IR 05000289/1973005
| ML19256D505 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/07/1973 |
| From: | Burzi A J, Folsom S, Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D500 | List: |
| References | |
| 50-289-73-05, 50-289-73-5, NUDOCS 7910180824 | |
| Download: ML19256D505 (18) | |
Text
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S,. ATOMIC ENERGY COCIISSION
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DIRECTORAT.E OF REGULATORY OPERATIONS
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REGION I
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m RO Inspection Report No.:
50-289/73-05 Docket No.:50-2
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Licensee:
Metr Politan Edison Company License No.:CPP
Box 542
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Priority:
Reading, Pa.
19603
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Category:
B
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773,.,a n Location: Middletown. W ( m y,, v4 3,.,
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Type of Licensee:
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. Type of Inspection:
ut ne, nannounce'd
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Dates of Inspection:
May 8-9, 16-18, June 4-5, 19-21, 1973 Dates of Previous Inspection:
March 26-28, 1973
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Reporting Inspector:
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Seth A. Folsom, Reactor Inspector
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Dat Accompanying Inspectors:
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W77 V J Burzi Reactor Inspecfot
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A.A. Varela, Reactor Inspector Dat
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Other Accompanying Personnel:
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L.L. Beratan, Sr.
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Reviewed By: '. /
Cd ~5 M*
3.F. Heishman, Sr. Inspector, Facility Dat Construction & Engineering Support Branch
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SUMMARY OF FINDINGS
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Enforcement Action None
_L_iuensing Action on Previously Identified Enforcement Matters The containment ring girder concrete repair work has been completed.
The documentation on this program was examined by the inspector and no deficiencies were observed.
This item is resolved.
(Details, Paragraph 2)
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Design Changes None Unusual Occurrences
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The licensee reported that silt had built'up in the River Water Intake Structure to a point where river water pur.p operation could be impaired.
Dredging operations are now in process.
(Details, Paragraph 9)
A.
Current Findings
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L 1.
Containment tendon tensioning had progressed, with all 166 vertical
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tendons tensioned and filled, and 32 dome tendons tensioned.
(Details, Paragraph 3)
2.
Tendon bearing plate displacement had been measured during tensioning.
The procedure specifies a maximum acceptable displacement of 0.25" which has to date not been exceeded.
Several bearing plates had been displaced during tensioning by as much as 0.140", and there appeared to be some correlation between the amount of displacement and the locations where ring girder concrete repairs were performed.
This will be carried as an unresolved item.
(Details, Paragraph 15)
3.
The licensee stated that Unit No. I was considered 93% complete,
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and that fuel loading was scheduled for February, 1974. Unit No. 2 was considered 31% complete, and that full loading was scheduled for April, 1976.
(Details, Paragraph 8)
4.
A substandard silo of cement had been used in several concrete placements.
This will be carried as an unresolved item.
(Details, Paragrap. 22).
5.
A microanalysis of a buttonhead was not included in a closed-out Deficiency Report. This will be carried as an unresolved item.
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(Details, Paragraph 26)
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6.
Buttonheading d's dimensions were_not available at the jobsite.
(Details, Parag raph 4)
7.
Conduit and cable tray separation was not in accord with the separation criteria.
These had alread.- been identified by quality control inspectors. This will be carried as an unresolved item.
(Details, Paragraph 34)
8.
The vendor's seismic documentation on the VBB distribution panel
had not been approved by the licensee. This will be carried as an unresolved item.
(Details, Paragraph 36)
9.
No evidence was available that the vendor's recommendations for seismic mounting of panels and cabinets had been follos,d.
This will be carried as an unresolved item.
(Details, Paragraph 35)
B.
Status of Previously Reported Unresolved Items
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The following items identified in previous inspections were resolved:
1.
Seismic integrity of battery room lighting fixtures (Details,
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Paragraph 10)
2.
Siphoning of spent fuel pool storage water. (Detaile, Paragraph 11)
3.
Scheduling and construction progress diagrams. (Details, Paragraph 12)
4.
Chloride contamination from fire in RPV piping. (Details,
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Paragraph 13)
5.
