IR 05000518/1979019
| ML19262A025 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 09/18/1979 |
| From: | Cantrell F, Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19262A006 | List: |
| References | |
| 50-518-79-19, 50-519-79-19, 50-520-79-19, 50-521-79-19, NUDOCS 7910260161 | |
| Download: ML19262A025 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION o g e REGION il .
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ATLANTA, GEORGIA 3o303 Report Nos. 50-518/79-19, 50-519/79-19, 50-520/79-19, and 50-521/79 19 Licensee: Tennessee Valley Authority 500 A Chestnut Street Tower II 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, CPPR-152, and 50-153 Inspection at Hartsville Site near Hartsville, Tennessee Inspector:
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r, rrt, _ / [[7f W. B. Swan '" ~ Date Signed Accompanying Personnel: F. S. Cantrell and P. D. Chendemi at conference on Wednesday, August 22, 1979 Approved by: NO.
9 1B/77 F. S. Cantrell, Se@ tion Chief, RCES Branch Date Signed SUMMARY Inspection on August 20-24, 1979 Areas Inspected This routine, announced inspection involved 40 inspector-hours onsite in the areas of project status; conference on resident inspector facilties; exit meet-ing on fire protection inspection; follow up of previously open items (IFI, URI, 50.55(e); Bulletins and Circulars).
Results Of the areas inspected, no 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 Construction Engineer, QC for STRIDE G. A. Gonsalves, QA Supervisor A. G. Debbage, QA Audit Supervisor W. T. Quinn, Construction Engineer, BOP
- W. R. Browt, Construction Engineer, STRIDE W. O. Brown, Assistant Construction 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 Engineer, Second Shift M. H. McGrory, Technical Services Supervisor L. H. Jackson, Project Engineering Assistant Construction Engineer N. W. Cravasse, QA Manager, Office of Power G. Killian, Power Production
- Attended exit interview.
2.
Exit Interviews On Wednesday, August 22, 1979 the inspector attended the exit interview conducted by W. H. Miller, RIl fire prevention engineer, concerning Hartsville's fire prevention procedures, personnel and facilities as described in Report 518/79-18.
On Friday, August 24, 1979 the inspector conducted an exit interview with the STRIDE Construction engineer, acting project manager, concerning summari79tica of findings in open items (IFI, URI, 50.55(e), IE Bulletins and Circulars), on work status, and consolidation of document control areas and the drawing spreading rooms. The management representative concurred in the inspection findings.
3.
Licensee Action on Previous Inspection Findings Not inspected (See discussion in paragraphs below of review of open items).
! 4.
Unresolved Items Unresolved items were not identified during this inspection.
5. ___I,ndependent Inspection Effort , _, a.
A followup inspection was made of foundation treatment work for the four spray ponds. The final crosion gullies in the Carters formation beneath and south of pond B2 were being cleaned and filled with crushed rock and fill concrete.
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The inspector made a general tour of nuclear safety related construc-tion areas. Status of construction and supporting activities were observed.
. No noncompliances or deviations were identified.
6.
Resident Inspector Facilities A conference was held on August 22, 1979 with the project manager and construction engineer concerning space and facility requirements for the NRC resident inspector scheduled to occupy site quarters by September 24, 1979. NRC attendees were the inspector, his section chief and the RII Administrative Branch Chief. The licensee was in the process of rehabil-itating a trailer situated between Construction Administration buildings #4 and #5. The general layout of spaces in the trailer were agreed upon, with provisions being made for occupancy by additional resident inspectors as the project advances. Electricity, telephone circuitry, potable water and sewer connections will be provided. A heat pump style air conditioner with over-the-trailer distribution ducting will be installed to facilitate , future relocation of the trailer to the power block area as construction activities intensify.
Access for public visitors of the resident inspector will be arranged by project management upon proper notification.
One telephone station through TVA's board will be assigned to the inspector.
Another will be locked out of their PBX operator's access. A third line will be assigned to the telefax transmitter.
Coordination will be required but there was no disagreement between the conferees on the objectives sought.
7.
Inspector Followup Items (Closed) IFI 518,519,520,521/78-07-01: Revision to Auditing Program for Reactor Pressure Vessels A TVA Office of Power QA audit team conducted an evaluation of G. E. ISE QA program at the Memphis shop of Chicago Bridge and Iron Company on February 13-14, 1979. There were no negative Category A findings during this audit.
/ A meeting was held at the Hartsville site on August 20, 1979 between Con-struction, site QA audit and General Electric representatives concerning the handling, receiving inspection, and placement of the RPV and auditing of the operations. The meeting was in anticipation of the scheduled ar- _r.ival of the Unit A-1 reactor pressure vessel by barge now expectef on October 10, 1979. Receiving inspection will be performed by GE site repre-sentatives, by the ASME authorized inspectors, and by TVA construction 1216 192
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forces under C.E.P. 7.02, Revision 4, dated 4-23-79, " Receiving Inspection."
