IR 05000289/1974019
| ML19256D408 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/18/1974 |
| From: | Folsom S, Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D403 | List: |
| References | |
| 50-289-74-19, NUDOCS 7910180755 | |
| Download: ML19256D408 (7) | |
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U.S. AT0!!IC ENERGY C0:t!ISSION
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DIRECTORATE 0" REGUL\\ TORY OPERATIONS
REGION I
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50-289/74-19 Docket No:
50-289
RO Inspection Report No:
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Licensee:
h tropolitan' Edison Company License No:
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P.O. Box 542 Priority:
Reading, PM.1sylvania 19603 Category:
Three Mile Island Unit 1 Location:
Mi a a l o e mm. Dauphin County. Pennsv1vania Ty of Licensee:
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Type of Inspection:
Routine, Unannounced
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( ates of Inspection:
April 4-5, 1974 Marc $26-28,1974 Dates of Previous Inspection:
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Reporting Inspector:
s Seth A. Folsom, Reactor Inspector Date Accompanying Inspectors:
NONE Date
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Date Date
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NONE Other Accompanying Personnel:
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Reviewed By:
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<c I r/7(/
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h J.F.Heishman,SeniorReactorinspeptor
/ /Date 4910180/ g
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SUMMARY OF FINDINGS Enforcement Action None Licensee Action on Previously Identified Enforcement Matters
Not Inspected Design Changes None Unusual Occurrences
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None
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Other Significant Findings (
A.
Current Findings
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1.
A carbon steel nut was found loose in the reactor internals at post-hot functional inspection.
This item is unresolved.
'(Details, Paragraph 9)
2.
A makeup pump was damaged when it was started without lubrica-tion.
This item is unresolved.
(Details, Paragraph 10)
B.
Status of Previously Reported Unresolved' Items 1.
The following items were resolved during the inspection:
a.
Failure of nuclear service river water pumps / motors.
(Details, Paragraph 2)
b.
Seismic mounting of cable trays and conduits.
(Details, Paragraph 3)
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c.
Lack of separation of seven electrical circuits beneath HVAC panel.
(Details, Paragraph 4)
d.
Replacement of suppression diodes in 480 - volt breakers.
(Details, Paragraph 5)
e.
Replacement of end caps on overcurrent trip delays in circuit breakers.
(Details, Paragraph 6)
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Ruptured diaphragm in condensate storage tank.
(Details, Paragraph 7)
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Pressurizer safety valve documentation.
(Details, Para-graph 8)
Management Interview
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A management interview was held at the site on April 5,1974 with the following personnel ir. attendance:
General Public Utilities Service Corporation (GPUSC)
}k. S. Levin, Project Engineer, Unit No. 1 Mr. G. L. Roshy, Auditor
Mr. M. J. Stromberg, Site Quality Assurance Auditor Mr. R. L. Wayne, Senior Quality Assurance Engineer Mr. J. E. Wright, Quality Assurance Manager i
United Engineers and Constructors (UE&C)
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Mr. D. C. Lambert, Field Supervisor, Quality Control
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The following items were discussed:
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A.
The inspector emphasized the importance of prompt reporting to RO:I of incidents per 10 CFR 50.55(e).
He stated that on nights or week-ends, if the RO:I office telephone answering service did not appear
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to perform satisfactorily, that the ' inspector should be called at his home.
The home phone numbers of the inspector, senior inspector, and branch chief were furnished to the licensee.
The licensee acknowledged this information, and agreed to notify those concerned.
B.
The inspector stated that the following items had been resolved at this inspection:
1.
Failure of nuclear service river water pumps /=otors.
(Details,
Paragraph 2)
2.
Seismic mounting of cable trays and conduits.
(Details, Paragraph 3)
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3.
Lack of separation of seven electrical circuits beneath HVAC panel.
(Details, Paragraph 4)
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4.
Replacement of suppression diodes in 480 - volt breaker.
(Details, Paragraph 5)
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5.
Replacement of end caps on overcurrent trip delays in circuit breakers.
(Details, Paragraph 6)
6.
Ruptured diaphragm in condensate storage tank.
(Details, Paragraph 7)
7.
Pressurizer safety valve documentation.
(Details, Paragraph 8)
The licensee acknowledged this inf ormation.
C.
T'ie licensee stated that the two items reported to the inspector during the inspection; carbon steel nut found loose in reactor internals, and failure of makeup pump, would be reported in writing within 30 days of the occurrence, in accordance with 10 CFR 50.55(e).
The inspector stated that these items were unresolved.
(Details,
Paragraphs 9 and 10)
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DETAILS 1.
