IR 05000327/1979003
| ML19261C056 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/05/1979 |
| From: | Conlon T, Crowley B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19261C051 | List: |
| References | |
| 50-327-79-03, 50-327-79-3, NUDOCS 7903140499 | |
| Download: ML19261C056 (6) | |
Text
UNITED STATES
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- o, NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 M ARIETT A STREET, N.W.
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ATLANTA, CEORGIA 30303
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Report Nos.: 50-327/79-03 and 50-328/79-01 Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name: Sequoyah Nuclear Plant, Units 1 and 2 Docket Nos.: 50-327 and 50-328 License Nos.:
CPPR-72 and CPPR-73 Inspection at Sequoyah *ite near Daisy, Tennessee Inspector:
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B. R. Crowley 1) ate Approving b M [ I k m W
T. E. Conlon, Section Chief, RCES Branch
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Inspection on January' 15-17, 1979 Areas Inspected This routine, unannounced inspection involved 24 inspectorhours onsite in the areas of reactor coolant pressure boundary piping activities and records (Unit 2), Safety related piping activities and records (Unit 2), housekeeping and general construction activities (Units 1 and 2), and previously identified inspection items (Units 1 and 2).
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Results Of the four (4) areas inspected, no apparent items of noncompliance or devia-tions were identified.
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DETAILS 1.
Persons Contacted Licensee Employees G. G. Stack, Project Manager, Construction J. W. Wilkins, Construction Engineer L. W. Jones, Welding Inspection Unit Supervisor W. C. Hatmaker, Welding Engineer M. F. Steakley, Welding Engineer D. G. Collins, Lead Inspector J. A. Thompson, Mechanical Engineering Group Leader J. D. Thornton, Mechanical Engineering Group Leader D. M. Watson, Mechanical Engineer Jan Bajreszewski, Mechanical Engineer E. C. Pendergrass, QC Records Unit Other licensee employees contacted included construction craftsmen, inspectors, and engineering personnel.
2.
Exit Interview The inspector had no items of noncompliance or deviation. These findings and a list of areas inspected were turned over to E. J. Vallish (RII) for presentation at the exit meeting to be conducted on January 19, 1979.
3.
Licensee Action on Previous Inspection Findings (Closed) Item of Noncompliance (327/78-33-02 and 328/78-24-01):
Failure to log weld rod oven temperatures. The inspector reviewed the licensee's corrective action and " Temperature Log of Rod Ovens" dated
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11/12/78 through 1/10/79 for the number 4 (Turbine Building) rod room and 1/15/79 through 1/17/79 for the number 1 (Elevation 690, Auxiliary Building) rod room. There are no further questions at this time.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort The following areas of interest were reviewed by the inspector:
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-2-a.
Walk-Through Inspection A general walk-through inspection of Units 1 and 2 (reactor building and auxiliary building) was made. Housekeeping and general construction activities were observed.
b.
Safety Related Piping (Welding) - Observation of Work and Work Activities (Unit 2)
The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various stages of weld completion. The applicable code for safety-related pipe weldin; is ANSI standard B31.7, 1969 Edition and the 1970 Addenda.
Observation of field welding activities included, where applicable, the following areas; weld identification and location, joint preparation and alignment, specified weld procedure, welder qualification, specified weld material, specified purge, specified preheat temperature, welding variables within limits and evidence of QC verification.
(1) Joint Fi jtu Joint h" umber Isometric System 2CX02633 206 CVC (2) Root Pass Joint Number Isometric System ICX02633 206 CVC (3)
Intermediate Pass Welding Joint Isometric System OUDT939B
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SI 2SI01666
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SI 2SI01667
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SI 2SI01672
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SI 15101655
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MS JMS00039
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2SE09258 276 SE 2CX02658 206 CVC 2MS00009 400 MS 2HY00579A 569
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(4) Observation of weld material control included; identification,
segregation, oven temperature, issue slips and control of unused material at issue stations 1 and.
-3-Within the areas examined, no items of noncompliance or deviations were identified.
6.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities (Unit 2)
The inspectot observed field welding as described below relative to reactor coolant pressure boundary piping. The applicable code for this welding is ANSI Standard B31.7, 1969 Edition and the 1970 Addenda.
Observation of field welding activities included, where applicable, the following areas; weld identification and location, use of applicable welding procedure, welder qualification, use of specified weld material, weld appearance, and evidence of welding variable checks.
a.
Weld Observed Joint Isometric System Size Status 2CX01078 501 CVC 2"
Final Layer b.
Weld Material Control Observation of weld material control included; identification, segregation, oven temperatures, issue slips and control of unused material at issue stations 1 and 4.
Within the areas examined, no items of noncompliance or deviations were identified.
7.
Reactor Ccolant Pressure Boundary Piping (Welding) - Review of Quality Records (Unit 2)
The inspector reviewed nonconformance reports 190, 233, 360, 361, 538, 539, 550, 863,1016, and 1160 relative to reactor coolant pressure
boundary pipe welding (see paragraph 6 above for the applicable code for reactor coolant pressure boundary pipe welding).
Within the areas inspected, no items of noncompliance or deviations were identified.
8.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities (Unit 2)
The inspector observed piping work activities as described below relative to reactor coolant pressure boundary piping. The applicable code is the same as that referenced for welding in paragraph 6 above.
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The following partially completed piping runs were inspected for compliance with the applicable code and drawings:
(1) RHR line between weld 85 at loop 4 and weld 86 at valve 2FCV 74-1 per drawings:
NAVC0 A7456 "TVA Contract 71C33 - 92615, Residual Heat Removal" and TVA 47W432 - 3 " Mechanical Residual Heat Removal System Piping" (2) Safety Injection line between weld 169 at valve 2-63-561 and weld 168 at valve 2-63-623 per drawings:
NAVC0 A7541 "TVA Contract 71C33 - 92615, Safety Injection System, LHSI to #2 and #3 Accum.
Pen. X20B" and TVA 47W435 -
14 " Mechanical Safety Injection Piping System" b.
The following pipe spools were observed in storage:
2UPI - 34 2UPI - 32 2UP1 - 40 Within the areas inspected, no items of noncompliance or deviations were identified.
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9.
Reactor Coolant Pressure Boundary Piping - Review of Quality Records (Unit 2)
The inspector review;d quality records as described below relative to reactor coolant pressure boundary piping activities. The applicable code is the same as that referenced for welding in paragraph 6.
above.
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Installation records for loops 1-3 and 1-4 in the form of " Weld History Records" for weld joints RC-2-5, RC-2-6, and RC-2-4, were reviewed in the areas of alignment and cleanliness checks. Joint RC-2-4 had not passed final radiographic inspection at the time of the inspection.
Within the areas inspected, no items of noncompliance or deviations were identified.
10.
Safety-Related Piping - Review of Quality Records (Unit 2)
The inspector reviewed the quality records described below relative to safety related piping outside the containment. The applicable code is the same as that referenced for welding in paragraph 5.b abov....
The records review included material test reports / certification record and receiving inspection records for the following piping components:
Piping Component Size System 90 E11 Mk.47W450-317 18" ERCW Spool Pc. 2CC-25C 8"
CC Spool Pc. 2RHR-13 12" RHR Spool Pc. 2CS-33 8"
RHR Spool Pc. 2CS-29 12" CS Spool Pc. 2CVC-19 4"
CVC bpool Pc. 2CVC-41 3"
CVC Within the areas inspected, no items of noncompliance or deviations were identified.
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