IR 05000566/1979010
| ML19208C661 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 08/02/1979 |
| From: | Cantrell F, Gouge M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19208C656 | List: |
| References | |
| 50-566-79-10, 50-567-79-10, NUDOCS 7909270198 | |
| Download: ML19208C661 (7) | |
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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ATLANT A, GEORGI A 30303
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Report Nos. 50-566/79-10 and 50-567/79-10 Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name: Yellow Creek Nuclear Plant, Units 1 and 2 Docket Nos. 50-566 and 50-567 License Nos. CPPR-172 and CPPR-173 Inspection at Yellow Creek Site near uka, Mississippi Inspector:
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I2!77 ms M. J. Gouge
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Date Signed
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Accompanying Personnel:
F. S. Cantrell 8' I
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Approved by:
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F.S.Cantrell,ActingSectidngfef,RCESorancli Date Signed SUMMARY Inspection on July 24-27, 1979 Areas Inspected This routine, unannounced inspection involved 36 inspector-hours on site in the areas of licensee action en previous inspection findings, IE Bulletin followup, QA audit review, concrete placement (Unit 1), safety-related welding (Unit 1),
and inspection of warehouse areas.
Results Of the six areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- M. M. Price, Project Manager L. S. Cox, Construction Engineer S. G. Carr, Assistant Constructica Engineer (PE)
- C. G. Wages, Assistant Construction Engineer (QC)
- J. N. Holl day, Supervisor, Project QA Unit
- J. D. Shanlever, Supervisor, Material Services Unit
- S. E. Alge, Supervisor, DCU E. W. McGuire, General Labor Foreman G. B. Alexander, Civil QC Unit D. P. Reynolds, Civil QC Unit
- C. M. Freeman, Civil QC Unit
- S. P. Watson, DCU J. B. Nelson, Project QA Unit L. B. Parker, Project QA Ur.it G. A. Beasley, Material Services Unit Other licensee employees contacted included various construction craftsmen, technicians and office pr.rsonnel.
Other Organizations Chicago Bridge and Iror. Company C. L. Spears, QA Superintendent L. Savage, QA Technician
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on July 27, 1979, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Infraction 566/79-09-03: Concrete Activities. 1he licen-see's corrective action is specified in the response letter dated July 12, 1979. Region II has reviewed this response which describes acceptable measures to correct the noncompliance and to prevent recur-rence of similar problems. The licensee implemented corrective action immediately to stop the practice of discarding out of specification concrete. samples. Spray nozzles in the moist curring room have been cleaned and an additional spray header installed to prevent concrete
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cylinders from drying out.
Cylinder molds are being removed from the cylinders in accordance with the licensee's procedures.
Concrete inspectors and concrete craft personnel have been instructed rrgarding the correct use of vibrators. The project inspector observed Category I wall pour Al-E73 described in further detail in paragraph 6a.
Vibration of concrete was observed to be in confort,ance with the licensee's pro-cedures and concrete was placed in a manner that precluded excessive horizontal flow.
This item is closed.
b.
(Closed) Infraction 566/79-09-04:
Bulkweld Powdered Metal Chemical Analysis. The licensee'n corrective action is specified in the re-sponse letter dated July 12, 1979. Region II has reviewed this re-sponse which describes acceptable measures to correct the noncom-pliance and to prevent recurrence of a similar problem.
Chicago Bridge and Iron Company (CBI) has received a revised certified material tert report (CTR) for bulkweld powdered metal heat number 0479008. The revised CTR indicates that the powdered metal meets the requirements of SFA 5.17 of Section II, Part C of the ASME Code for all six elemental concentrations. The containment plates that had been placed on hold due to the incomplete original CTR have been released from the CBI nonconformance list.
This item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inspection and Enforcement Bulletins (IEBs) (Units 1 and 2)
The licensee has received and reviewed IEBs through IEB 79-15 at the site.
The project manager and const ruction engineer review all IEBs for site applicability and coordinata a response if needed with corporate design and licensing personnel. The follcwing IEBs are not applicable to the site or require no action (issued for information only):
IEB 79-01, 01A IEB 79-05, 5A, 5B IEB 79-06, 6A, 6B IEB 79-08 IEB 79-10 IEB 79-12 IEB 79-13 1049 072
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The bulletins listed above are closed. The bulletins listed below required action by the licensee and their status is indicated as follows:
a.
(0 pen) IEB 78-12, 12A, 12B: Atypical Weld Material in Reactor Pressure Vessel Welds. TVA has submitted responses dated May 29, 1979, and July 9, 1979. TVA is currently reviewing the Combustion Engineering generic response dated June 8, 1979, and will submit a supplemental report by August 31, 1979.
This item remains open.
b.
(0 pen) IEB 79-02:
Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. Region II is currently reviewing TVA's response dated July 5, 1979.
