IR 05000327/1987005
| ML20206B940 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/03/1987 |
| From: | Hooks K, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20206B902 | List: |
| References | |
| 50-327-87-05, 50-327-87-5, 50-328-87-05, 50-328-87-5, NUDOCS 8704100091 | |
| Download: ML20206B940 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
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Report Nos.:
50-327/87-05 and 50-328/87-05 Licensee:
Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Docket Nos.:
50-327 and 50-328 License Nos. OPR-77 and DPR-79 Facility Name:
Sequoyah 1 and 2 Inspection Conducted:
January 19-23, 1987 Inspectors h
'Kenneth R. Hooks, IE, Team Leader Date Signed Contractor Consultants:
H. Jimenez, O. Mallon and F. Soto Y!.E!E7 Approved By:
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d R. Lee Spessardf Deputy Director, DI/IE Date Signed Scope:
This special, announced inspection was conducted at TVA's Sequoyah Nuclear Plant site.
The inspection was performed to review and evaluate 13 Employee Concern Task Group (ECTG) final Sequoyah Element Reports, in the categories of Construction and Materials Control, to determine accuracy and adequacy of content and conclusions.
No inspections of hardware to verify concerns or corrective acticns were performed by the NRC inspectors.
Five of the final Element Reports were evaluated to be satisfactory as written; five were evaluated as requiring revision or other written explanation to clarify or add details.
Three reports were insufficiently reviewed by the NRC inspectors to determine their adequacy which will be evaluated in a future inspection.
Results:
No violations or deviations were identified.
8704100091 870407
{DR ADOCK 05000327 PDR
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REPORT DETAILS
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1.
Persons Contacted Licensee Employees
- L. Alexander, Modification Sect. Supervisor, DNC/ Mod.
- R. Anderson, Asst. to Lead Civil Engineer, SQED
- W. Andrews, Asst. Div. Director - QA, DNQA
- N. Black, Proj. Elec. Principal Engineer, DNE/EEB
- R. Briggs, QA Specialist, NQA&EB
- L. Bryant, Engr. Supervisor, Mech. Maint.
- R. Collins, Proj. Elec. Group Leader, DNE/EEB
- M. Cooper, Comp. Licensing, SQN Licensing
- W. Harris, Jr., OES/ Engineer, DNE/0ES
- J. Howard, Construction CEB-H, WBN-ECTG
- J. Kelly, EA Engineer, SQEP M. Martin, WBN-ECTG
- L. Marvin, Site Quality Manager, DNQA
- F. Mashburn, Licensing Engineer, Comp. Licensing
- R. McCraney, WBN-ECTG B. McCreary, QC Supervisor
- L. Nobels, Plant Manager, SQN
- R. Olson, Modification Mgr., DNC/ Mod.
- B. Patterson, Maintenance Superintendent G. Portwood, WBN-ECTG
- M. Purcell, Licensing Engineer, Comp. Licensing M. Rudolphi, Manager, WBN-ECTG F. Smith, WBN-ECTG J. Swearingen, SQN
- L. Wheeler, Materials Supervisor, Site Services Other licensee employees contacted included engineers, technicians,
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security office members, and office personnel
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized during an exit interview on January 23, 1987 with those persons indicated by an asterisk in Para-graph 1 above.
The NRC inspectors described the areas inspected and
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discussed the inspection findings.
No dissenting comments were received from the licensee.
3.
Documents Reviewed In addition to the " final" Sequoyah Element Reports which had been issued at the time of the inspection, the Employee Concern Task Group (ECTG)
files for the elements, and other supporting documents, were reviewed to the extent required to support the inspection.
The final Element Reports-1-
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and the major supporting documents reviewed during this inspection are
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listed below:
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a.
C0 10603-SQN, Rev. 3 ECSP Corrective Action Tracking Documents (CATO) dated:
11/3/86, 10/27/86, 12/2/86 Drawings No.:
47W450 - 19, Rev. 19
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47W464 - 13, Rev. 21
Bill of Materials: 47BM450-11 47BM464-26 b.
