IR 05000518/1979015
| ML19261F151 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 09/04/1979 |
| From: | Cantrell F, Swann W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19261F150 | List: |
| References | |
| 50-518-79-15, 50-519-79-15, 50-520-79-15, 50-521-79-15, NUDOCS 7910250219 | |
| Download: ML19261F151 (5) | |
Text
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'o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
g e
REGION 11
o 101 MARIETTA ST., N.W.. SUITE 3100 g
ATLANTA, GEORGIA 30303
.....
Report Nos. 50-518/79-15, 50-519/79-15, 50-520/79-15, and 50-521/79-15 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name: Hartsville Nuclear Plants, A and B Docket Nos. 50-518, 50-519, 50-520, and 50-521 License Nos. CPPR-150, CPPR-151, CPPR152, and CPPR-153 Inspection at Hartsville Site near artsville, Tennessee Inspector:
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W. B. Swan ' '
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Date Signed Accompanying Personnel:
F. S. Cantrell Approved by:
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F. K ~Cantrell, Acting 4hief, RCES Branch Date' Signed SUMMARY s
Inspection on July 23-27, 1979 Areas Inspected This routine, unannounced inspection involved 44 inspector-hours onsite in the areas of project status; measures for curtailing Plant B construction; Category I concrete; open items review; unresolved items, IE Bulletins and Circulars; 50.55(e) and Part 21 items; inspector evaluation; and consultation on facilities for resident inspector.
Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- R. T. Hathcote, Project Manager
- H. S. Sheppard, Assistant Constr"ction Engineer, QC for STRIDE
- G. A. Gonsalves, QA Supervisor
- A. G. Debbage, QA Audit Supervis _
- W. T. Quinn, Construction Engineer, B0P
- W. R Brown, Construction Engineer, STRIDE
- W. O. Brown, Assistant Constructiou Engineer, Engineering Services B. E. Huffaker, Civil / Materials QC Supervisor, B0P G. England, DCU Supervisor, Second Shift R. C. Nixon, Document Control Supervisor J. T. Dorman, Assistant Construction Engiaeer, Second Shift R. L. Long, Materials Engineer M. H. McGrory, Technical Services Supervisor E. D. Peoples, Assistant Construction Engineer, B0P
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized.an June 22, 1979, with those persons indicated in Paragraph 1 above, in the areas of concrete, open items, project status; and preparation for shutdown of Plant B con-struction. No items of noncompliance or deviations were identified.
Licensee representatives expressed no dissent with the findings detailed.
3.
Licensee Action on Previous Inspection Findings (Closed) Deviation (518,519,520,521/79-01-02), Sampling of Pumped Concrete.
The licensee letter of response dated March 5, 1979 has been reviewed and determined to be acceptable by Region II.
The licensee has revised Quality Control Instruction (QCI) C-208 to require sampling of pumped concrete at the end of the pumpline in accordance with ANSI N45.2.5-1974 and since January 22, 1979 sampling has been done in accordance with this standard.
(Closed) Unresolved Item (518,519,520,521/78-16-02), QC Procedures Do Not Requi.re Checking of Calculations of Test Results.
In order to prevent mathematical errors in test results on earth fill from going undetected for a long time such that major corrective actions are necessary, the site QC unit will review test documentation in a timely manner to enable errors te be caught before extensive additional work is accomplished; and a " checked by" block was added to compaction test forms in QCI-C-101 to record this review.
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4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort A followup inspection was made of faundation treatment and concrete a.
work for pumphouses for the four sp. ay ponds. The erosion gullies in the Carters formation beneath and scuth of pond B-2 were being cleaned and filled with crushed rock and fil.! concrete.
b.
The inspectors made a general tour of site construction. Supporting activities were observed. Discussions were held with the site QA unit.
A review as made of the QA unit's status report on 50.55(e) items, 10 c.
CFR 21 items, and IE Bulletins and Circulars.
d.
Installation of timber frameworks as supports for plastic sheets to protect rebar during Plant B construction curtailment was observed by the inspector throughout the Plant B STRIDE structures.
Discussions were held with the Site Manager and the STRIDE Construction e.
Engineer concerning plans for assignment of an NRC resident inspector.
The licensee has located a trailer for the inspector between construc-tion administration buildings No. 4 and No. 5. The inspector stated that relocation of the NRC trailer to the Plant A power block vicinity may become advisable when construction activities become more complex.
