IR 05000327/1979036
| ML19249D463 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah, Midland  |
| Issue date: | 08/02/1979 |
| From: | Cantrell F, Gouge M, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19249D461 | List: |
| References | |
| 50-327-79-36, 50-328-79-21, NUDOCS 7909240695 | |
| Download: ML19249D463 (9) | |
Text
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Report Nos. 50-327/79-36 and 50-328/79-21 Licensee:
Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Faci.'.ity 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 Site near Daisy, Tennessee and TVA Corporate Offices in Knoxville, Tennessee Inspectors:
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f C. R. McFarland, Date Signed
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M. J. Gouge /
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Date Signed Approved by:
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F. S. Cantrell, Sectioy Chief, RCES Branch Date' Signed SUMMARY Inspection on July 10-13, 1979.
Areas Inspected This routine, unannounced inspection involved 52 inspector-hours on-site by two NRC inspectors in the areas of noncompliance, 10CFR 50.55(e) items, inspector follow-up items, and IEB's.
In addition, the principal inspector responsibility was transferred for Unit 2.
Results Of the four areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- G. G. Stack, Project Manager, Sequoyah Nuclear Project (SNP)
- D. W. Mack, Assistant Construction Engineer
- R. W. Farrell, Supervisor, Quality Engineering Records Unit
- R. W. Olson, Assistant Construction Engineer
- E. C. Pendergarass, Engineer, QC Records Unit (QCRU)
- J. M. Munns, Supervisor, Construction QA Unit (CQAU)
R. B. Bruce, QA Engineer, CQAU L. W. Jones, Supervisor, Welding Inspection
- M. A. McBurnett, Nuclear Engineer, Regulatory Staff S. Duhan, Supervisor Quality Compliance, Engineering Design (ENDES)
J. F. Cox, Nuclear Licensing (NL), ENDES W. I. Dothard, NL, ENDES D. L. Wall, NL, ENDES Other licensee employees contacted included several construction craftsmen and engineering office personnel.
Resident Inspector
- W.
T. Cottle
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on July 13, 1979 with those persons indicated in Paragraph 1 above.
Mr. McFarland reviewed the highlights of the Region II managerent meeting with TVA in Knoxville on July 10, 1979 as applicable to the construction work at the Sequoyah project, introduced Mr. Cottle as the resident inspector for operations and the principal inspector for Unit 1, and introduced Mr. Gouge as the new prin-cipal inspector for construction work on Unit 2.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Deficiency 50-327/78-27-01 and 50-328/78-21-01, Corporate audit documentation.
The inspectors reviewed the OEDC Audit report 79-4 of the organiza-tion, QA progra.a, and the audit program of the Division of Construc-tion for all projects (except Browns Ferry, the only project not under construction). The audit was conducted from March 26 through May 1, 1979 (reference Region II reports 50-327/79-20 and 50-328/79-11). The audit identified two deficiencies relative to training records and
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procedural inconsistancies, neither finding related to the Sequoyah proj ect. The auditors' evaluation was that the effectiveness of the elements of the QA program audited are adequate with the exception of the above two deficiencies.
b.
(Closed) Infraction 50-328/79-04-01, Failure to follow procedure for handling and protection of stainless steel piping.
The inspector reviewed the TVA response to Region II dated April 9, 1979 and the corrective action program as reported in Region II report 50-328/78-16. On this inspection the inspector reviewed the documen-tation of the unscheduled QC inspections of May 9, 16 and 23 and of June 2 of the storage and handling of core spray and residual heat removal piping for Unit 2.
The inspector reviewed the projects standard operating procedure (SOP)
numbered 318 entitled " Resolving and Documenting Items Identified in NRC Exit Meetings or Inspection Reports," revision 0 dated June 11, 1979.
S0P 318 provides for routine inspections of the corrective actions taken by TVA in response to noncompliances and other deficien-cies cited by NRC. The inspections are expected to utilize existing inspection procedures, instructions and records, but are expected to be performed while the corrective action is being implementd for each noncompliance or other deficiency.