CO 11103-SQN, Rev. 5 Generic Concern Task Force (GCTF) Report, Rev. 1 dated 4/25/86 c.
C0 11203-SQN, Rev. 3 Workplan No. 10512
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TVA Sequoyah Nuclear Plant (SQN) Administrative Instruction (AI)-16 " Fuse Control" CATD-11203 - SQN-01 d.
C0 11206-SQN, Rev. 1 Nuclear Safety Review Staff (NSRS) Report No. I-85-860-SQN Employee Concern Assignment Request Transmittal No. T50194 e.
CO 11301-SQN, Rev. 6 f.
CO 11305-SQN, Rev. 6
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C0 11306-SQN, Rev. 4 h.
C017101-SQN, Rev. 2 Initial Evaluation Plan dated 7/3/86 i.
C0 17105-SQN, Rev. 1
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Initial Evaluation Plan No. 17100 SQN TVA SQN Surveillance Instruction (SI)-566 "ERCW System Flow Verification Test" Engineering Change Notice (ECN) No's:
L5009, L6560, L6534-2-
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CO 19101-SQN, Rev. 2
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TVA SQN Modification and Addition Instruction (M&AI)-6
" Installation of Conduit and Junction Boxes," Rev. 6 TVA General Construction Specification G-40 National Electric Code Article 370-20 k.
C0 19203-SQN, Rev. 2 Standard Procurement Specification for Rigid Steel Conduit (zinc coated) No.21-001 dated 2/2/81
Calculation Package B45851028551
General Construction Specification G-40
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ANSI Standard C80-1-1977 " Specification for Rigid Steel Conduit, Zinc Coated" Underwriters Laboratories UL-6 " Rigid Metal Conduit" 1.
MC 40503-SQN, Rev. 2 GCTF Report No. EX-85-1 dated 5/14/86 Contract No. 72C 53-72795-2 Motor Operated Valves Contract No. 84 PJG-834280 Limitorque Valves
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TVA SQN AI-11, Attachment 9 TVA SQN AI-19 (Part IV), Rev. 12 TVA SQN M&AI-1, Rev. 13
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MC 40512, Rev. 3 General Construction Specification G-32
TVA SQN M&AI-10 TVA SQN M&AI-11 4.
Discussion and Observations
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The following observations were made on the Element Reports:
C0 10603-SQN, Rev. 3 " Bolting Material Compatibility" a.
The three concerns in this element were adequately evaluated, both in depth and detail, and the recommended corrective actions, consisting of inspecting all stainless steel flanged connections in systems
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r containing boric acid and the replacement of carbon steel bolts with
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stainless steel bolts, are also adequate.
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C0 11103-SQN, Rev. 5 " Method Used During Construction" The evaluation performed by the ECTG of the concerns, relating to snubbers and auxiliary steel, was adequate in depth, detail and scope and the corrective actions recommended in the element report are adequate.
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C0 11203-SQN, Rev. 3 " Electrical Fuse Identification" The TVA investigation of the concern was appropriate and their resolution of the concern as described in the element report is adequate.
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C0 11206-SQN, Rev. 1 " Unauthorized / Undocumented Work" The element report contains adequate depth and detail regarding procedural aspects and no further action is required in this regard.
The element report, and the NSRS report, do not identify the root l
cause of the problem, i.e., why the CI refused to sign the as-built l
drawings.
The reports show no attempts to discover whether the concern was isolated or general.
The reports do not show the magni-
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tude of the concern in terms of the number of drawings that the CI i
i refused to sign.
The position, education, training and experience of the concerned individual should be explicitly described, his reasons for refusing to sign the drawings thoroughly investigated and clarified, and the nature of the problem whether isolated or programmatic determined.
If this information is not available, it should be explicitly stated in the Element Report.
e.
C0 17101-SQN, Rev. 2 " Valves"
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The concerns regarding valve orientation, maintenance requirements such as stroking, and inaccessible hand valve have been investigated in depth by the ECTG.
