IR 05000518/1980015
| ML19351D231 | |
| Person / Time | |
|---|---|
| Site: | Hartsville |
| Issue date: | 08/27/1980 |
| From: | Cantrell F, Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19351D225 | List: |
| References | |
| 50-518-80-15, 50-519-80-15, 50-520-80-15, 50-521-80-15, NUDOCS 8010090244 | |
| Download: ML19351D231 (7) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
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,e REGION 11 Y
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101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
AUG 2 819BC Report Nos. 50-518/80-15, 50-519/80-15, 50-520/80-15 and 50-521/80-15
Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Hartsville Nuclear Plant Docket Nos. 50-518, 50-519, 50-520 and 50-521 License Nos. CPPR-150, CPPR-151, CPPR-152 and CPPR-153 Inspection at Hartsville site near Hartsville Tennessee Inspectors:_)d.
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$f-A7-so W. B. Swan
Date Signed l
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- q F. S. Cantrell (JulyC19-30, 1980)
D6te Signed Approved by:
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AElh 6[27/60 F. $. Cantrell, Secti @ Chief, RCES Branch D' ate Signed SIMMARY
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Inspection on June 30 thru July 31, 1980 Areas Inspected This routine, announced inspection involved 181 inspector-hours on site by the resident inspector in the areas of earth compaction and structural concrete for spray ponds; structural steel in A-1 fuel building; concrete in Units A-1 and A-2 buildings; follow up on open items; and independent inspection effort.
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Results
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Of the five areas inspected, no items of noncompliance or deviations were identi-fled.
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DETAILS 1.
Persons Contacted Licensee Employees
- R. T. Hathcote, Site Project Manager
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W. R. Quinn, Construction Engineer
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L. H. Jackson, Assistant Construction Engineer, STRIDE Engineering W. O. Brown, Assistant Construction Engineer, Second Shift H. S. Sheppard, Assistant Construction Engineer, Quality Control K. Stewart, Assistant Construction Engineer, Engineering Services B. Huffaker, Supervisor, Civil QC - Materials J. Davenport, Supervisor, Materials QC - Civil S. P. Stagnolia, Supervisor, Welding QC R. S. Luther, Soils Engineer, QC - Materials J. W. Henry, Assistant Construction Engineer, QC F. E. Laurent, Principal Mechanical Engineer, STRIDE T. O. Wilkenson, Supervisor, Material Services H. F. Bates, Principal Civil Engineer, STRIDE S. T. Downey, Civil Engineer, STRIDE Project Engineering W. K. Anders, OEDC - QA Auditing J. L. Howard, Civil Engineer G. A. Gonsalves, Unit Supervisor, Site QA Unit J. T. Dorman, Assistant Construction Engineer, Concrete Coordination A. G. Dobbage, Audit Supervisor, Site QA Unit N. L. McCrory, Unit Supervisor, Technical Services L. G. Hebert, OEDC - QA Audit Unit R. C. Botsch, Unit Supervisor, BPE Civil H. E. Bell, Electrical Engineer, SPE Instrumentation i
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J. R. Lewis, Civil Engineer, Structural QC T. E. Poe, Construction Superintendent, Instrumentation Other licensee employees contacted included eight technicians and engineering sides in Q.C. Units, five QC Technicians and 11 construction foremen and craftsmen.
- Attended exit interviews 2.
Exit Interviews i
l The weekly inspection scope and findings were summarized with the project manager on July 7,11,18, and 25,1980.
On July 29-30, 1980, F. S. Cantrell and the inspector held discussions with the site manager, the construction engineer and assistant construction engineers, and made surveillance tcurs of Plants A and B and support facil-ities.
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3.
Licensee Action on Previous Inspection Findings No inspection activity.
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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identified during this inspection are discussed in paragraphs 5 and 10.
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5.
Independent Inspection Effort During routine surveillance site tours the inspector inspected construction activities on peripheral structures such as the intake pumping station, trans-former yards and the component cooling water treatment building. Earth fill and compaction about these structures and the base mat adjacent to the power blocks structure of Plant A were inspected.
Fittings and tack welding of sections of the fifth ring of the A-1 steel containment wall were inspected on July 10 and 11,1980.
