IR 05000338/1979023
| ML19249B892 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/05/1979 |
| From: | Conlon T, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19249B873 | List: |
| References | |
| 50-338-79-23, 50-339-79-32, 50-404-79-04, 50-405-79-04, NUDOCS 7909070044 | |
| Download: ML19249B892 (6) | |
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3., gg(',,g NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA sT., N.W., sulTE 310o o,
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AT L ANTA, GEORGI A 30303
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Report Nos. 50-338/79-23, 50-339/79-32, 50-404/79-04 and 50-405/79-04 Licensee: Virginia Electric and Power Company Post Office Box 26666
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Richmond, Virginia 23261 Facility Name: North Anna Power Station, Units 1, 2, 3, 4 Docket Nos. 50-338, 50-339, 50-404, and 50-405 License Nos. NPF-4, CPPR-78, CPPR-114, CPPR-115 Inspection at North Anna Site near Mineral, Virginia Inspector: d[8 b
7/f/79 J. J. Lenahan Date Signed
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Approved by I I 7[f [74 p
T. E. Conlon, Section Chief, RCES Branch D' ate Signed SUMMARY Inspection on May 29-June 1, 1979 Areas Inspected This routine, unannounced inspection involved 26 inspector-hours onsite in the areas of structural concrete QA/QC controls, work activities and quality records, Units 1 and 2 service water pumphouse settlement records, Unit 2 containment structural integrity test quality records, and licensee actions on previous inspection findings.
Results Of the four areas inspected, no apparent items of noncompliance or deviations wo e identified in three areas; two apparent items of rencompliance were found in one area (Infraction - Failure to calibrate conc ~: + batch plant scales -
paragraph 3, and Deficiency - Testing of plant'
.ucrete paragraph 8).
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DETAILS 1.
Persons Contacted Licensee Employees
- P.- A. Slater, Resident QA Engineer
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A. Harrision, QC Engineer P. G. Perry, Senior Pesident Engineer T. Johnson, QC Engineer D. S. Hart, QC Engineer D. Maclean, Supervisor, Engineering Services, Units I and 2 R. C. Sturgill, Assistant Engineer, Units 1 and 2 B. Brookman, QC Inspector Other Organizations Stone and Webster Engineering Corporation (S&W)
- D. P. Barry, Resident Enginee., Units 1 and 2, S&W
- A. J. Foussekis, Resident Engitter, Units 3 and 4, S&W J. Sullivan, Structural Engineer, S&W Champion, Inc.
D. A. VanLoon, QC Engineer NRC Resident Inspector M. S. Kidd
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on June 1, 1979, with those persons indicated in Paragraph I above.
The licensee acknowledged the noncompliances discussed in paragraphs 3 and 8.
3.
Licensee Action on Previous Inspection Findings (Open) Unresolved Item (338/79-13-01): Review of Piezometer Data.
a.
The inspector reviewed the latest revision to Periodic Test No.
1-PT-75.7, " Service Water Reservior-Ground Water Level". The revised procedure requires plotting of the piezometer data in orde -
to perform a trend analysis and assist in disclosing potentially incorrect readings. The revised procedure also requires initiating a settlement survey of the SWPH if piezometer data indicates a drop in the ground water table elevation in the vicinity of the SWPH.
Discussions with responsible licensee representatives disclosed that the manufacturer of the pore pressure indicator (instrument used to
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read piezometers) and piezometers visited the site in late March and reviewed the licensee's procedures, observed the licensee's repre-sentatives while they collected the piezometer data, and checked the instrument and piezometers to verify they were in good working condition. This item remains open pending NRC review of the manu-facturer's report.
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b.
(Closed) Unresolved Item (404/405/79-03-02):
Calibration of Batch Plant Scales. Examination of quality records disclosed that the concrete batch plant ccales had not been calibrated since March 24, 1978, when the scale calibration had been performed by the Common-wealth of Virginia, Department of Agriculture.
Specification NAS-30113, dated Janua ry 24, 1979, requires that the concrete batch plant scales be calibrated every 90 days. Discussions with respon-sible engineers and review of quality records disclosed that quality concrete had been placed in rait 3 powerblock area after expiration of the last calibration of the batch plant scales (March 24, 1978).
This item is closed as Unresolved Item 404/405/79-03-02 and upgraded to Infraction Number 404/79-04-01, " Failure to Calibrate Concrete Batch Plant Scales".
The inspector examined Quality Control Instruction 10.2.1,
" Calibration of Batch Plant Equipment and Measuring Devices",
approved on April 30, 1979, which was prepared by the licensee to specify requirements for calibration of the concrete batch plant scales. The procedure requires calibration of the batch plant scales throughout their full range every 90 days.