Suspension of reacto_ coolant pump.
(Details, Paragraph 14)
6.
Control room annunciation of vital circuit breakers inoperative.
(Details, Paragraph 19)
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7.
Fire barriers within control room console. (Details, Paragraph 17)
8.
Control console procurement documentation.
(Details, Paragraph 33)
9.
Construction logs and records.
(Details, Paragraph 25)
10. Separation of redundant cabling in control room console.
(De tails,
Paragraph 18)
11. Battery room ventilation.
(Details, Paragraph 27)
12. Instrument power coto -generator unprotected. (Details, Paragraph 29)
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Separation of reactor trip breakers wiring. (Details, Paragraph 32)
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14. Color coding on ESF signal cables to bistable cabinets. (Details, Paragraph 31)
Management Interview The management interview was held at the site on June 21, 1973.
Personnel Attending General Public Utilities Service Company
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Mr. B.G. Avers, Quality Assurance Manager Mr. W.T. Gunn, Project Site Manager Mr. R.W. Heward, Jr., Proj ect Manager Mr. G.L. Kopp, Quality Assurance Specialist Mr. J.A. Renshaw, Quality Assurance Specialist Mr. M.J. Stromberg, Site Quality Assurance Auditor Mr. J.E. Wright, Site Quality Assurance Manager
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Mr. J.H. Wright, Resident Civil Engineer'
United Engineers and Constructors Mr. V.E. Cichocki, Quality Assurance / Quality Control Coordinating c
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Superintendent Mr. N.A. Vitale, Quality Control Administrative Assistant Gilbert Associatec Mr. D.D. Krause, Quality Assurance Engineer Mr. P. Shipper, Project Electrical Engineer s
The following items were discussed:
The inspector stated that the following items from previous inspections A.
had been resolved:
1.
Containment ring girder repair.
(Details, Paragraph 2)
2.
Seismic integrity of battery room lighting fixtures.
(Details, Paragraph 10)
3.
Siphoning of spent fuel pool storage water during loss of site power.
(Details, Paragraph 11)
4.
CPM diagram.
(Details, Paragraph 12)
5.
Chloride contamination from fire in reau tor coolant piping.
(Details, Paragraph 13)
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Suspension of Reactor Coolant Pump.
(Details, Paragraph 14)
7.
Control Room annunciation that vital circuit breakers are inoperative.
(Details, Paragraph 19)
8.
Fire barriers within control room console.
(Details, Paragraph 17)
9.
Control console procurement documentation.
(Details, Paragraph 33)
10. Construction logs and records.
(Details, Paragraph 25)
B.
The inspector stated that he had examined.ne field buttonheading of dome tendons.
No requirements were availaole in tha procedures for matching the buttonheads to the machined matir.g surface of the anchor head.
The licensee agreed to obtain this information from Inland
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Ryerson, the post-tensioning subcontractor.
The inspector stated
_ Details, Paragraph 4)
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that this would be carried as an unresolved item.
C.
The inspector stated that a clocei-out Deficiency Report included (~N mention of a microanalysis of tendan buttonheads, which was not available for the inspector's examination.
The licensee stated that A-the laboratory report had been delayed in the mail, and would be available at the next inspection. The inspector stated that this would be carried as an unresolved item.
(Details, Paragraph 26)
D.
The inspector asked for the number.of tendons which had been scrapped to date.
The licensee replied that one vertical tendon had been scrapped because of excessive defective buttonheads, and four vertical tendons had been scrapped because of damage c~aused by kinking or dropping.
(Details, Paragraph 23)
E.
The inspector asked for the number of horizontal tendons which because of interfereaces would be tensioned from one end.
The licensee stated that their previous estimates of the number of "one-end pulls"
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had been high, and that present indications were that only 16 horizontal tendons would be tensioned from one end, in addition to one horizontal tendon which could not be pulled from either end, and this was being studied by the architect-engineer.
(Details, Paragraph 16)
F.
The licensee furnished the following schedule information:
Unit No. I was 93% complete as of June 1, 1973, with fuel loading scheduled for February. 1974.
