IR 05000327/1979020
| ML19289F287 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/10/1979 |
| From: | Herdt A, Macfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19289F285 | List: |
| References | |
| 50-327-79-20, 50-328-79-11, NUDOCS 7906070162 | |
| Download: ML19289F287 (8) | |
Text
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ATLANTA, GEORCIA 30303 \\,...../ Report Nos. 50-327/79-20 and 50-328/79-11 Licensee: Tennessee Valley Authority 500A Chesnut Street, Tower II Chattanooga, Tennessee 37401 Facility Name: Sequoyah Nuclear Plant, Units I and 2 Docket Nos. 50-327 and 50-328 License Nos. CPPR-72 and CPPR-73 Inspection at Sequoy h Site near Daisy, Tennessee //T
' Inspector: ,/ C. R. McFarland Date Signed Approv by: ./[ / '/"7/</br>A. R. Herdt, Section Chief, RC&ES Branch Date Signed SUMMARY Inspection on March 26-29, 1979 J</br>Areas Inspected This routine unannounced inspection involved 32 inspector-hours on site in the areas of noncompliances, 10 CFR 50.55(e) items, inspector follow-up items, and QA audits by TVA Construction Division.</br></br>"</br>Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified.</br></br>2232 281 79060701%</br>.</br></br>.</br>.</br>DETAILS 1.</br></br>Persons Contacted Licensee Employees G. G. Stack, Project Manager, Sequoyah Nuclear Project (SNP)</br>*J.</br></br>E. Wilkins, Construction Engineer</br>*D. W. Mack, Assistant Construction Engineer</br>*R. W. Farrell, Supervisor, Quality Engineering Records Unit</br>*E. C. Pendergrass, Engineer, QC Records Unit (QCRU)</br>*J. M. Munns, Supervisor, Const ruction QA Unit (CQAU)</br>*R. B. Bruce, QA Engineer, CQAU W. M. !! organ, QA Engineer, CQAU S. T. Wright, Civil Engineer, Civil Engineering Unit J. A. Thompson, Mechanical, Engineer, Mechanical Group</br>*R. W. Wright, Mechanical Engineer, Mechanical Hanger Group</br>*S. H. Mindel, Engineering Design (EN DES) QA</br>*D. L. Wall, Nuclear Licensing, EN DES Licensing</br>*M. A. McBurnett, Nuclear Engineer, Regulatory Staf f L. G. Hebert, Office of Engineering Design and Construction (0EDC) QA Auditor W. K. Anders OEDC QA Auditor Other licensee employees contacted included several construction craftsmen and office personnel.</br>* Attended exit interview.</br></br>2.</br></br>Exit Interview The inspection scope and firidings were summarized on March 29, 1979 with those persons indicated in Paragraph I above.</br></br>,</br>3.</br></br>Licensee Action on Previous Inspection Findings (0 pen) Item of noncompliance, Deficiency 327/78-27-01 and a.</br></br>328/78-21-01, Corporate audits. The inspector met the Office of Engineering Design and Construction (0EDC) QA auditors who were conducting audit number M 79-4 on March 26-28, 1979 at the SNP as a part of an audit of all TVA nuclear projects during the period March 26 through May 1, 1979.</br></br>The OEDC QA audit will review all projects relative to 10 CFR 50 Appendix B Criteria I, II and XVIII. The purpose of the audit is (1) to verify that management controls are being properly implemented, (2) to verify the adequacy of the QA program interfaces between the appropriate TVA 2232 282</br></br>.</br>.</br>-2-offices and their contractors. The Region II inspector attended the OEDC audit exit meeting on [[Exit meeting date" contains a listed "[" character as part of the property label and has therefore been classified as invalid.-no audit deficien-cies were identified.
The Region II inspector will review the OEDC QA audit report during a subsequent inspection.
4.
Unresolved Items Unresolved items were not identified during ths inspection.
5.
Licensee Identified Items (Units 1 and 2) TVA has reported a number of items to Region II as rep.rtable items in compliance with 10 CFR 50.55(e) and the inspector reviewed the items below and the supporting docun e tation, and discussed the items with . responsible staf f during the inspection.
a.
(Closed) Item 327/78-02-12 and 328/18-01-15, Lack of Procedures for Review of Certain Design Activities.
The inspector reviewed the TVA responses to Region II dated February 6, 1978, July 3, 1978, August 28, 1978 nd October 30, 1978, NCR M77-7.
The inspector reviewed the current revisions to the engineering procedures noted in the corrective action proposed in the final report These revisions provide for reviewing, identifying, documenting (including the cause of the deficiency), analyzing the repetitive deficiencies, and reporting the deficiencies to the NRC. The corrective actions have been completed and are being implemented.
b.
(Closed) Item 327/78-14-02 and 328/78-10-01, Embedments for Reactor Coolant Pump Tie Rods. The inspector reviewed the TVA responses to Region II dated June 8, 1978, November 17, 1978, and February 16, 1979, NCR SQN-002.