4.
Unresolved Items No new unresolved items were identified during this inspection.
5.
Licensee Identified Items (Units 1 and 2)
TVA has reported a number of items to Region II as reportable items in compliance with 10CFR 50.55(e) and the inspectors reviewed the items below and the supporting documentation, and discussed the items with responsible staff during the inspection.
a.
(Closed) Item 50-328/79-0/-03, Omitted lateral restraints in chemical volume control system piping.
The inspectors reviewed the TVA final report dated January 12, 1979, NCR CEB 78-2 and engineering change notice (ECN) 2063 which have been closed by TVA. The drawing revisions made for ECN 2063 apply to work on Units 1 and 2.
Work related to Unit I was reported in Region II reports 50-327/79-29 and 50-328/79-16.
b.
(Closed) Item 50-328/79-07-04, Heating, Ventilating and air con-ditioning penetrations in containment design.
The inspectors reviewed the TVA final report dated February 23, 1979,.
NCR CEB 78-3 and ECN 2196 which have been closed by TVA. The drawing
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-3-revisions made for ECN 2196 apply to work on Units 1 and 2.
Work related to Unit I was reported in Region II report 50-327/79-29 and 50-328/79-16.
c.
(Closed) Item 50-327/79-12-06 and 50-328/79-07-06, Seismic quali-fication of heating and ventilating system ductwork.
The inspectors reviewed the TVA final report dated January 29, 1979, NCR SWP 78-S-3, and ECN 2166 which has been closed by TVA. The drawing revisions made for ECN 2166 apply to work on Units 1 and 2.
d.
(Closed) Item 50-327/79-20-08 and 50-328/79-11-08, Essential raw cooling water (ERCW) drain valves.
The inspectors reviewed the TVA final report dated March 23, 1979, NCR SWP 79-S-3, and ECN 2223 which has been closed by TVA. The valves have been replaced by qualified valves as verified by the completed work plan.
e.
(Closed) Item 50-327/79-19-01, Error in small line supports.
The inspectors reviewed the TVA final report dated March 7, 1979, NCR SWP 79-S-1, and ECN 2192 which has been closed by TVA. The drawing revisions made for ECN 2192 apply to Unit 1.
ECN 2305 applies to Unit 2 and has not been closed by TVA (50-328/79-16-05).
f.
(0 pen) Item 50-327/79-36-01 and 50-327/79-21-01:
Incorrect Weight of Velan Swing Check Valves.
On May 22, 1979, TVA informed Region II of this reportable item iden-tified as NCR MEB 79-20.
TVA stated in an interim report dated June 22, 1979 that a final response for this item will be included in the final response to IEB 79-04 and will be submitted prior to fuel load at Sequoyah U it 1.
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(0 pen) Item 50-327/79-36-02 and 50-328/79-21-02: Reactor Vessel Insulation Supports.
On June 4, 1979, TVA inform.:1 Region II of this reportable item identified as NCR CEB 79-20.
TVA stated in an interim report dated July 3,1979 that a subsequent report will be submitted by August 31, 1979.
h.
(0 pen) Item 50-327/79-36-03 and 50-326/79-21-03: ERCW Valve Positioning.
On Jp. e 7,1979, TVA infonned Region II of this reportable item ident fied as NCR MEB 79-22. TVA submitted a final report on this item dated July 3, 1979. The final report stated the corrective action required would be accomplished prior to initial criticality of Sequoyah Unit.
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(0 pen) Item 50-327/79-36-04 and 50-328/79-21-04:
Class IE Junction Boxes in Containment Not Environmentally Qualified.
On June 15, 1979, TVA informed Region II of this reportable item identified as NCR EEB 79-7.
TVA submitted a final report on this item dated July 12, 1979. This item is presently under review by Region II.
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(0 pen) Item 50-327/79-36-05 and 50-328/79-21-05: Deficiencies in Penn Ventilation Company QA Program.
On June 15, 1979, TVA informed Region II of this reportable item identified as NCR QEB 79-2.