Unit No. 2 was 31% complete as of June 1, 1973, with fuel loading
scheduled for April, 1976.
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-5-m All 166 vertical tendons had been stressed and filled, and 32 dome tendons had been filled to date.
(Details, Paragraph 8)
G.
The inspector requested information on the extent to which loads of concrete had been rejected and dumped.
The licensee furnished documentation which showed a large number or rejected and dumped concrete.
(Details, Paragraph 9)
H.
The licensee reported that silting had occurred at the Unit No. 1 river water intake, and that dredging operations were in progress.
(Details, Paragraph 9)
I.
The inspecen* stated that the extent of bearing plate indentation during tendon tensioning had been examined during the inspection. The amount of indentation appeared to be excessive, even though the specification maximum had not been exceeded.
The licensee was asked whether any
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investigation would be conducted on t' hose bearing plates having the greatest indentation. The licensee stated that a program to study this indentation would be considered.
(Details, Paragraph 15)
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The inspector stated that he had found a number of cables tightly ()
tied to the sharp edges of the cable trays. The licensee stated that the procedure covered only safeguards cables, but that this condition
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would be corrected on all cables.
(Details, Paragraph 20)
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K.
The inspector stated that the cabling in the control console had been corrected to conform to the separations requirements, and that this item was resolved.
The licensee acknowledged this information.
(Details, Paragraph 18)
L.
The inspector stated that he had found an error in the containment strain gage location records, but that this had been corrected during the inspection.
The licensee acknowledged this information.
(Details, Paragraph 21)
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M.
The inspector stated that he had been informed that a silo of substandard cement had been partially used at the site, and that it presently appeared that the concrete strength would be acceptable. The licensee stated that the investigation was still in progress.
This will be carried as an open item.
(Details, Paragraph 22)
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The inspector stated that he had found that the FSAR now properly describes the battery room ventilation system and that this item is resolved.
(Details, Paragraph 27)
The inspector stated that the condition of the unprotected terminal O.
strips in the cable spreader room had been referred to the Directorate of Licensing for their resolution. The licensee acknowledged this information.
(Details, Paragraph 28)
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The inspector stated that he had been informed that the CRD undervoltage P.
assemblies had been removed and would be replaced. This will be carried as an open item.
(Details, Paragraph 30)
Q.
The instrument power motor-generator set had been found to include a flywheel vhich appeared to endanger adjacent safeguards electrical equipment. The licensee stated that the relocation or protection of this equipment would be considered.
This will be carried as an un-
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resolved item.
(Details, Paragraph 29)
The inspector stated that the separation of the four reactor trip R.
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breakcrs and their respective trip circuit wiring (four circuits - four k_$
conduits) is acceptable.
The licensee acknowledged this information.
s This item is resolved.
(Details, Paragraph 32)
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The inspector stated that the color coding on the ESF signal cables
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to their amplifier - bistable cabinets is now acceptable. This item is resolved. The licensee acknowledged this information.
(Detaile,
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Paragraph 31)
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T.
The inspector stated that he had found electrical conduits and tray separation in some cases which did not meet the separation criteria.
These had already been identified by quality control, but not yet corrected.
This will be carried as an unresolved item.
The licensee acknowledged this information.
(Details, Paragraph 34)
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The inspector stated that the seismic documentation on the VBB distribution panel had not been approved by the licensee.
This will be carried as an unresolved item.
The licensee stated that this documentation would be available at the next inspection.
(Details, Paragraph 36)
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V.
The inspcetor stated that there was no available evidence that the vendor's recommendations for seismic mounting of panels and cabinets had been followed in the site installation.
The licensee stated that this information would be available at the next inspection.
(Details, Paragraph 35)
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I DETAILS
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1.