Construction forces response to the intended QA unit audit of receiving and handling activities are prescribed by C.E.P. 18.01, Revision 5, dated 6-28-79, " Auditing Construction Activities."
- Transporting of the vessel from interim field storage and installation on the RPV pedestal in Unit Al Containment is estimated to start about October 24, 1979 contingent on completion of welding repairs on the pedestal.
(Closed) IFI 518/79-09-01: Low Compresshe Strenghths on Cylinders of Placement AIR-2B Six cylinders tested at 90 days yielded an average strength of 4561 psi versus required strength of 4000 psi.
(0 pen) IFI 518,519,520,521/79-12-04: QA Training for Welders.
(Closed) IFI 519/79-13-01, Low Cylinder Breaks in Pour BIR-2B This matter will be tracked through 50.55(e) Item 519/79-13-01.
8.
Status of Previously Unresolved Items (0 pen) Unresolved Item 518,519,520,521/78-12-01: Failure to recard miti-gating actions following excusions over maximum pH limit and failure to report exceeding maximum assigned pH limit.
(Closed) Unresolved Item 518,519,520,521/78-12-02: Required dust control of batch plant No. I during cement charging phase of operation.
Adequate control has been confirmed by NRC Environmental Engineer.
(Closed) Unresolved Item 518,519,520,521/79-01-03: RIS and PM Procefures prepared prior to receipt of vendor's technical data and RCIC PM data incomplete.
Assignment of storage class for equipment is by computer printout based on the procurement specifications. Equipment manuals which arrive with the article are checked for verification of storage class required. Warehouse-men call Knoxvillle QA Unit whenever the vendor demands a class of storage above that shown on the computer printout. A call is made also whenever field men believe an item should have higher c' ass of storage or tighter preventive maintenance during storage.
(Closed) Unresolved Item 518,519,520,521/79-01-04: Procedures for drilling and grouting and determination of cavity limits for spray ponds not clear.
The controlling documents for drilling and grouting are specification N6C-875 through SRN 19, " Earth and Rock Foundations and Fills"; SOP-2, 1216 193 .
. -4- . " Foundation Evaluation and Treatment"; Specification G-26, " Pressure Grouting of Rock Foundations with Portland Cement"; and QCI C-109, " Drilling and Grouting Inspection". Revisicus to these documents were reviewed.
- The procedure for determining the limits of a cavity is handled on an individual basis on instructions given by the site geologist or a geologic team.
All drill holes and grouting pipes whose exact locations were uncertain from the records have been located, removea or completed, and accurately mapped.
The problem of cavity limits for the area of spray ponds A-1 and B-2 and the rock dike area was rendered moot by removal of the earth and Hermitage formation rock down to the Carters formation and the treatment of the foundation rock with dental concrete and fill concrete.
(0 pen) Unresolved Item 518,519,520,521/79-03-02: Storage and control of drawings.
Drawing storage and spreading rooms are being consolidated into STRIDE and BOP groups, following curtailment of construction of Plant B facilities.
Microfilming of drawings is in process.
(Closed) Unresolved Item 518,519,520,521/79-08-01: Inspection status and centrol of safety related equipment in warehouse storage areas.
The Site QA unit Supervisor prepared an " Inspection and Test Status Flow Chart" which shows the sequence of activities and references the controlling procedure for each s' :p ?nd the various tags used.
Control of the current inspection, test and operating status is through C.E.P. 14.01, Revision 1, dated 7-23-79, and by QA unit audits.
9.
Status of Previous Licensee Identified 50.55(e) Items (Closed) 50.55(e) Item 518,519/78-06-01: Inryco S. S. Sump Liners, Defective Welds.
A supplement to the licensee's " final" report to RII on this matter was issued on February 23, 1979. It described the corrective actions already taken and those planned for liners still in storage.
On August 23, 1979 the inspector was told by the assistant construction engineer, engineering services, that corrective actions had been completed.
- NCR HNP A-014 has been closed out.
-~ (0 pen) 50.55(e) Items 520,521/78-06-02, 519/78-06-03, 518/78-06-04: H. P.
core spray motor control center wiring discrepancies-NCR-HNP-A-013.
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. -5- . The licensee's " Supplement to Final Report" dated February 28, 1979 stated that completion of corrective actions is planned by September 28, 1979.
On August 23, 1979 the inspector was told that corrective work had been com-pleted by General Electric but that documentation had not been provided through (GE) site representative John E. Nichols.
~ (Closed) 50.55(e) Item 518,520/78-08-03: H. P. core spray diesel generator control switchgear, wirirg discrepanci s-NCR-HNP-A-021, Units A-1 and A-2.
The Hartsnille HPCS DG switchgear for all flow units was returned by GE to the Morrison-Knudson shop for correct identification and documentation of the as-built and as-tested circuitry.
TVA's final report dated March 3, 1979 indicated that ne gear would be released to the site only after documentation and rework had been inspected and approved.