The inspector reviewed the documentation and drawings related to the changes to the subject embedments due to new concrete shear loads due to new LOCA analysis conditions. The embedment design has been modified to accomodate the increased loads.
The Westinghouse load analysis has been accepted by TVA. The inspector observed the work in progress on Unit I and discussed the subject with the cognizant civil engineer.
c.
(Closed) Item 327/78-14-03 and 328/78-10-02, Pressurizer Safety Relief Line. The inspector reviewed the TVA responses to Region Il dated June 1, 1978, August 8, 1978, and December 12, 1978 and February 22, 1979, NCR CSQ 78-2.
The inspector reviewed the documentation and drawings related to the changes to the pressurizer safety relief line due to reanalysis of the blowdown using a computer program capable of modeling the valve water seal 2232 283
. . -3-at defined temperatures. The inspector observed the work in progress on Unit 2 and discussed the subject with the cognizant mechanical engineer.
d.
(Closed) Item 327/79-12-02 and 328/79-07-02, Signal Cable Used Without Proper Environmental Qualification n-ta.
The inspector reviewed the TVA responses to Region II dated January 4, 1979, and Janua ry 23, 1979, NCR EEB 78-4.
The inspector reviewed the docu-mentation verifying the ccmpletion of the corrective action.
The original cable has been pulled from both Units 1 and 2 and fully qualified cable has been installed.
The original cable had been contracted for before the current environmental conditions were developed in 1977.
e.
(Closed) Item 328/79-07-12, Deficient Concrete in Unit 2 Crane Wall.
The inspector reviewed the TVA responses to Region II dated August 18, 1978, January 4, 1979, and February 5, 1979, NCR 1079.
The inspector reviewed the documentation verifying the adequacy of the concrete and discussed the subject with the cognizant civil engineer The inspector observed the thin steel plates installed to protect the concrete from possible deterioration of both the inside and outside surfaces of the crane wall at the area of concern.
f.
(Closed) Item 327/78-02-08 and 328/78-01-09, RHR Pump Natural Frequency.
The inspector reviewed the TVA responses to Region II dated October 14, 1977, January 26, 1978, March 10, 1978, August 18, 1978, February 16, 1979, and March 27, 1979, NCR 69D.
The inspector reviewed documentation referenced in the final report relative to the TVA reanalysis of the RHR system piping loads, ;he Westinghouse confirmation that the new nozzle loads are accep. ' ele, and the changes to the piping supports and a sway strut as required by the reanalysis.
g.
(Closed) Item 327/79-12-01 Upper Head Injection Rate. The Region II staff has reviewed the TVA final report to Region II dated December 28, 1978, NCR MEB 78-4.
The corrective action has been verified for Unit 1 as reported in IE Report No. 50-327/79-19.
The work for Unit 2 was not inspected (item 328/79-07-01).
h.
(Open) Item 327/79-20-01 and 328/79-11-01, Accumulator Level Transmitter Lines.
On March 1,1979, TVA informed Region II of a potentially reportable item relative to the subject, NCR SWP 79-S-4.
A section of the instrument line does not meet ASME requirements and is not presently seismically qualified.
A final report dated March 30, 1979 has been received subsequent to the inspection.
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. . -4-i.
(0 pen) Item 327/79-20-02 and 328/79-11-02, Overheating of Bearings Motor Driven Aux Feedwater Pumps. On March 7, 1979 TVA informed Region II of a potentially reportable item relative to the subject NCR MEB 79-11.
Thrust bearings on the subject, Ingersoll-Rand pumps are overheating during testing.
j.
(0 pen) Item 327/79-20-03 and 328/79-11-03, Pipe Seismic Analysis; Velan Valve Weights. On March 20, 1979, TVA informed Region 11 of a potentially reportable item relative to the subject, NCR HEB 79-13.
Westinghouse has informed TVA that the weights for certain swing check valves were less than the actual weights of the valves.
This is a generic problem related to several other plants with Westinghouse reactor systems.
k.
(0 pen) Item 327/79-20-04 and 328/79-11-04, Stress Analysis Inadequate for ERCW Piping System.
On March 20, 1979, TVA informed Region II of c potentially reportable item relative to the subject, NCR CEB-79-11.
TVA has not analyzed the safety related sections of the Essential Raw Cooling Water (ERCW) piping system for temperatures from minimum through ambient to the maximum specified temperature as required by ASME III NC 3652.3.
1.
(0 pen) Item 327/79-20-05 and 328/79-11-05, Containment Penetrations Seismic Reanalysis.
On March 21, 1979, TVA informed Region II of a potentially reportable itec. relative to the subject, NCR CEB 79-14.
Certain Residual Heat Removal and Containment Spray penetrations of the containment vessel need to have the stresses reanalyzed for certain conditions.
(0 pen) Item 327/79-20-06 and 327/79-11-06, Control Loop Bistable m.