Persons Contacted General Public Utilities Service Company Mr. B.G. Avers, Quality Assurance Manager Mr. J. Gilley, Construction Quality Control Coordinator Mr. W.T. Gunn, Project Site Manager Mr. R.L. Hawkins, Construction Quality Control Coordinator Mr. R.W. Heward Jr., Proj ect Manager Mr. T.S. Hreczuch, Mechanical Engineer
Mr. G.L. Kopp, Quality Assurance Specialist Mr. S. Levin, Project Engineer, Unit No.1 Mr. P.A. Levine, Quality Assurance Specialist Mr. J.A. Renshaw, Quality Assurance Specialist Mr. M.J. Stromberg, Site Quality Assurance Auditor Mr. J.E. Wright, Site Quality Assurance Manager Mr. J.H. Wright, Resident Civil Engineer
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United Engineers & Constructors Mr. R.V. Boudrias, Construction Mr. V.E. Cichocki, Quality Assurance / Quality Control ()
Coordinating Superintendent Mr. D.C. Lambert, Assistant Quality Control Supervisor Mr. F. Long, Lead Quality Control Engineer, Civil Mr. N. Reitzi, Quality Control Surveillance Inspector
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Mr. R.N. Moyer, Quality Control Supervisor Mr.
N.A'. Vitale, Quality Control Administrative Assistant Gilbert Associates Mr. G.R. Joseph, Quality Assurance Engineer Mr. K.E. Nodland, Project Civil Engineer Mr. D.D. Krauee, Quality Assurance Engineer Mr. R. Fleming, Site Quality Assurance Engineer Mr. P. Shipper, Project Electrical Engineer
Mr. V. Williams, Project Instrumentation & Control Specialist Mr. W.F. Sailer, Project Manager Inland Rye'rson Mr. C.K. Fredrick, Quality Control Supervisor Mr. R.S. DeCheske, Quality Assurance Manager Mr. G. Johnston Post Tensioning Supervisor Mr. H. Carawski, Post Tensioning Supervisor
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Mandil, Panoff and Rockwell Associates Mr. F. Sellers 2.
The documentation covering the entire containment ring girder repair work had been assembled into six filing cases.
Many of the documents had been examined by the inspector in previous inspections when repairs were in progress.
The documents included repair procedures and their addenda, specifications, concrete core boring data quality assurance / quality control data sheets, audit repcrts and surveillance reports.
No deficiencies in the documentation were found, except that copies of Deficiency Reports were filcd vhich did not indicate completed resolution. This was corrected during the frapection.
The deficiencies identified in previous inspections which related to the ring girder repair program are now considered resolved.
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3.
The installati;n of four dome tendons was observed on May 9, 1973.
The work appeared to be in conformance with the procedures.
The QC documentation for each tendons was being maintained, and no deficiencies were observed. The inspector observed the application of casing filler ( N.
to the tendon as it was being pulled in, to provide additional
corrosion protection.
At the time of the inspec_ ion all 166 vertical tendons had been in called, tensioned and filled, and 32 dome tendons had been installed and tensioned.
4.
The inspector observed field buttonheading on two dome tendons.
The work appeared to be in conformance with the procedures; including the use of no - go and eccentricity gages.
QC documentation was being maintained on a random 10% of the " ires per procedure requirement 16101.
Only one type of uspetting die w:.s
'n use at the site, to preclude the possibility of an improper die being used. The specific dimensional requirements for the die to produce a buttonhead seat to conform to the anchor head were nor available at the site.
The licensee agreed to secure this information. This will be carried as an unresolved item.
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5.
The inspector observed work performed on temporary protection of dome tendons follcwing buttonheading.
Controls were observed in use to exclude moisture from tendons prior to stressing and filler material application.
Rubber-sealed cans were installed against the bearing plates to seal out moisture. The inspector was informed that bulk filling for extended corrosion protection would be performed prior to stressing, on those tendons nearing nine-months since installation.
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Vertical tendons V-11 and V-150 were single-end stressed on May 17
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The procedures were being followed, including dual dial indicator t
gaging of bearing plate displacement.
Stage stressing was employed because of ram length limitations.
Elongations of 11% and 25% in excess of calculated values were observed on the two tendons.
The inspector was told that this tendon elongation, beyond the acceptable 5% excess, was being studied at Inland Ryerson's Chicago Engineering Office.