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(0 pen) Item 50-327/79-36-06 and 50-328/79-21-06:
Pipe Restraint Structural Strand Temperature.
On May 17, 1979, TVA informed Region II of this reportable item iden-tified as NCR MEB 79-18.
TVA submitted a final report on this item dated June 18, 1979, stating corrective action will be accomplished prior to fuel loading for each respective plant unit.
1.
(Open) Item 50-327/79-36-07 and 50-328/79-21-07:
Pipe Support Deflection Summation.
On May 22, 1979, TVA informed Region II of this reportable item identified as NCR SWP-79-S-7.
TVA stated in an interim report dated June 21, 1979 that a subsequent report will be submitted by Septe:nber 10, 1979.
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(0 pen) Item 50-327/79-36-08 and 50-328/79-21-08: Emergency Diesel Generator Lubrication Problem.
On June 21, 1979, TVA informed Region II of this reportable item identified as NCR MEB 19-26. A 30-day written report is due to Region II by July 20, 1979.
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(0 pen) Item 50-327/79-36-09 and 50-328/79-21-09:
Steam Generator Reference Column Water Level Error.
On June 29, 1979, TVA informed Region II of this reportable item identified as NCR MEB 79-32. Westinghouse is reporting this generic item per 10CFR21. A 30-day written report is due to Region II by July 30, 1979.
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(0 pen) Item 50-327/79-36-10 and 50-328/79-21-10:
Seal Water Injection Flow Elements Orifice Site.
On June 7, 1979, TVA informed Region II of this reportable item identified as NCR MEB 79-21. TVA submitted a final report dated July 5, 1979 which stated corrective actions would be accomplished prior to the fuel load of each plant unit.
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(0 pen) Item 50-327/79-36-11 and 50-328/79-21-11: Design Deficiency of Vendor Supplied Discharge Accumulator.
On June 12, 1979, TVA informed Region II of this reportable item identified as NCR CEB 79-22.
A final report was submitted on this item dated July 9, 1979 and stated corrective action will be accomplished prior to fuel loading.
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(0 pen) Item 50-327/79-36-12:
Pressurizer Relief Piping Supports.
On May 29, 1979, TVA informed Region II of this reportable item identified as NCR SWP-79-S-8.
A final report was submitted on this item dated June 22, 1979 and stated corrective actions will be accomplished prior to fuel loading for Unit 1.
This item applies to Unit 1 only, (0 pen) Item 50-327/79-36-13: Failed Barton Steam Generator Level r.
Transmitters. On June 13, 1979, TVA informed Region II of this reportable item identified as NCR MEB 79-24. A 30-day written report is due July 13, 1979. This item applies to Unit 1 only, s.
(0 pen) Item 50-327/79-36-14:
Corosion of Terminal Blocks in Junction Boxes:
On June 27, 1979, TVA informed Region II of this reportable item identified as NCR 9P. A 30-day written report is due July 27, 1979.
This item was reported for Unit 1.
The licensee is evaulating its applicability to Unit 2.
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(0 pen) Item 50-327/79-36-15: Flexible Bellows Penetration Misalignment.
On May 25, 1979, TVA informed Region II of this reportable item identified as NCR 1666. TVA submitted an interim report dated June 25, 1979 to Region II, and stated a subsequent report would be submitted by September 11, 1979.
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(open) Item 50-327/79-36-16: Valve Position Indicator Transformer Failure.
This item was reported February 16, 1978 to Region II as a reportable item for Unit 2 only. TVA has submitted written reports dated March 17, 1978, June 16, 1978, July 5, 1978, and June 20, 1979.
Review by Region II indicates a potential circuit design problem and this item has been forwarded to IE:HQ for review. This item is opened for Unit 1 due to the potential design problem currently under review.
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6.
Inspection Followup Items (IFI) (Units 1 and 2)
a.
(Closed) IFI 50-327/78-27-04 and 50-328/78-21-04, Open 1975 and 1976 OEDC audits.
