IR 05000327/1979063
| ML19260C417 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/15/1979 |
| From: | Cantrell F, Gouge M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260C416 | List: |
| References | |
| 50-327-79-63, 54-328-79-31, NUDOCS 7912260306 | |
| Download: ML19260C417 (5) | |
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'o,, UNITED STATES
NUCLEAR REGULATORY COMMISSION o $ E REGION Il
e' o 101 MAR!ETTA ST., N.W., SUITE 3100 o ATLANTA, GEORGIA 303o3
NOV 161979 Report Nos. 50-327/79-63 and 50-328/79-31 Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name: Sequoyah Nuclear Plant Docket Nos. 50-327 and 50-328 License Nos. CPPR-72 and CPPR-73 Inspection at Sequoyah Site near Dai Tennessee 8//Y/77 Inspector: / / mf-M. J. Gouge / ' Date Signed [[/ ////5/) Approved by: ? F.S.Cailtrell,Sectionthp,RC&ESBranch Dhte Sign'ed SUMMARY Inspection on October 30 - November 1, 1979 Areas Inspected This routine, unannounced inspection involved 22 inspector-hours onsite in the areas of 10 CFR 50.55(e) items, nonconformance report control and observation of safety-related work activities.
Results Of the three areas inspected, no items of noncompliance or deviations were identified.
1618 291 7912260
B DETAILS 1.
Persons Contacted . Licensee Employees
- G. G. Stack, Project Manager
- J. E. Wilkens, Construction Engineer E. G. Beasley, Nuclear Safety Review Staff J. W. Coan, Sequoyah Design Project R. D. Guthrie, CEB, ENDES M. A. McBurnett, Nuclear Engineer, Regulatory Staff
- C. M. Callihan, Nuclear Engineer, Regulatory Staff D. L. Wall, Nuclear Licensing, ENDES C. R. Morgan, Nuclear Licensing, ENDES
- R. W. Olson, Assistant Construction Engineer
- J. L Smith, Assistant Construction Engineer
- D. W. Mack, Assistant Construction Engineer
- J. M. Munns, Supervisor, Construction QA
- R. W. Farrell, Supervisor, QC Records Unit
- E. C. Pendergrass, Engineer, QC Records Unit P. Elia, Unit 1 Coordination Unit J. A. Naik, Unit 1 Coordination Unit J. C. Prevo, Unit 1 Coordination Unit W. Loomis, Unit 1 Coordination Unit K. G. Galloway, Welding Inspection Unit Other licensee employees contacted during this inspection included various construction craftsmen and technicians.
Other Organizations Westinghouse Electric Corporation R. Mathieson, Site Manager NRC Resident Inspector
- W. T. Cottle
-
- Attended exit interview
-2- , 2.
Exit Interview The inspection scope and findings were summarized on November 1, 1979, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
- 4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Licensee Identified Items (Units 1 and 2) TVA has reported a number of items to Region II as reportable in compliance with 10 CFR 50.55(e).
The Region II inspector reviewed the items listed below and the supporting documentation, and discussed the items with respon-sible licensee staff during the inspection.
a.
(Closed) Item 50-327/79-12-09 and 50-328/79-07-09: Main Feedwater Line Water Hammer (MEB 79-1).
The inspector reviewed the TVA final report dated May 16, 1979, and the revised final report dated October 10, 1979. The licensee has analyzed the ability of the main feedwater check valves and associated piping to remain functional following the most severe postulated main feedwater line break. The results of these analyses conclude that the main feedwater line check valves and associated piping will maintain their integrity and remain functional under all expected accident conditions.
b.
(Closed) Item 50-327/79-36-02 and 50-328/79-21-02: Reactor Vessel Insulation Supports.
The inspector reviewed the licensee's final report dated October 26, 1979, the closed NCR CEB 79-20, FCR W-47 and various vendor drawings. The restraint system installed in Unit I by TVA to prevent excessive movement of the insulation during a seismic event was inspected.
The bumper restraint arrangement was installed in accordance with FCR W-47.
The restraint system will be installed in Unit 2 in accordance with vendor drawings as revised by FCR W-47.
c.
(0 pen) Item 50-327/79-53-01 and 50-328/79-28-01: RHR Pump Service Factor.
The licensee has submitted a final report on this item, NCR NEB 79-3, dated October 17, 1979. The inspector reviewed records of the following Unit I welds in the Safety Injection and Residual Heat Removal systems: ISI00002A 1618 293 ISI00002E ISI00011A ISI00011E IRH00042A IRH00042C
-3- . Records reviewed included fitup inspection, visual inspection, PT inspection, RT inspection and operations check list.
These welds were required to install flow restrictors in each RHR pump hot leg and the cold leg injection header. This modification was documented by closed ECN 2653 and controlled in Unit 1 by work plan 5188.
This item remains open pending review by the resident inspector of preoperational test data of the system flow testing to verify effectiveness of this modi-fication.
' d.
(0 pen) Item 50-327/79-63-01 and 50-328/79-31-01: Inadequate Design of Containment Spray Heat Exchangers.
On October 24, 1979, TVA informed Region II of this reportable item identified as NCR 16P. A 30-day written report is due November 23, 1979.
6.
Independent Inspection Effort (Units 1 and 2) Review of Nonconformance Reports (NCR) a.
The inspector reviewed all open construction project NCR's.
Construc-tion Procedure P-2, R12 entitled " Handling Nonconformances" specifies procedures for the handling and control of NCR's.
Open NCR's through NCR 1928 were inspected for conformance to the above procedures, adequacy of proposed corrective action, and proper evaluation of significance. Site QA audit SN-G-79-19, "Nonconformances" was reviewed by the project inspector. NCR's are handled in accordance with proce-dure P-2 and proposed corrective action is adequate for those NRC's reviewed. Significant NCR's had been properly identified and reported to the NRC. There were approximately 20 open NCR's that affected safety-related components or structures in Unit 1 or common facilities.
The project inspector requested that the licensee review these items to ensure that corrective action, if applicable, is completed prior to fuel loading of Unit 1.
This item will be monitored by the project inspector and is identified as inspector followup item 50-327/79-63-02: Open Unit 1 NCR's.
No items of noncompliance or deviations were identified.
b.
Observation of Safety-Related Activities The Region II inspector observed installation of cadweld 147 in the Essential Raw Cooling Water (ERCW) Pump House. Areas inspected included alignment of cadweld sleeve, preparation of rebar sur' face, actual cad-welding, QC inspection of the completed cadweld and qualification of the cadwelder.
In process welding of weld 2CX00012D was observed in the auxiliary building. This weld joined parts 2CVC9 and A376. This 6", Class B weld was performed to weld procedure GT-88-01.
Areas inspected included 1618 294
. -4-J documentation of fitup inspcetion, proper adherence to QC hold points, purge gas control, control of interpass temperatures, welder qualifi-cation, welding rod control and weld techniques.
The project inspector conducted a general walk-through inspection of Units 1 and 2 Containment Buildings and the auxiliary building. Areas inspected included general housekeeping practices, storage of QA materials, rigging practices, measures to control cleanliness of ~ piping, and installation of various supports for safety-related piping and valves.
No items of noncompliance or deviations were identified.
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