Persons Contacted Cencral Public Utilities Servicy_ Corporation (GPUSC)_
Mr. J. Barton, Manager, Startup and Test
Mr. W. T. Gunn, Project 31;c 'Enager Mr. R. W. Heward, Jr., Project Manager Nb. S. Levin, Project Engineer. Unit 1 Mr. P. Levine, Quality Assurance Engineer Mr. G. L. Kopp, Quality Assurance Specialist Mr. G. P. Miller, Site Startup Manager Mr. H. M. Mitchell, Maintenance Supervisor Mr. D. H. Reppert, Safety and Licensing Health Physicist
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Mr. G. L. Roshy, Auditor Mr. M. J. Stromberg, Site Quality AssuTance Auditor Mr. R. L. Wayne, Senior, Quality Assurance Engineer Mr. J. H. Wright, Resident Civil Engineer (.
Mr. J. E. Wright, Quality Assurance Manager
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United Engineers and Constructors (UE&C)
Mr. D. C. Lambert, Field Supervisor, Quality Control
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2.
Failure of Nuclear Service River Water Pumps / Motors Five categories of difficulties had been encountered in the pre-operational testing of the three nuclear service river water pumps and motorst a.
Excess vibration b.
Broken pump shaft Corroded bearing cooling water filters c.
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Movement of foundation e.
Cracking of motor bearing support Each p' ump had been operated for several months without dif ficulty.
The problems encountered were analyzed, and engineering chaages made.
At the time of the inspection one pump was in operatica, another was operable and on " standby". Repairs to the third pt=p were underway with cc=pletion scheduled for April 7, 1974.
The changes made were documented, and appeared to insure future re-liable operation.
This item is resolved.
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Seismic Mounting of Cable Travs and Conduin The inspector examined the reinforced suspension and bracing of the electrical cable trays and conduits.
The reinforcement was in The accordance with the architect-engineer's revised drawings.
licensee's Deficiency Report disposition, and the licensee's Audit Report confirmed that all required seismic reinforcement had been completed.
This item is resolved.
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Lack of Separation of Seven Circuits Beneath HVAC Panel
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The inspector examined the modified routing of the seven cables numbered CQ 163, CBE 472, PR 113, RP 114, EA 310, CM 572, and RH 64.
The following documentation was also reviewed:
Corrective action memorandum by V. E, Cichocki, dated January
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21, 1974.
b.
Disposition verification by D. C. Lambert and R. Liscom, dated Mart.h 6, 1974.
~This item is resolved.
5.
Repla_ccment of Suppression Diodes in 480 - Volt Breakers The' inspector examined the following:
Unusual Occurrence Report No. 3, certifying the replacement of a.
the IN 5404 diodes with 6B20AP10BZ thyrectors, dated April 1, 1974.
b.
Diode replacement report, referencing Deviation Report Nc. 211, with attached drawing, dated March 28, 1974.
This item is resolved.
6.
Replacement of End Caps on Overcurrent Trip Delavs in Circuit Breakers _
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The inspector examined randomly - selected end caps installed in safety-related circuit breakers and found that each had been re-placed and tested in accordance with the constructor's letter of
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March 29, 1974'to the licensee.
The test data was also reviewed.
This item is resolved.
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Ruptured Diaphragm in Condensate Storage Tank The inspector examined the interior of Condensate Tank 1B (C07-1B)
from the manway rear ground level.
An angle-iron guard had been installed to protect the outlet nozzle from clogging, in accordance with the licensee's letter to Dr. D. F. Knuth, dated March 15, 1974. This iten is resolved.
8.
Pressurizer Safety Valve Documentation
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The vendor documentation on the two Dresser 2 " x 6" Pressurizer Safety Valves RC-RV1A and RC-RVlB was examined during the inspec-tion.
The documentation included:
a.
Purchase Order (31022Z) with nine Change Orders.
b.
Purchase Specifications OS-187 and PT-ll.
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c.
Mill certs of castings examined, dated April 9, 1973.
d.
Quality Assurance Data Sheet Package dated August 4, 1971.
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' Dresser Certification of Quality, including test data, dated e.
June 30, 1971.
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No deficiencies were identified.
Thie f.em is resolved.
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9.
Carbon Steel Nut Found Loose in Reactor Internals The licensee reported the following during the inspection.
"On
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April 3,1974, during post-hot functional inspection of the reactor internals a 3/4" carbon steel nut was found laying on top of the lower grid assembly at the interface of core positions L-2 and M-3.
Photographs of the nut and the surrounding area were taken before removal of the nut from the internals.
A detailed inspection of the core internals did not revea? any damage.
Additional inspec-tions and investigations are in ;rogress." The licensee stated that this would be reported, per 10 CFR 50.55(e).
This item re-mains unresolved.
Makeuo bumo Damaved by Lack of Lubrication During the inspection the licensee reported that on April 4, 1974 the tbkeup Pump A had been started without required lubrication, apparently due to operator error.
The bearings required replace-ment.
Repairs were scheduled for cocpletion by April 10, 1974.
This item is v2nresolved.
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