ML19246C308
| ML19246C308 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/24/1979 |
| From: | Herdt A, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19246C302 | List: |
| References | |
| 50-327-79-29, NUDOCS 7907240129 | |
| Download: ML19246C308 (2) | |
See also: IR 05000327/1979029
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETT A sT., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303
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Report Nos. 50-327/79-29 and 50-328/79-16
Licensee: Tennessee Valley Authority
500A Chestnut Street Tower II
Chattanooga, Tennessee 37401
Facilty Name:
Sequoyah Nuclear Plant, Units 1 and 2
Eocket Nos. 50-327 and 50-328
License Nos.
CPPR-72 and CPPR-73
Inspection at S
oa Site near Daisy, Tennessee
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Date Signed
Approved by:
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A. R. Herdt, Section Chief, RCES Branch
Dat'e Signed
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SUMMARY
Inspection on May 8-11, 1979
Areas Inspected
This routine unannounced inspection involved 26 inspector hours on site in the
areas of noncompliance, 10CFR 50.55(e) items, inspector follow-up items, IEB 79-02, and containment penetrations.
Results
Of the five ercas inspected, no apparent items of noncomplianc3 or deviations
were identified.
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DETAILS
1.
Persons Contacted
Licensee Employees
- G. G. Stack, Project Manager, Sequoyah Nuclear Porject (SNP)
- J. E. Wilkins, Construction Engineer
- D. W. Mack, Assistant Construction Engineer
- R. W. Farrell, Supervisor, Quality Engineering Records Unit
- R. W. Olson, Assistant Construction Engineer
- E. C. Pendergrass, Engineer, QC Records Unit (QCRU)
- J. M. Munns, Supervisor, Construction QA Unit (CQAU)
R. B. Bruce, QA Engineer, CQAU
L. W. Jones, Supervisor, Mechanical Inspection
J. A. Thompson, Mechanical Engineer
R. M. Callegari, Mechanical Engineer
S. N. Scott, Mechanical Aide
- M. A. McBurnett, Nuclear Engineer, Regula'mry Staf f
K. G. Gallaway, Welding Inspector
J. M. Boone, Mechanical Inspector
- W. E. Andrews , Power Production, QA Sta.'
'e rvisor
- G. W. Killian, Office of Power, QA Coordtaatot
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Other licensee employees contacted included several construction
craftsmen and engineering office personnel.
- Attended exit interview
2.
Exit interview
The inspection scope and findings were summarized on May 11,1979 with
those persons indicated in Paragraph I above.
3.
Licensee Action on Previcus Iqspection Findings
(Open) Item of Noncomplaince, Infraction 50-328/79-04-01, Failure to
Follow procedure for Handling and Protection of Stainless Steel Piping.
The inspector reviewed the TVA April 5, 1979 response to Region II and
the corrective action stepc taken by TVA to correct the problem and to
avoid further noncompliance. The inspector reviewed QC inspection
records of the reactor building, but there has been no documented
inspection of the areas of concern as stated in the Notice of Violation.
TVA will conduct two special inspections of the areas of concern in the
Special inspections will be initiated routinely for
future noncompliances.
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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 items in
complianca with 10CFR 50.55(e) and the inspector revewied the items below
and the supporting documentation, and discussed the items with responsible
staff during the inspection.
6.
(Closed) Item 50-327/79-12-03 Omitted Lateral Restraints on the
Chemical Volume Control System (CVCS) Piping. The inspector
reviewed TVA January 12, 1979 response to Region II NCR CEB78-2, the
engineering change notice (ECN) Number 20.63 and representative
drawings. The inspector observed the completed work in Unit I
related to Chemical Volume Control Hangers (CVCH) 551, 557, 676,
627, 628 and 629 as representative work.
Work related to Unit 2 was
not inspected.
b.