It had tentatively been determined that the excessive elongation resulted from a combination of tendon untwisting, bearing
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plate indentation at both ends, and a relatively small difference between the characteristics of the tendon wire used at this facility, and the wire used at other locations.
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7.
The licensee had stated that strain gage readings and visual examinations would be made in the areas of the ring girder concrete repairs during stressing operations, the integrated leak rate tests, an. at 6, 12, 24 and 36 months following the acceptance test. The inspector observed Brewer Enginaering Company engineers, on May 10-11, 1973 (prior to tendon tensioning) taking initial readings on 28 strain gages (14 hoop and 14 vertical) previously installed on ring beam
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reinforcing bars.
Also, four designated 6'x12' areas on external vertical ring girder surfaces were whitewashed for crack pattern study.
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8.
The licensee reported the following construction completion estimates:
v Unit No. 1 was 93% complete as of June 1, 1973, with fuel loading scheduled for February, 1974 Unit No. 2 was 31% complete as of June 1, 1973, with fuel loading scheduled for April, 1976 Unit No. 1 electrical completion status as of June 3, 1973 Conduit installed - 99.4%
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Trays installed - 100%
Power Cables installed - 93.5%
C & I Cables installed - 99.4%
Power Cables connected - 77.1%
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C & I Cables terminated - 87.2%
9.
The licensee reported that silting from the river had recently occurred at the Unit No. I river pump house. The silt had reached the intake screens.
This silting appeared to have been caused by eddy currents in the river resulting from the temporary cofferdams erected during construction of the Unit No. 2 river pu=p house. A dredging company had been contracted to dredge the intake area, and work was in progress during the inspection.
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10. The seismic integrity of the fluorescent lighting fixtures located
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directly above the racks in the battery rooms had been questioned.
The fixtures have now been relocct:d away from the batteries. Thd.s item is resolved.
11. The licensee had provided a vacuur break in the refueling pool fill line to prevent emptying of the p< al' in the event of a power failure.
This item is considered resolved now that there is a vacuum break in the fill line, and the drawing has been changed.
12. Data is being provided regularly by the licensee on the details of construction schedules and project completion.
This item is resolved.
13. The documentation of the reactor pressure vessel nozzle fire and the subsequent cleanup of the resulting chloride contamination was examined by the inspector at previous inspections.
The records included procedures, quality control checklists, chemical analyses and audits. This item is resolved.
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14. The suspension of the reactor coolant pumps by piping which traversed a 24-foot span had been questioned by the inspector at a previous inspection.
It had subsequently been determined that this suspension, in conjunccion with the hangers and restraints was acceptable. This 7-s item is resolved.
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15. The licensee compiled,at the inspector'c request, the 15 deepest bearing plate indentations in the 166 vertical tendcas resulting from tensioning, as follows:
Tendon No.
Indentation (inches)
V26 plus.176 (This tendon was reported to have raised up during tensioning.
All others were depressed into the containment concrete.
V31
.140
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V70
.140 V76
.134 V79
.132 V105
.120
V126
.110 V8
.098
.V122
.095 V15
.095 V30
.095 V51
.094 V36
.090 (_
V165
.090 V113
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Average (of 166) top of containment.041" (shop end)
Average (of 166) at tendon gallery.0035" (field end)
There had been 33 doce tendons tensioned at the time of inspeccion.
The following exhibited the deepest bearing plate indentations of these 33.
Tendon No.
Indentation (inches)
Shop End D-325
.033 D-149
.030 D-337
.030 D-321
.030 s
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D-109
.027 Average of all 33 dome tendons.018"
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Field End D-201
.135 D-309
.125
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D-141
.098 (_,
D-109
.097 D-205
.090 Average of all 33 dome tendons.031"
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s The tensioning specification permits a mLximum indentation of 0.25 inches, which the inspector stated. appeared to be insufficiently restrictive. None of the indentations to date had exceeded this specificaticn.
The inspector stated that it would appear that the condition of the concrete under the bearing plate having the greatest indentation should be examined. The licensee agreed to consider performing this investigation.
