IR 05000289/1974006
| ML19253B748 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/06/1974 |
| From: | Folsom S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19253B747 | List: |
| References | |
| 50-289-74-06, 50-289-74-6, NUDOCS 7910180736 | |
| Download: ML19253B748 (7) | |
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U. S. ATOMIC ENERGY CO:f!ISSION DIRECTORATE OF REGULSTORY OPERATIO:;S
REGION I
R0 Inspection Report No.:
50-289/74-06 Docket No.:
50-289 Licensee:
Metropolitan Edison Company License No.: CPPR-40 P.O. Box 542 Priority:
a Reading, Pennsylvania Category:
B (Three Mile Island - Unit 1)
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Location:
Middletown, Dauphin County, Pe'nnsylvania Type of Licensee:
PWR 871 MWe (B+W)
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Type of Inspection:
Routine, Unannounced Dates of Inspection:
February 19-21, 1974 Dates of Previous Inspection:
February 12-15, 1974 Reporting Inspector:
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Seth A. tolscam, neactor inspecm
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I Acco=panying Inspectors:
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Date
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Other Accompanying Personnel:
None Date
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- D M M Jad Reviewed By:
R. F. Heishman, Reactor Inspector Date I
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SUK ARY OF FINDINGS Enforcement Action None t
Licensee Action on Previously Identified Enforcement Matters A.
A task force was formed by the licensee to identify cabling dis-crepancies and to insure their correction. The inspector 's re-audit show-ed cabling to be in conformance with pull cards and drawings.
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i This item is resolved.
(Details, Paragraph 2)
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Unusual Occurrences
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l None identified l
Design Changes j
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None identified
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Other Significant Findings j
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A.
Current Findings
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The inspector examined the handling and inspection of nuclear
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fuel.
No deficiencies were identified.
(Details, Paragraph 3)
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2.
The licensee stated that the containment structural integrity
test (SIT) was re-scheduled to start on March 4, 1974. Fuel loading was re-scheduled to start March 28, 1974.
(Management l
Interview, Paragraph A)
B.
Status of Previous 1v Reported Unresolved Items
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1.
The following items were resolved during the inspection:
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Handling and inspection of nuclear fuel.
(Details, a.
l Paragraph 3)
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b.
Bent thermocouple guide tubes.
(Dett.
.s, Paragraph 4)
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Core flood tank valve malfunction.
(Details, Paragraph 5)
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d.
QA program breakdown on electrical equipment inspection and testing.
(Details, Paragraph 6)
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Welding filler electrodes for major components.
(Details, Paragraph 7)
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Coolant bleed tank welder identification.
(Details, Paragraph 8)
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Management Interview A management interview was held at the site on February 21, 1974 with the following personnel in attendance:
General Public Utilities Service Corporation (GPUSC)
Mr. R. A. Burns, Assistant Project Manager
Mr. W. T. Gunn, Project Site Manager Mr. J. A. Renshaw, Project Engineer Mr. D. H. Reppert, Safety & Licensing Health Physicist Mr. G. L. Roshy, Auditor
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Mr. M. J. Stromberg, Site Quality Assurance Auditor Gilbert Associates (GAI)
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Mr. G. R. Joseph, Quality Assurance Assistant Program Manager Mr. P. J. Shipper, Project Electrical Engineer United Engineers & Constructors (UE&C)
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Mr. V. E. Cichocki, Construction QA/QC Coordinating Superintendent Mr. R. L. Hawkins, Construction QA/QC Coordinator
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Mr. B. E. O'Connor, Quality Control Documents The following items were discussed:
A.
In response to the inspector's questions concerning schedules the licensee stated that the containment structural integrity test (SIT) had been re-scheduled to start March 4, 1974, with
fuel loading re-scheduled to start March 28, 1974. The licensee agreed to notify the inspector of any change in the SIT schedule.
B.
The inspector stated that the following items had been resolved at this inspection:
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1.
Cable routing discrepancies (Details, Paragraph 2)
2.
Inspection of nuclear fuel (Details, Paragraph 3)
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Bant ther=occuple guide tubes (Details, Paragraph 4)
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4.
Core flood tank valves malfunction (Details, Paragraph 5)
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QA program breakdown on electrical equipment inspection and
l testing (Detai'.s, Paragraph 6)
6.
Welding filler electrodes for major components (Details,
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Paragraph 7)
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Coolant bleed tank welder identification (Details, Paragraph 8)
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The licensee acknowledged this information, and stated that every effort l
would be expended to resolve the remaining outstanding items within tha next week.