(Closed) Item 50-327/79-12-04, Heating, Ventilation and Air-
Conditioning (HVAC) Penetration in Containment Design. The
inspector reviewed the TVA responses to Region II dated January 12,
1979 and February 23, 1979, NCR CE3 78-03, the documentation
relative to the penetration loads in the design specification, ECN
2196 and representative to relived overstressed condiitions. The
inspector observed the completed work on Unit I related to IIVAC
supports 319, 320, 321, 323, and 324 ( 3 vacuum breakers) as
representative work. Work related to Unit 2 was not inspected.
c.
(Closed) Item 50-327/79-12-08 and 50-328/79-07-08 Piping Embedded in
Structural Concrete.
The inspector reviewed the TVA responses to
Region II dated February 8,1979 and March 21, 1979, NCR CEB 79-01.
The inspector reviewed TVA documentation of the subject and an
analysis of each of the defic .ncies noted in NCR CEB 79-01 and the
results indicate that the integrity of the structures and the piping
systems were not degraded by these violations. Therefore, had the
deficiency gone uncorrected, the safety of operation of the plant
would not have been adversely affected. The inspector also reviewed
documentation of the revision to the general civil design criteria
for the S quoyah Nuclear Plant (SNP), SQN-DC-V-1.1 RG, that requires
"a revir
of the conduits and pipes to be embedded in concrete to
.aat the requirements of section 703 of ACI 318-63 are met
ensure
d.
(0 pen) Items 50-327/79-29-01 and 50-328/79-16-01, Vibration in RHR
Piping.
Region II has received two interim reports in the subject
NCR CEB 79-04, dated March 9, 1979 and May 8, 1979. The next report
is expected to be submitted June 8, 1979.
Pipe vibration problems
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have been encountered on Unit 1 RHR piping during certain modes of
operation. Supports have been added. Retests have been conducted.
Further corrective action is being investigated.
This item was not
inspected.
(0 pen) Item 50-327/79-29-02 and 50-328/79-16-02, Fire Load not
e.
considered iu the Fire Hazard Analysis.
Region II has received the
TVA final report on the subject, NCR MEB 79-16, dated May 4, 1979.
A vapor barrier mode of Pittcote 300 material is used with a 4 foot,
4 inch high belt of foam glass insulation around the inside of the
steel conta:.nment vessel at elevation 679.
The Pitteote 300 material
is combustitle and constitutes a fire load that has not been consi-
dered in the SNP Fire Hazard Analysis.
Pittcote 300 was reonved
from all specification where required to meet the requirements, but
this particular specification was over looked. This item was not
inspected,
f.
(0 pen) Item 50-327/79-29-03 and 50-328/79-16-03, Installation of
Improper Coils in AFW and EGTS Control Circuits.
Region II has
received the TVA final report on the subject, NCR 7P, dated May 1,
1979. During preoperational testing and routine maintenance, four
instances were found where improper coils ware installed in control
circuits for the Auxiliary Feedwater (AFW) and emergency Gas Treatment
(EGTS) Systems.
In the four instances cited above, direct current
(dc) circuits and ac coils were installed in de circuits. When the
affected circuits with improper coils were energized, the coils
failed and disabled those control circuits a concerted effort is
being made to identify other possible similiar deficiencies as part
of the preoperational program.
This item was not inspected.
g.
(Open) Item 50-327/79-29-04 and 50-328/79-16-04, "- tainment Piping
Support Design Basis. On May 11, 1979 TVA infor
'gion II of a
l ative to the subjt
.LR CEB 79-19.
potentially reportable item re
TVA has found that the design basis accident (DBA) movement of the
steel containment was not properly accounted for in the design of
piping supports inside containment. A written report is to be
submitted to Region II by June 10, 1979.
This item was not
inspected.
h.
(Closed) Item 50-327/79-05-01, Signal Cable Used Without Proper
Environmental Qualification Data.
This item is the same as
50-327/79-12-02 (TVA NCR EEB 78-4) which was closed in report
50-327/79-20. The original cable has been pulled and fully
qualified czble has been installed.
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(0 pen) Item 50-328/79-16-05, Error in Design of Small Line Supports.