Eight stainless steel tanks and three carbon steel tanks (10,000 to 20,000 gallons capacity) were fabricated on site by the vendor, and stored in the field at the fabrication site pending relocation to their installation site;. These tanks have not been accepted by TVA from the vendor. The j
manways and other openings had been left unsealed. When this condition was
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identified to the licensee, the openings were promptly sealed. The licensee is investigating to determine the storage requirements for these tanks.
This is identified as unresolved item 518, 519, 520, 521/80-15-04.
The inspector inspected ultrasonic examination activities, by a special GE team, on exterior areas of the Unit B-1 reactor pressure vessel stand near the unloading dock.
The vendor had not examined these areas with the automatic ultrasonic examination equipment in the shop because of blocking obstructions. The inspector observed use of the UT sensors in the inspected areas, the monitoring of the wave displayr, and the recording of results.
No determinations of acceptability were made during this inspection by GE personnel. This is identified as inspector followup item 519/80-15-02.
No items of noncompliance or deviations were identified during these obser-vatiocP of construction and testing activities.
6.
Quality Assurance Program Review During this report period the inspector held discussions with two TVA audit,
teams:
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A welding audit team which was auditing TVA's welding and welding QC programs at all active constru : tion sites following repeated citations at these sites.
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An OEDC audit team which made an exhaustive review of QA-QC performance at TVA construction sites. These findings were reported in audit report OEDC 80-06.
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The inspector. will follow TVA's evaluation and resolution of concerns identified in both audits and document as appropriate. This is identified as inspector follow up item 518, 519, 520, 521/80-15-06.
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Licensee Identified 50.55(e) Items (Open) 518, 519, 520, 521/80-15-01 Rosemont Model 1152 Pressure Transmitter Defcets (NCR PRC 80-28) (Reference OIE Bulletin 80-16 and IE Circular 80-16).
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The defect involves on scale output from Model 1152 transmitters when exposed to pressures outside the calibrated ranges.
The final report on this matter is due by September 17, 1980.
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(Open) 518/80-15-02 Heaters Omitted from Motor Operator (NCR HNP-097)
i During storage maintenance testing it was found that ne heating element had
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been installed in the motor control of one RCIC turbine steam inlet valve.
The deficient motor is to be replaced by November 30, 1980.
I (open) 518, 519, 520, 521/80-15-03 Deficiency in Drawing Control (HNP QA Audit HT-G-80-12, Deficiency No.1).
i Approximately twenty percent of the drawings reviewed at various locations throughout the HNP project had been superceded by later revisions to the drawings. Corrective actions to assure compliance with QA program require-ments were being studied by licensee management at the end of this report period.
8.
Status of OIE Bulletins (Open) 80-08 Examination of Containment Liner Penetration Welds i
The licensee's letter of July 7,1980, detailed the results of TVA's investi-
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gation on these penetration welds. This response is being evaluated.
The licensee received and reviewed for action the following bulletins, none of which is applicable to Hartsville:
(Closed) 79-28 Possible Malfunction of NAMCO Model EA 180 Limit Switchas at Elevated Temperatures - Not applicable. The licensee does not pian to use these switches.
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(Closed) 80-11 Masonry Wall Design - Not applicable to construction
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(Closed) 80-17 Failure of Control Rods to Fully Insert During a Scram at a BWR - Not applicabic to construction sites.
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Status of IE Circulars The inspector determined that the licensee has received and assigned for review the following circulars, which are closed for record.
(Closed) 80-16 Operational Deficiencies ~in Rosemont Model 510 DU Trip Units and Model 1152 Pressure Transmitters (Closed) 80-17 Fuel Pin Damage Due to Water Jet from Baffle Plate Corner 10.
Lakes, Dams and Canals - Spray Ponds for Plants A&B During this report period, construction and inspection operations continued in earth fill and compaction and in concrete placements in the essential service water (ESW) pump stations.
The inspector made follow on inspections of earth placement, compaction and testing, and of the placement of the base layers of 3" rocks for the rock dixe.
Additional inspections were made of preparations for placement and placement of concrete in the pumping stations and of curing operations following placement. On the evening of July 29, 1980, the inspector wit-nessed placement of 60 cubic yards of concrete in pour A2KESWP5-57, for a i
wall of A2ESW pump station.