This item remains open.
c.
(Closed) IEB 79-03: Longitudinal Weld Defects in ASME SA-312 Type 304
, Stainless Pipe Spools: The licensee's response dated July 13, 1979, states no ASME SA-312 stainless steel pipe spools of the type refer-enced in the bulletin have been procured for use in safety-related syrtems on site.
This item is closed.
d.
(Closed) IEB 79-04:
Incorrect Weights for Velan Swing Check Valves.
The licensee's response dated May 31, 1979, states that no 3-inch, 4-inch, or 6-inch diameter Velan swing check valves are installed or scheduled for installation in any seistic Category I piping system.
This item is closed.
(Open) IEB 79-07:
Seismic Stress Analysis of Safety-Related Piping.
e.
Region II is currently reviewing TVA's response dated May 31, 1979.
This item remains open.
f.
(Closed) IEB ;9-09: Failure of GE Type AK-2 Circuit Breakers in Safety-Ralated Systems. The licensee's response dated June 20, 1979, states that GE type AK-2 circuit breakers are neither in use nor are planned for use in safety-related systems.
This item is closed.
6.
Independent Inspection a.
Concrete Placement (Unit 1)
The inspector observed placement of Category I concrete wall pour Al-E73 at elevation 450.5 feet in the Unit I reactor building area.
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-4-Acceptance criteria examined by the inspector are specified in the following documents:
(1) Section 3.8 of the PSAR and TVA Topical Report TR-75-1A (2) TVA Specification G-2, " Plain and Reinforced Concrete" (3) Quality Control Instructions C-201 through C-214 (4) Drawing 4RE0417-5R-1, Walls and Slabs (5) Drawing 4RE0418-5R-1, Reinforcement (6) Specification N8C-887, " Plain and Reinforced Concrete" Forms were tight after some minor repairs and clean.
Preplacement inspection was indicated by the completed pour card.
Areas inspected included deliverf, conveying, placement, consolidation, and curing of concrete. The following records were reviewed by the inspector for pour Al-E73:
(1) Concrete Pour Card (2) Concrete Sample Data Sheet (3) Mixing Plant Report (4) Slump Control Record (5) Concrete Curing Report Concrete operations were continuously monitored by Civil QC personnel.
Concrete placement, testing and inspection were conducted in accordance with applicable procedures.
No items of noncompliance or deviations were identified.
b.
Quality Assurance (QA) Audits (Units 1 and 2)
The following audits conducted by the site QA unit were examined by the project inspector for completeness, deficiencies found, corrective action taken and implementation in accordance with the licensee's procedures QASP 7.1 and CEP 18.01:
Audit No.
Subject YC-G-79-07 Housekeeping during the Construction Phase of Nuclear Power Plants YC-G-79-08 Receiving Inspection 1049 074
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YC-G-79-09 Quality Control Investigation Reports and Nonconforming Condition Reports YC-G-79-10 Surveillance of Site Contractors Activities -
Containment Vessel Erection YC-S-79-01 Containment Vessel YC-W-79-01 Welding Activities and NDE Activities The above audits were found to be conducted and documented in an objective manner.
No items of noncompliance or deviations were identified.
Safety-Related Welding (Unit 1)
c.
The innpector observed fitup, welding and inspection of various three-quarter-inch socket welds in the chilled water system (VA). The applicable weld procedure for these Class C ASME Code welds is GT-88-01, Revision 5.
areas inspected included fitup, control of preheat and interpass temperature, welding rod control, weld technique, and welder qualification to the procedure referenced above. The procedures had been reviewed by the Aethorized Nuclear Inspector (ANI)'and ANI hold points had been identified on the weld control cards. Welds had been properly identified on the weld map. Fitup, welding and inspection were conducted by qualified personnel in accordance with applicable procedures.
No items of noncompliance or deviations were identified.
d.
Inspection of Warehouse and Storage Facilities (Units 1 and 2)
The project inspector conducted an inspection of site warehouses A and B and the adjacent storage yards. Areas inspected included assignment of proper storage level, control of received items, control of nonconforming items, identification or marking of stored items and access control to the warehouse areas.
Items received are placed in a 1049 075
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cage pending completion of QC receipt inspection and proper marking.
All nonconforming items were observed to be in the QC hold cage with the exception of two charging pumps that were stored in a separate location due to their size. Two safety-related component cooling water (CCW) heat exchangers were stored in the outside storage yard.
These items were in a QC hold status pending disposition of numerous discrepancies noted on receipt inspection.
The licensee has imple-mented a computer program and associated data input cards to control the accomplishment of preventive maintenance on safety-related items in storage. The effectiveness of this program could not be evaluated due to the short period of time safety-related items requiring preven-tive maintenance have been on site.
No items of noncompliance or deviations were identified.
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