Failures.
Region II has received the first interim report dat'd March 14, 1979, NCR MEB 79-10.
A deficiency exists relative to the failure of bistables associated with certain control loops in the Auxiliary Control Room.
The bistables fail in an undesirable position on loss of control power.
n.
(Open) Item 327/79-20-07 and 328/79-11-07, Anchor Tensile Capacities.
Region II has received the TVA first interim report dated March 14, 1979, NCR CEB 79-5.
A deficiency relative to progressive cracking in the heat affected zone of welded stud anchors in flexible plate connections has been identified.
No items of noncompliance or desiations were identified.
o.
(Open) Item 327/79-20-08 and 328/79-11-08, Essential Raw Cooling Water (ERCW) Drain Valves.
Region 11 has reviewed the TVA final 2232 285
. o-5-report dated March 23, 1979, NCR SWP-79-S-3.
A deficiency rela-tive to installing class G instead of class C drain valves in the ERCW side of the diesel generator heat exchangers (one valve per each of eight heat exchangers) has been identified.
Seismically qualified, class C, valves will be installed.
6.
'aspector Followup Items (IFI) a.
(Closed) IFI 327/78-27-02 and 328/78-21-02, Control of Documents.
The inspector reviewed the CQAU Supervisor's FSAR and observed that it is being kept current.
Revision 60 dated March 2, 1979 has been received.
Chapter 17 is updated through revision 59, dated January 26, 1979. Revision 60 contained no changes to Chapter 17.
b.
(Closed) IFI 327/79-12-13 and 328/79-07-13, 10 CFR 50.55(e) Status Report Emphasis. The QCRU status report "NRC Inspections, SNP Response Status" and the Regulatory Staff report "Sequoyah Nonconformance Reports (NCRS)" have been modified to include NCRS telepnoned to Region Il and to note responsibilities within TVA that are required before the corrective action is complete.
7.
Independent Inspection - Constructis, QA Audits (Units 1 and 2) The schedule of construction QA audits for January through June, 1979 was reviewed with the supervisor of the Construction QA Unit. The inspector reviewed the documentation of the audits noted below as representative of the current work.
Audit plana adequately describe the scope, list the controlling documents, and list the previous audits for items requiring followup of corrective actions taken due to the findings of previous audits. The audit reports summarize the findings and provide details of the deficiencies identified.
The deficiency sheet for each deficiency identifies the requirements, the deficient items (documents and/or hardware), the recommended corrective action (s) (with an estimated completion date,) the corrective action proposed and implemented, and the verification of the corrective action.
The audit reports document the preaudit and past audit conference attendence.
The reports are distributed to managers and supervisors responsible for the construction and QA work onsite and in Knoxville, Audit Audit No.
Subject Dates G-79-01 Reactor Coolant System 1/2-18/79
Including Supports and Restraints (Unit 1) 2232 286
. . -6-Audit Audit No.
Subject Dates G-79-02 NRC-0IE Responses, NCR Processing 1/2-23/79 and Drawing Control C-79-02 Steel Fabrication and Erectioc 2/26-3/15/79 I-79-02 Installation and Documentation 1/4-26/79 Associated with Unit 1 Reactor Coolant System Instrumentation I-79-03 Installation of Instrumentation 1/31-2/15/79 Cable and Conduit The audit reports verify the adequacy of the construction QA audit program.
Deficiencies are routinely identified and, tracked until closed during a subsequent audit.
A deficiency identified in G 79-01 initiated a 10 CFR 50.55(e) reportable condition reported in Paragraph 5.a as item 327/78-02-12 and 328/78-01-15.
Some audit reports (I-79-02, I-79-03 and G 79-02) :ontained auditors committments to followup on pending items and concerns that were not labeled "significant" (relative to 10 CFR 50-55(e) reporting,) which were not tracked as " deficiencies" The CQAU supervisor is aware of the need to initiate a pending items list.
This will be identified as inspector followup item 327/79-20-09 and 328/79-11-09 " Tracking QA Audit Pending Items." QA staff activities are now being conducted per the procedures and instructions included in the "QA Staff Manual", November 1,1978, and the "QA Program Manual", February 9,1979. The QA Program Manual contains a matrix of the QA procedures used for the current TVA nuclear projects including Sequoyah.
. An audit of audit responses is currently identified as G-79-0 and is scheduled for the last week in April and the first week in May, 1979.
No items of noncompliance or deviations were identified.
8.
10 CFR Part 21 Inspection (Units 1 and 2) The site facilities were inspected to determine if the posting re-quirements specified in 10 CFR 21.6 had been implemented. The licensee had posted notices prepared per 10 CFR 21.6(b) in at least three conspicuous locations in the construction office buildings.
The 2232 287
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-7-Posting requirements or 10 CFR 21.6 had been implemented at Sequoyah Nuclear Plant.
No items of noncompliance or deviations were identified.
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