(Closed) 50.55(e) Item 518,519,520,521/78-15-01: Use of non-ASME compo-nents on primary containment personnel access airlocks-NCR CHT/PB-78-1.
TVA's final report, dated August 16, 1979, has been received. The W. J.
Woolley Company has been directed to redesign and refabricate the airlock systems to include ASME Class 2 components as required. The W. J. Woolley Ccmpan'; has submitted the rede gn for approval.
The redesign is presently under review by the technical engineer and TVA. The final approved design will include ASME class 2 components in the personnel access airlocks as required. Documentatica received with the fabricated airlocks will be reviewed to ensure that all design requirements have been met.
(0 pen) 50.55(e) and Part 21 Item 518,519,520,521/79-03-03: General Electric Design Deficiency - Safety Relief Valve Control System.
TVA's final report on this matter dated August 29, 1979 stated that TVA endorses the design modifications proposed by General Electric to correct the design deficiency. TVA is to implement the modifications and any other measures as approved and directed by NRC-NRR.
This item is lett. ep n pending notification on NRR action.
(0 pen) 50.55(e) Item 518,519,520,521/79-10-02: Factor of safety for actual design of welded anchors-NCR-CEB-79-16.
TVA's second report on this matter dated August 13, 1979 stated that a final report would be submitted by December 21, 1979.
(0 pen) 50.55(e) Item 518,519,520,521/79-12-05: Reactor pedestal weld cracking NCR HNP-A-050.
7A repair work was in process during this inspection'. ~~ (0 pen) 50.55(e) Item 50-519/79-13-01: Use of incorrect concrete mix in Unit B-1 shield building wall pour B1R-2B.
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. -6- . The licensee anticipates that the concrete will attain the required average test results of 4005 psi. The 90 day breaks of three cylinders on August 5, 1979 (#10401) averaged 4156 psi. Those from cylinders (#10402) averaged 3873 psi; cylinders (#1186) averaged 3396 psi. Additional testing will be made at 180 day step on November 3, 1979.
~ (0 pen) 50.55(e) ani Part 21 Item 518/79-13-02: Faulty welding by Lakeside Bridge and Steel oi drywall vent structure NCR HNP-A-038.
TVA interim report dated July 5, 1979 states that TVA will perform necessary investigation and h7E of Lakeside's weld preparation repairs on vent wall sections and accomplish repairs acceptable to the GE technical engineer and to TVA QC after ratest.
TVA's final report is to be transmitted on or before October 1,1979.
(0 pen) 50.55(e) Item 518,519,520,521/79-19-01: Defective GE SB-12 auxiliary switches in safety-related switchgear (NCR-2-1).
TVA's final report, dated August 16, 1979, stated that ESW switchgear which had been shipped to Hartsville will be reequipped with the replacement SB-12 auxiliary switches to be supplied by GE-SBD. These replacement sw_tches are to be installed by February 29, 1980. Other shipments of switchgear to Hartsville will have the replacement switches installed by GE-SBD before shipment.
NOTE: IE Circular No. 79-17, entitled Contact Problem in SB-12 Switches on General Electric Metalclad Circuit Breakers, has been issued on this matter.
10.
Status of Inspection and Enforcement Bulletins The following bulletins are being closed out for record because of non-applicability to Hartsville, for information only, or no action required by site personnel: (Closed) Bulletin No. 78-9; 78-13; 79-01; 79-01A; 79-05; 79-08; 79-10; 79-12; 79-13; 79-16, 79-17; 79-18, 78-19, 79-20; 79-21 and 79-22.
The following bulletins are held open pending completion of regional and IE-HQ evaluations: ~ (0 pen) Bulletins 78-12; 78-12A; 79-02; 79-02, Rev. 1 The status of additional bulletins is as follows: (Closed) Bulletin 79-03, Longitudinal Weld Defects in.ASME SA-3,12 Type 304 _~ Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Company (YWEC).
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. -7- . TVA's response dated March 12, 1979, transmitted by letter dated July 13, 1979 assures that no YWEC pipe of this type has been procured for use at Hartsville.
(0 pen) Bulletin 79-14 thru Supplement 2: Seismic Analysis for As-built Safety-Related Piping Systems.
(0 pen) Bulletin 7 -15: Deep Draft Pump Deficiencies.
/ 11.
Inspection and Enforcement Circulars The licensee has received, evaluated and initiated appropriate action on the following I&E circulars: Circular 78-08: Invironmental Qualificatica of Safety Related Electrical Equipment.
Circular 79-11: Design Instruction !Dterface Problems.
Circular 79-12: Potential Diesel Generator Turbocharger Problem.
Circular 79-13: Replacement of Diesel Fire Pump Starting Contactors.
Circular 79-16: Excessive Over Exposure to Members of the Public and Radiologists.
Circular 79-17: Contact Problem in SB-12 Switches on General Electric Metal Clad Circuit Breakers.
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