There appeared to be some correlation between the location of the bearing plates with the greatest indentation and the location of the
ring girder concrete repair work, 16. The inspector questioned the number of horizontal tendons which would be tensioned from one end because of interferences at the other end of the tendon.
The licensee stated that previous estimates of the number of these one-end pulls had been high cnd that presently it appeared that there would be 16 one-end pu]ls, plus one tendon which, because of interferences at both ends, could not be tensioned. The latter was still under study by the architect-engineer.
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The licensee stated that friction tests had been performed to implement the one-end pulls, in accordance with Inland Ryerson 's Tensioning Manual, Appendix B, Chapter 6 which had been written for this facility. Tests had been run on horizontal tendons H46-046 through H46-051 inclusive had been performed by Inland Ryerson at the i
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17. The inspector at a previous inspection had identified apparently inadequate fire barriers in the control room console, and had i
questioned the licensee as to their adequacy to prevent the spread of
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a fire which might occur in one section of the console. At this inspection the fire barriers installed were re-examined and found
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acceptable. The fire barrier material between the control room and
i the cable spreader room was indicated on the drawings but vculd not i
be installed until cabling in this area was complete. This item is resolved.
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18. Coils of wire in the control room console were found in previous
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inspections to violate the separation criteria of redundant safeguards cable. These coils had been removed by shortening and rerouting the
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This wires, and the specified separation criteria were maintained.
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item is resolved.
([f 19. The inspector stated that at a previous inspection he had questioned C
the lack of control room annunciation in the event that a vital circuit breaker was inoperative or otherwise out of service. This had subsequently been referred to the Directorate of Licensing, which had advised that such annunciatien.was not required at this facility.
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This item is resolved.
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20. The inspector stated that several cables had been found to be tightly
tied to the sharp underside edges of cable trays.
The GAI Specification
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SP-5616, Revised May 76, 1972, page I-20, Paragraph 1.19.9 stated
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" Cable shall be formed --- to avoid bearing against edges of trays-- ".
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The licensee stated that this specification referred only to Safeguards cables and that none of the cables observed by the inspector as being
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variance with the specification were in the Safeguards category.
licensee, however, considered this condition unsatisfactory on any cable, and agreed to correct this condition.
This item is unresolved.
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21. The incpector found that Strain Gage No. tC installed in the ring girder repair area was apparently not located at azimuth 352, elevation
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446 f t., as specified on the Brewer Engineering drawing.
Following
investigation, the licensee reported that there was a typographical error on the quality control check list which had been examined by and that Strain Gage No. 60 was in the required location.
the inspector, As evidence of this, the inspector was shown the Brewer Engineering Setup Report of April '.7,1973, Appendix I which listed actual final locatica
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of all strain gages. The UESC QC report of March 27, 1973 also confirmed the location.
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22. The 'icensee had reported that a silo of substandard cement had been encount :ed at the Bar.' Plant. A moving average record of 3-day cylinder creaks had
>a) ' this condition.
The silo of cement had been returned *
.he vem'ot The subsequent cylinder breaks, egular and s tecial, had improved and present indications were that the final 90- ia 'reaks would be within the tolerances for concrete attengt'.. per*
_;d by the ACI specification.
This will be carried as at. unresolved item.
23. The licensee stated that one vertical tendon had beer scrapped to date becausc of an excessive number of defective buttonheads at the field end.
In addition, four vertical tendons had been scrapped due to kinking and dropping during' tendon installation.
24. Information had been requested at a previous inspection as to evidence of loads of concrete having baen dumped as the result of quality control effort at the truck discharge point.
The licensee presented
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for the inspect r's review a folder of Pittsburgh Testing Laboratory concrete load sheets which showed numerous instances of concrete dumped for various reasons, for example, high slump, high temperature
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and over-rotation.
These occurred during the periods selected (.
for review, from December 1-21, 1972 and from June 8-15, 1973.
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25. The inspector had examined a number of plant logs and records of previous inspections, including those of different contractors.
The records had been reviewed from the standpoint of their~ possible inclusion of extraneous, derogatory information and unresolved deficiencies. Some instances of th.ese had been found by the inspector.