The inspector then observed operation of the north batch plant in mixing concrete for the A-2 turbine building. Leakage of water from feed facil-ities, and sloshing of water from the mixer during charging, resulted in water entering the transport truck prior to and following discharge of mix into the truck. In addition the inspectors noted cement and/or fly ash dust being blown from the charging facilities and mixer. These conditions were reported to the shift supervisor and the QC inspector, who stated that these were intermittent but recurring problems as a result of equipment maladjustment and clogging of the feedwater sluice. Corrective actions were taken then and the following morning.
On this following day the inspector again observed mixing operations.
Water spillage had been cor-rected and loss of cement and fly ash had been reduced to an acceptable level.
Residual mismatch of the mating flanges of the mixer bowl' and charging duct, which rotates to alternate mixers, permitted loss of a minor amount of small aggregate and cement. The civil QC supervisor and the batch plant supervisor stated that the equipment required trequent adjustments to assure acceptable matchup of the mating flanges.
(These deficiencies were not cited as an item of noncompliance because at the time concrete was '
being mixed for nonsafety related structures. The inspector will follow?
TVA's program to insure that these type deficiencies are promptly identified and corrected while mixing concrete for safety related structures. (Unresolved Item 50-518, 519, 520, 521/80-15-05.))
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The earth and rock work criteria are described in TVA Construction Specifi-cation N 6C - 875, Revision 12 dated 3/28/80, " Earth and Rock Foundations and Fills" and by notes on the construction drawings; and SRM N6C-875-23 dated May 6, 1980, and SRN N6C-875-24 dated May 28, 1980. Inspection and testing are guided by Civil Quality Control Instruction C-102, Revision 7, dated 8/30/79, " Foundation and Fill, Earthfill Control Testing". Concrete installation is controlled by C. F. Braun Specification 300-01 CONCRETE thru Revision 8, dated Ifay 15, 1980. Inspection and testing is controlled by TVA Civil procedures QCI-C-201 to 218 No items of noncompliance or deviations were identified.
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Concrete in Plant A Power Block Structures During this report period the inspector verified the correctness of curing operations and other operations.
Rebar and embedment installation, forming, cleaning, placement, and initial curing provisions after placement were inspected for pours AIR-2-Ja in the tenth lif t of the A-1 containment shield wall, AIF-17E, two placements in the A2 fuel building preparations for AIC-100 in the A-1 control building and preparations for miscellaneous pours in these and other power block locations.
The inspection criteria used are identified in paragraph 10 above.
No items of noncompliance or deviations were identified.
12.
Containment (Steel Structures, and Supports) Observation of Work and Work Activities The inspector reviewed repair operations on the anchor bolt chair welds at the base of the Unit A-1 containment wall (Reference 50.55(e) Item 518, 520/79-17-20). Preheating was being properly done and QC inspector coverage was present at each work station.
The inspector inspected the erection of structural steel in the Unit A-1 fuel building, control building and auxiliary building. Steel erection in the A-1 fuel building and auxiliary building had advanced to the 11'-0" level with'less than 50% of the joints bolted and/or welded.
Completed bolted joints had been accepted by QC. The inspector verified that erection corrections required by errors in fabrication and embedded support details were authorized and made by QCIR's. Raquirements for these structures are described in the HNP PSAR and GESSAR section 3.8, supplemented by C. F. Braun specification 300-04, TVA work packages C129-C2 and C-135C, TVA and Atlas '
Machine and Iron Works fabrication drawings.
Inspection is controlled by QCI-C-302, Interim-1, Rev. 3, Structural Steel Erection and Bolted Connec-tions, and QCI N-502 (was W-102) Visual Inspection of AMS Welds. Erection, bolting and welding were inspected in the A-1 fuel building at the 11'-0",
(-) 5 '-3 ', and (-) 17 '-0" levels.
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The records of visual and magnetic particle inspections of four welds at the 11'-0" level were reviewed as well as for others at elevations (-)
19 '-9", (-) 17 ' -0", (-) 11'-1" and-5'-3".
No items of noncompliance or deviations were identified.
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