Their findings show that existing maintenance and inspection practices meet the requirements for installation and maintenance of the Limitorque valve motor operators specified by the
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vendor.
No inaccessible emergency hand valve was found.
f.
C0 17105-SQN, Rev. 1 " Piping / Fittings" The NRC inspectors agree with the evaluation, conclusions and resolu-tion of the concern for the ERCW system stainless steel material replacement.
The replacement of carbon steel piping with stainless steel in the small lines and further replacements based on the periodic surveillance testing of the system flow rates is adequate.
The NRC inspectors require further details regarding the hydrotest of penetration welds.
The affected penetrations must be identified and the welds marked on the penetration design drawings.
Before the evaluation can be performed the governing design codes must be-4-
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identified, as well as jurisdictional boundaries between components
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(process pipe vs containment) and between codes.
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CO 19101-SQN, Rev. 2 " Electrical Equipment" The NRC inspectors believe that the TVA resolution of the concern as described in the Element Report is not adequate and conclude that General Construction Specification G-40, Modification and Addition Instruction M&AI-6, and Standard Drawing SD-E13.6.3-1 should be revised to specifically include galvanized steel as an acceptable material for junction boxes.
h.
C0 19203-SQN, Rev. 2 " Conduit Fittings" A review of General Construction Specification G-40 revealed that no controls have been established related to the addition of zinc coated or die cast materials within the containment building; however, TVA intends to take the following corrective actions:
Prepare a procedure that ensures an accurate update of
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inventories of light metals to be included in the calculations of hydrogen buildup inside containment.
Revise General Construction Specification G-40 to prohibit the use of die cast zinc conduit components inside primary componen.t.
Utilize TVA Specification 21.001 for all procurements of conduit and conduit fittings.
The NRC inspectors conclude that the TVA investigation of the concern was appropriate and their resolution and corrective action is adequate.
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MC 40503-SQN, Rev. 2 " Valves (Test 70)"
The element report does not seem to reflect actual practices as
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evidenced by the documents examined.
Further, identification of valves by descriptions, in lieu of unique type mark numbers devised by manufacturers, may fail to identify correctly equal valve bodies with different trims.
A more detailed explanation of TVA practices regarding valve identi-fication, for purchasing, storage, installation, welding, maintenance, piping stress analysis, system tests, plant operating instructions, and tech specs, is required before the NRC inspectors can properly
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evaluate the Element Report.
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MC 40512, Rev. 3 " Containment Vessel Plate" The NRC staff concludes that TVA's investigation and resolution of the concern was adequate.
However, the element report should document how it was determined that Support Pad No. 125 was the plate with the wrong material and not one of the other plates.
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s Detailed comments regarding the Element Reports were given to the o
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appropriate ECTG evaluators and/or ECTG Category Evaluation Group-Head (CEG-H) of the appropriate group by telephone from the Sequoyah Nuclear plant site.
5.
Conclusions A total of 11 Construction category and 2 Materials Control category final Element Reports were reviewed and evaluated in part or in whole by the NRC inspection team.
a.
The five final Element Reports listed below were evaluated as satis-factory; SER input for these reports can be prepared without addi-tional review unless final in-office review raises new questions.
C0 10603-SQN C0 11103-SQN C0 11203-SQN C0 17101-SQN CO 19203-SQN b.
The three final Element Reports listed below require further review and evaluation before a conclusion can be reached; the evaluations are continuing in the contractor's offices, and may require further on-site inspection at either the Employee Concern Task Group (ECTG)
offices at the Watts Bar Nuclear Plant or the Sequoyah Nuclear Plant.
C0 11301-SQN C0 11305-SQN C0 11306-SQN Five final Element Reports were evaluated as inadequate, and will c.
require revision or additional explanation in writing by TVA.
The reports are:
C0 11206-SQN
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C0 17105-SQN C0 19101-SQN MC 40503-SQN MC 40512-SQN j-6-l l
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