The batch plant was calibrated in accordance with this procedure on April 28, 1979.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort This inspector examined the following areas:
a.
Reinforcing steel laydown area.
b.
Concrete laboratory and currentness of calibration of laboratory equipment.
c.
Construction status of Units 3 and 4.
d.
Units 1 and 2 Service Water Pumphouse (SWPH) settlement data.
SWPH settlement surveys have been performed on a weekly basis since April 6, 1979, when the average SWPH settlement was 0.138 feet.
This amount is 92 percent of the total average SWPH settlement permitted by Technical Specification 3.7.12.1.
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-3-reviewed the results of the weekly surveys made through'May 23, 1979. The survey results indicate no additional SWPH settlement since April 6, 1979.
No deviations or items of noncompliance were identified.
6.
Containment Structural Integrity Test (SIT) - Unit 2 The inspector examined Nonconformance and Dispisition Report Number 3774(N&D 3774). This report was generated due to cracks opening in the concrete containment structure during the SIT in excess of the FSAR predicted value of.03 inch. These cracks occurred at the springline of the dome and adjacent to the equipment batch. N&D 3774 was closed on April 27, 1979, upon completion of the SIT and examination of the cracks by S&W structural engineer. Dispostion of N&D 3774 was to accept "as is" No repairs were required since the cracks closed to less than.005 inch. The inspector examined the containment structure areas where the cracks occured and observed that the cracks were barely visible.
No deviations or items of noncompliance were identified.
7.
Containment (Structural Concrete) - Review of Quality Assurance Implementing Procedures - Units 3 and 4 The inspector examined QA/QC controls for containment structural concrete.
The following procedures were examined to determine if work activities and quality control and quality assurance functions were provided for as stipulated in NRC requirements and PSAR Sections 15.3, 15.4 and 15.5.
Specification NAS-30113, " Mixing and Delivering Structural and Heavy a.
Aggregate Concrete" b.
Specification NAS-30114, " Structural Concrete Testing Services" Specifiction NAS-30120, " Placing Concrete and Reinforcing Steel" c.
d.
Quality Control Instruction 10.2, " Concrete Quality Control" Quality Control Instruction 10.2.1, " Calibration of Batch Plant e.
Equipment and Measuring Devices" f.
Construction Procedure P0P-804, Rev.
2, " Field Procedure for Concrete Placement - Vertical Exterior Walls - Reactor Containment" No deviations or items of noncompliance were identified.
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8.
Containment (Structural Concrere II) - Observation of Work and Work Activities, Unit 3 The inspector observed partial placement and inspectionof pour number 9390-3, pour 2, in the wall of the Unit 3 reactor containment building.
Acceptance criteria examined by the inspector were drawing numbers 1RJ80-FC-49D-5 and 12180-FC-49G-3, Sheet 7, and those procedures listed in paragraph 7.
Forms were tight, clean and level.
Rebar was properly installed and clean. Placement activities pertaining to delivery time, f ree f all, flow distance, layer thickness and consolidation conformed to specification.
Concrete placement activities were continuously monitored by QC inspectors.
Samples of plastic concrete were obtained from the pumpline discharge.
Examination of batch tickets indicated that the specified design mix was being delivered Examination of the batch plant indicated materials were being controlled and accurate batch records were being generated.
Storage of materials (aggregate, cement and air-entraining admixtures) were observed to be in accordance with specification requirements. Batch plant activities were continously monitored by QC inspectors.
Observat.ons of inprocess tests for slump, air content, temperature, unit weight and cylinder molding disclosed the following noncompliance.
Construction Quality Control Instruction 10.2 requires that plastic concrete be sampled in accordance with ASTM-C-172. ASTM C-172 requires that tests for air content and slump be started within 5 minutes after sampling of concrete is completed. ASTM C-172 requires that molding of concrete cylinders be started within 15 ninutes after sampling.
Obser-vations of inprocess testing by the inspector, discussions with quality control inspectors, and review of quality control records disclosed that the 5 minute limit was exceeded for slump and air content tests performed on 4 of 10 samples of record on May 30, 1979.
However molding of cylin-ders, which form basis of final acceptance of the concrete, was started within the 15 minute time limit.
This was identified to the licensee as Deficiency Number 404/79-04-02.
No deviations were identified.
9.
Containment (Structural Concrete II) - Review of Quality Records - Unit 3 The inspector examined the following records relating to pour number 9390-3, pour number 2 in the wall of the Unit 3 Reactor Containment Building:
a.
Mixer efficiency tests.
b.
Batch plant scale calibration records of April 28, 1979.
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Testing records of 7 QC inspectors.
d.
Preplacement inspection record (pour card).
Acceptance criteria examined by the inspector are listed in parag.aph 7.
No deviations or items of noncompliance were identified.
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