Region II has received the TVA final repor'. ot. .Ls subject, NCR
SWP-79-S-1, dated March 7, 1979.
Movement of tne steel containment
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vessel (SCV) was not accounted for in the design of supports for
several small lines that penetrate the shield building and the SCV.
This NCR was reported as item 50-327/79-19-01 for Unit 1.
This item
was not inspected for Unit 2.
6.
Inspecter I'ollow-up Items (IFI)
(Closed) IFI 327/79-20-09 and 328/79-11-09, Tracking QA audit Pending
Items. The inspector reviewed the Construcd on QA Units "Pending List QA
Activities". The list has been developed for ou6 standing items that are
of concern to the CQAV inspector and require follow-up during subsequent
audits.
The 1 sit is routinely used for audits scheduled each quarter.
7.
Independent Inspection - Containment Penetrations (Units 1 and 2)
The inspector reviewed the following items for a general review of the
subject:
"Containemt Penetration Schedules Unit 1 and 2", TVA drawing
a.
47B333-2G8 lists and locates all penetrations.
b.
" Structural Steel Containment Vessel Pentration Scehdule TVA drawing
48N 406 provides general details of six types of penetrations.
Seventeen spares are listed.
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" Penetrations" Chicago Bridge & Iron Company drawing numbers 30 and
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31.
d.
FSAR Sections 6.2 " Con
inment Systems", and 3.8 " Penetration
Analysis".
6.2.1.1. Erimary Containment System Design and 6.2.1.2
" Secondary Containment System Design".
" Nondestructive Examination NDE) Requirements" by the Division of
e.
Engineerine Design (ENDES) Lists by ce;mponent and penetration number
information relative to weld location, applicable, code, material,
joint type, preheat, applicable NDE procedure numbers (specifications
and acceptance standards), weld procedure numbers, remarks relative
to alternate weld procedures and bracket information.
f.
" General Construction Specification" numbered G-19M, contains process
specifications for welding, heat treatment, NDE, and allied field
fabrication operations related to welding (such as pending, brazing,
stud welding, fit up and visual and dimensional examination of weld
joints). A series of Construction Procedures, W-1 through W-7,
written to further define the work required by the process specifi-
cations W-3 " Weld Procedure Assignment and Welding Surveillance"
further defines weld processes 4: used for penetrations.
g.
Construction QA procedure (QAP) written relative to all plant proce-
dures.
Inspection Instructions (II) provide the details of inspecting
for each of the QAP's, the NDE processes, and the unusual requirements
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of the various components and the craft procedures.
The structural
inspection of containment penetrations are related to the fit-up of
the welds and the welding process.
h.
The following Construction QA Audits related to containment penetra-
tions were reviewed as typical of the audits to date:
SN-76-02 Welding Ac'.ivities Class ABC & D Piping
SN-M-76-10 Installation of Mechanical Containment Penetrations
SN-E-76-05 Installation of Electrical Penetrations
SN-M-77-09 Mechanical Penetrations
SN-78-01 Electrical Penetrations, Storage, and Insta11atien
SN-79-02 Electrical Penetrations Unit 2
No items of noncompliance were identified.
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8.
IE Bulletin 79-02 Pipe Support Base Plate Desioner Usino
Expansion Anchor Bolts (Units 1 and 2)
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The inspector reviewed the following Inspection Instructions that are
related to IE Bulletin 79-02:
II 66 Inspection of Supports
II 93 Testing of Expansion Anchors Set In Hardened Concrete
II 66 Incorprates the Inspection Instruction previuosly contained in II 1
Inspection of Bolted Connections, II 36 Orientation and Alignment, and II
38 Inspection of Site Fabricated Assemblies.
NCR CEB 79-5 " Tensile '<2chor Capacities Lower than assumed in design
allowables also related to IEB 79-02.
The final interim report, dated
March 14, 1979, on NCR CEB 79-5 has been received by Region II.
No items of noncompliance were identified.
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