The inspectors discussed the subject with OEDC supervisor of quality ccmpliance and reviewed the June 29, 1979 "0EDC Active QA Audit Status Report". All 1975 and 1976 audit findings are closed. The status of the open items was reviewed, the oldest items are identified as M77-10-01 and 02.
The status of open findings and the number of open items are routinely reported to management. The number of outstanding items is currently about half of the number at the time of the Region II audit of OEDC management audits (50 items as of May, 1979 versus 98 items as of September, 1978.)
b.
(0 pen) IFI 50-327/78-27-03 and 50-328/78-21-03, Training The inspectors discussed the subject with the OEDC supervisor of quality compliance.
The work plan outline and schedule of training activities were reviewed. The open findings of OEDC audit 78-05 relative to QA training and indoctorination is to be reviewed in a followup audit scheduled for July 1979.
7.
Independent Inspection The inspectors conducted a walk through inspection of Units 1 and 2 Containment Buildings and the Auxiliary Building.
Welding of safety injection system piping in the Unit 2 Containment Building was the major safety related construction activity in progress.
The inspectors observed welding of a 2 inch, class A pipe weld in the safety injection system (weld #01988). The applicable weld procedure was GT-88-01, Revision 5.
The qualification of the welder to this procedure was verified. The welding was conducted in accordance with the above weld procedure by qualified welding personnel. The certified material test report for the ER308 Jiller material heat number 462317 being used in the weld was reviewed to determine conformance to the chemical requirements of SFA5.9 of Section II, Part C of the ASME Code. The certified material test report met the chemical requirements specified above.
No items of noncompliance or deviations were identified.
8.
IE Bulletins, Circulars and Information Notices (Units 1 and 2)
Discussions conducted with management personnel at the site indicated that IEB's, IEC's, and IN's are being reviewed by both site and corporate design personnel for site applicability and the need for a response. The following
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-7-h IEB's were forwarded to the site for information only.
No action was required by the licensee.
IEB 78-14 Deterioration of Buna-N Components in ASCO Solenoids
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IEB 79-1, IA Ensironmental Qualification of Class IE Equipment
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IEB 79-5, SA Nuc.' ear Incident at Three Mile Island
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IEB 79-6, 6A, (
Review of Operational Errers and System Misalignment
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Identified During the TMI Incident IEB 79-8 Events Relevant to BWR Reactors Identified During Three Mile
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Island Incident IEB 79-10 Requalification Training Program Statistics
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IEB 79-12 Short Period Scrams at BWR Facilities
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The bulletins listed above are closed.
The following bulletins require a response from the licensee. The status of these bulletins is indicated below:
(0 pen) IEB 78-12, 12A, 12B:
Atypical Weld Material in Reactor
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Pressure Vessel Welds.
The licensee response dated May 29, 1979 stated that the Westinghouse generic report is scheduled to be submitted to the NRC in October, 1979. The licensee will submit a supplemental response verifying that this generic report addresses IEB 78-12 for the Sequoyah Nuclear Plant within 30 days after the generic report is submitted.
(0 pen) IEB 79-02 Revision 1:
Pipe Support Base Plate Designs Using
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Concrete Expansion Anchor Bolts.
The licensee submitted a response to this bulletin dated July 5, 1979.
This response is currently under review by Region II.
(Closed) IEB 79-03:
Longitudinal Weld Defects in ASME SA-312 Type 304
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Stainless Steel Pipe Spools Manufactured by Youngstown Welding Company.
The licensee's final response dated June 1, 1979 stated that no ASME SA stainless steel piping manufactured by Youngstown Welding and Engineering Company had been received at Sequoyah Nuclear Plant for use in safety related systems. This item is closed.
(Closed) IEB 79-09: Failures of GE Type AK-2 Circuit Breakers in
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Safety Related Systems.
The licensee stated in the response u tad June 20, 1979 that no GE Type AK-2 circuit breakers are in use 3r planned for use in NSSS safety related systems. The GE Type AK-2 breakers are used in some
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