systems OL or CP 79-08 Events Relevant to BWR 4/14/79 All BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seis.ic Stress Analysis 4/14/79 All Pever Reactor of S fety-Related Piping Facilities with an OL or CP
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IE Bulletin No. 79-15 Enclosure July ll, 1979 Page 2 of 4
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LISTING OF IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Is To No.79-06B Review of Operational 4/14/79 AllCombu$tionEngineer-Errors and System Mis-ing Designed Pressurized alignments Identified Water Power Reactor During the Three Mile Facilities with an Island Incident Operating Licensee 7 9-06A Review of Operat12nal 4/18/79 All Pressurized Water (Rev 1)
Errors and Syster Mis-Powe:: Reactor Facilities alignments Identified of testinghouse Design r
During the Three Mile wit n an OL Island Incident 79-06A Review of Operational 4/14/79 All Pressur red Water Errors and System his-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island Incident 79-06 Review of Operational 4/11/79 All Pressurized Water Errors and Systen Mis-i over Reactors with an align =ents Identified OL except B&W facilities During the Three Mile Island Incident 79-05A Nuclear Incident at 4/5/79 All B&W Power Reactor Three Mile Island Facilities with an OL 79-05 Nuclear Incident at 4/2/79 All Power Reactor Three Mile Island Facilities with an OL and CP
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IE Bulletin No. 79-15 Enclosure July 11, 1979 Page 3 of 4 LISTING OF I4 BULLETINS ISSUED IN LAST WELVE MONTHS Bulletin Subject Este Issued Issued To No.
79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an Manufactured by Velan OL or CP Engineering Corporation 78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 79-03 Longitudinal Welds Defects 3/12/79 All Power Reactor In ASME SA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstown Welding and Engineering Co.
79-02 Pipe Support Base Plate 3/2/70 All Poser Reactor Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or CP 79-OlA Environmental Qualification 6/6/79 All Power Reactor of Class lE Equipnent Facilities with an (Deficiencies in the Envi-OL or CP ronmental Qualification of ASCO Solenoid Valves) 79-01 Environmental Qualification 2/8/79 All Power Reactor of Class IE Equipnent Facilities with an OL or CP 78-14 Deterioration of Buna-N 12/19/78 All GE BWR facilities Component In ASCO with an OL or CP Solenoids b $. -)
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IE Bulletin No. 79-15 Enclosure July 11, 1979 Page 4 of 4 LISTIhv 0F IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subj ect Date Issued Issued To No.
78-13 Failures in Source Heads 10/27/78 All genefal and of Kay-Ray, Inc., Gauges specific licensees Models 7050, 7u504, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B gauges78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities v1th an Vessel Welds OL or CP 7f-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-11 Framination of Mark I 7/21/78 BWR Power Reactor Containment Torus Welds Facilities for action:
Peach Bottom 2 and 3, Quad Citier I and 2, Hatch 1, Monticello and Vermont Yankee 442 237
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