6.
Status of Previous Licensee Identified 50.55(e) Items (Closed) 518,519,520,521/79-04-01 Inaccurate Reporting. The QA Unit super-visor at the site has approved and implemented Quality Assurance Operating Instruction QAU-01 1.1 to ensure that everything reported to NRC has been reviewed and inspected for accuracy by the Site QA Unit. The inspector reviewed the procedure and found it to be apparently adequate.
(Closed) 518/79-08-03 Seismic Qualification Failure of Differential Relay.
The licensee's final report on this matter was transmitted by letter dated April 5, 1979.
On March 19, 1979, TVA was notified in writing by General Electric (GE)
that they had reported a Part 21 defect to the Region V Office of NRC-0IE on March 7, 1979. "The panels for Hartsville were not shipped. New seismi-cally qualified differential relays will be installed in all panels."
This item is closed for Hartsville.
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7.
Status of Inspection and Enforcement Bulletins The following bulletins are closed for record as being not applicable to Hartsville: 79-05A,-05B,-05C; 79-06,-06A,-06B,-06C.
(Closed)Bulletin 79-07 Seismic Stress Analysis of Safety Related Piping.
The licensee's final response, transmitted by letter of August 10, 1979, was reviewed by Howard J. Wong, IE-HQ, and RII was notified by telecon on August 6, 1979 that the response was acceptable.
(Closed)Bulletin 79-11 Faulty Overcurrent Trip Device in Circuit Breakers for Engineered Safety Systems. TVA's letter of July 20, 1979 stated that none of the DB-50 and DB-75 circuit breakers with overcurrent trip devices have been used or are planned for use at Hartsville.
(0 pen)Bulletin 79-02, Rev. 1, Pipe Support Base Plate Designs Using Concrete Expansion Bolts. TVA's letter of July 5, 1979, transmitted the results of investigations performed in response to Bulletin 79-02.
The transmittal included generic response to the four action items detailed in the bulletin, including details of design analysis, TVA Civil Design Standard DS-C6.1
" Concrete Anchorages", and TVA Construction Specification G-32, Rev. 5,
" Bolt Anchors Set in Hardened Concrete".
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This item remains open pending RII review of response and-followup inspec-tions.
8.
Lakes, Dams and Canals - Observation of Work and Work Activities A follow on inspection was made of the cleaning of erosion channels in the Carters formation foundation rock under spray ponds A-1 and B-2 and con-tiguous earth and rock structures. The cleaned channels were being filled and sealed with crushed rock and fill conctete in accordance with geologic team instructions.
No noncompliance or deficiency was identified.
9.
Containment (Structural Concrete II) - Observation of Work and Work Activities on Containment Shield Walls of Units A-1 and B-1 The inspector made a follow on inspection of installation of reinforcing steel for the A-1 containment shield wall.
a partial concrete placement had been made for the fourth ring of this shield wall and the forms stripped.
The completed concrete was inspected.
The third lift of the B-1 containment shield wall, pour BIR-2C had been made on July 12, 1979. Forms had been sti:ipped. The exposed concrete and curing measures were inspected.
No noncompliances or defiencies were identified.
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Containment (Structural Concrete II) - Review of Quality Records for Unit B-1 Shield Wall The inspector was told that a test cylinder from placement BIR-2R would be broken at 180 days from placement, about August 5, 1979 and another at 270 days. The results of the successive tests will be plotted and evaluated to see if ultimate strength of the concrete can be adequate. This matter will be tracked by inspector Followup Item 519/79-13-01, since converted to 50.55(e) item 50-519/79-13-01, Wrong Concrete Mix in Pour B1R-2B.
The available records for placement BIR-2C were reviewed.
Included were the results of the three day cylinder breaks:
1144 and 1397 psi, yielding moving averages of 1221 and 1291 psi. These yields were well above expec-ted strength. 460 cubic yards of 400.75 BFO-P Mix were placed under the controls of QCI C-201, Rev. 4.
No items of noncompliance or deviations were identified.
11.
Containment (Steel Structures and Supports) - Observation cf Work and Work Activities on Steel Containment Wall and Reactor Pressure Vessel Pedestal for Unit A-1 The inspector observed assembly of some of the sections of the fourth liner ring on the assembly template pad for Unit A-1 containment.
Repair work on the copper contaminated welds on A-1 RPV pedestal was observed.
No items of noncompliance or deviation were identified.
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