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DETAILS tw.
1.
Persons Contacted General Public Utilities Service Corporation (GPUSC)
Mr. J. Barton, Manager, Startup & Test Mr. R. A. Burns, Assistant Project Manager Mr. I. Feinberg, Electrical Engineer Mr. R. F. Fenti, Shif t Engineer Mr. W. T. Gunn, Project Site Manager
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Mr. S. Levin, Proj ect Engineer, Unit 1 Mr. P. Levine, Quality Assurance Engineer Mr. J. A. Renshaw, Proj ect Engineer Mr. D. H. Reppert, Safety & Licensing Health Physicist
Mr. G. L. Roshy, Auditor
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Mr. M. J. Stromberg, Site Quality Assurance Auditor
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Mr. J. E. Wright, Quality Assurance Manager
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Gilbert Associates (GAI)
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Mr. G. R. Joseph, Quality Assurance Assistant Program Manager Mr. P. J. Shipper, Project Electrical Engineer United-Engineers & Constructors (UE&C)
Mr. V. E. Cichocki, Construction QA/QC Coordinating Superintendent
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Mr. R. H. Hawkins, Construction QA/QC Coordinator Mr. D. C. Lambert, Field Supervisor, Quality Control Mr. B. E. O'Connor, Quality Control Documents 2.
Safeguards Cabline Discrepancies
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During a previous inspection the inspector found numerous instances where cables including safeguards, were not routed in accordance The licensee with the. pull cards, computer printouts or drawings.
had since formed a special task force to verify all cabling, identification and routing, and to make corrections where necessary.
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The inspector re-audited the safeguards cables in several systems
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ar.1 no deficiencies were identified.
This item is resolved.
3.
Handline and Inspection of Nuclear Fuel l
l The inspector examined the handling and inspection of nuclear fuel, I
together with associated documentation. The following items were
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included:
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a.
Vendor inspection program
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b.
Document control (1F1-201)
Tool and gage control (lF1-205)
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c.
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Cleaning and cleanliness (1F1-206)
Radiological control (1F1-203)
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Receipt inspection fit-up and storage (lFP-603)
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g.
Separation of deficient material
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h.
Handling equipment test certification 1.
Personnel and materia'l control
't j. Assqmbly of control rods into fuel elements
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Accounting records
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Shift logs
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t Fuel purchase documentation, change orders and vendor
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quality certification.
I No deficiencies were identified.
This item is resolved.
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4.
Bent Thermocouple Guide Tubes
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The guide tubes on the veat valve ther=ocouples had previously been l
bv.nt when'the reactor vessel head was installed. The licensee has since determined that these thermocouples would not be required
for the expected power levels.
The thermocouples and guide tubes have been removed. This item is resolved.
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5.
Core Flood Tank Valves Malfunction
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The inspector examined Babcock & Wilcox letter of February 20, 1974
to the licensee, and the core flood system valve vendor's letter to B&W ef September 4, 1973 " Core Flood System Valves." The vendor
stated that machining errors were the cause of the valve malfunction, and that the A564, Grade 360 material used wc3 an authorized sub-stitution.
This iten is resolved.
6.
0A Program Breakdown on Electrical Eauipment
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The licensee has completed the corrective action on the failure of an electrical equipment vendor to perform the quality control op-erations required in the vendor's program.
The vendor's re-test program, dated August 22, 1973, was approved by the licensee ana was completed with no deficiencies being identified.
The licensee's
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audit report 73-49, dated December 3, 1973 noted that "the testing i
was conducted as written, and that QC was provided."
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The inspector examined the results of the testing program, involving i
7 reports, including E9048 and E8958, and no deficiencies were identified. This item is resolved.
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7.
Welding Filler Electrode on Maior Comoonents The welding filler electrodes used on the steam generators were not a
traceable, as this was not a requirement at the time of manufacture.
The vendor had prepared Topical Report No. BAW-1402, dated January 1973, which provided the data necessary to justify the use of certain
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lots of weld filler material which had incomplete documentation of mechanical properties.
This iten is resolved.
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Coolant Bleed Tank Welder Identification
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t At a previous inspection, it was found that welder identification was not available for the welding on the Reactor Coolant Bleed Tank 1A.
At this inspection, the inspector examined PDM Drawing WL-1, dated
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Sep tember 11,1968 " Reactor Coolant Bleed Tank 1A" which included the identification of individual welders for each seam.
This item is resolved.
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