The licensee had since developed an audit program covering all site contractors, to control the type of information to be included in plant records. At this inspection a wide variety of logs and records maintained at the site were examined by the inspector, and were found to be accept 2ble.
26. A Deficiency Report which had been closed out on Fby 1,1973 on replaced vertical tendon V-139 noted that the disposition required
a mi. ro-analysis to be performed to e;tablish the cause of excessive buttonheads splitting. The licensee stated that Inland Ryerson's
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Chicago Office would submit the microanalysis results to the architect-engineer for evaluation. This was delayed in the mails.
This will be carried as an unresolved item.
27. The battery room ventilation is provided by scoarate ducts, and one ventilating fan.
The individual battery rooms are isolable from each other by dampers in the ducts.
The FSAR has been re-written to conform to this system. This item is resolved.
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18. The terminal strips in the cable spreader room are not protected, and the terminals appear vulnerable to accidental contact from persons and objects in the vicinity of the unprotected strips.
This condition has been referred to Licensing for review.
This item is unresolved.
29. The motor-generator set which provides " clean" isolated power for the low-level counting instruments is equipped with a flywheel and is located in one of the 480. volt ESF switchgear rooms with vital ESF equipment in both rooms located in the probable trajectory of the flywheel.
The rooms are separated by thin sheet steel.
The licensee stated that the relocation or protection of this motor-generator set would be considered.
30. A control rod drive undervoltage trip assembly had been found defective at another facility. The condition was described to the licensee, and it was determined that action had already been taken by the NSSS sopplier to identify and test the CRD.undervoltage trip breakers at
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Three Mile Island I.
The assemblies were found to partially exhibit the same characteristics which had caused the problem at the other facility, and the assemblies were removed and will be replaced with modified breakers. This will be continued as an open item until
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L-replacement trip assemblies have been installed.
31. The color coding on ESF signal cables to their amplifier - bistable cabinets had been identified as deficient in a previous inspection.
The inspector re-examined this cabling during this inspection, and found the color coding acceptable. This item is resolved.
32. The separation of the wiring on the four reactor trip brellers had been found to be deficient at a previous inspection. At this inspection the wiring was re-examined and the separation found to be acceptable.
This item is resolved.
33. The inspector had found at a previous inspection that there was a lack of adequate packaging and crating requirements for the control
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console.
It was found that the console at that time had already been shipped. This item is resolved.
34. Conduit an,d tray separation were not in accord with the separation criteria in some cases. The contractors quality control had already identified this deficiency.
This will be carried as an unresolved item.
35. The vendor of the electrical panels and cabinets specified the method of mounting the panels and cabinets to provide seismi: protection.
There was no evidence available to show that the recommendated mounting methods had been followed.
This will be carried as an unresolved item,
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36. The vendor's seismic documentation on the VBB distribution panel had not been approved by the licensee.
This will be carried as an unresolved item.
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MEMO ROUTE SUP Furm AEC.93 (Rev. Af ay 14,1947) AECkt 0240
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For s.(nefure.
For Informs'lon.
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omvAu ntuARns R0 Chf, Field Supt & 1:nf Br, HQ RO IUSPECTION REPORT No. 50-289/73-05
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,m RO: HQ (5)
METROPOLITAN EDISON COMPANY
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t 4 s' OR Central Files eArt m
RO Files Central Mail & Files THREE MILE ISIAND 1
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The attached report is being forwarded for informatic n.
REMARK 5 IMDAG To (Name and unet)
Regulatory Standards (3)
Directorate of Licen<> Lng (13)
Distribution to PDR, Local PDR, NSIC,DTIE, and state RO Directors (4)
arc representatives will be made after proprietary reviev PDR Local PDR TO (Name and unit)
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is completed by the licensee.
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DTIE St te of Pennsylvania e,rg
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FRoM (Name and unst)
gruAAg3 E. M. Howard
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PHONE pc DATE 278 8-9-73 c;no : g,73 o.,,3.,9 USE OrHER SeCE FOR ADDITION AL REM ARKS v
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