IR 05000328/1981002
| ML20003E327 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/19/1981 |
| From: | Cantrell F, Wright R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20003E325 | List: |
| References | |
| 50-328-81-02, 50-328-81-2, NUDOCS 8104020894 | |
| Download: ML20003E327 (8) | |
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UNITED STATES o
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NUCLEAR REGULATORY COMMISSION REGION 11 g"
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101 MARIETTA sT., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303
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Report No. 50-328/81-02 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Sequoyah, Unit 2 Docket No. 50-328 License No. CPPR-73 Inspection at: Sequoyah Nuclear Plant near Chattanooga, Tennessee Inspector:
N bll-4.!/9!0 /
R. W. Wright (
Date Signed Approved by:
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F. S. Cantrell, Sect 14 ef, RC&ES BRANCH Date ' Signed Inspection on January 13-16, 1981
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Areas Inspected i
This routine, unannounced inspection involved 26 inspector-hours on site in the area of licensee identified items.
Results
For the area 1:1spected, no items of violation or deviations were identified.
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DETAILS 1.
Persons Contacted
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Licensee Employees
- G. G. Stack. Construction Project Manager
- T. B. Nort'him, Jr., Construction Engineer
- 0. W. Mack, Assistant Construction Engineer
- J. M. Munns, QA Unit Supervisor, Construction
- D. O. McCloud, QA Unit Supervisor, Nuclear Power
- R. C. Miles, Assistant Construction Engineer
- E. C. Pendergrass, Engineering Associate
M. A. McBurnett, Nuclear Engineer, Power / Reg. Staff D. A. Kulisek, Nuclear Engineer, Power / Reg. Staff D. Baese, Instrumentation Engineer, IEU H. W. Loftis, Mechanical Engineer, MEU J. Fox, Engineering Associate, MEU
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Other licensee employees contacted included construction craftsmen, techni-
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cians, QC inspectors, and office personnel.
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" Attended exit interview i
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2.
Exit Interview
.The inspection scope and findings were summarized on January 16, 1981 with
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- those persons indicated in Paragraph 1-above. The licensee was advised that no new items of violation or deviations were-identified by the inspector.
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3.
Licensee Action on Previous Inspection Findings
Not inspected.
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Unresolved Items
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Unresolved items were not identified during this inspection.
5.
Licensee Identified Items (LII)
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.TVA has reported a number of items to Region II as reportable in a.
"com e with 10 CFR 50.55(e). The Region II inspecte reviewed the i tt sted below and the supporting documentation, and discussed the
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Litems,ith responsible ~ licensee staff during -this-inspection.
(Closed) LII 328/79-31-01': Inadequate' Design of _Containn'ent Spray Heat
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Exchangers.(CSHX), ~ NCR 16P and NCR 2070.
This item was previously discussei in RII inspection reports-50-328/80-09 and 50-328/79-32. The inspectoit reviewed.the TVA final report to RII dated February 1,1980, the' closud disposition of NCR 2070, the corrective actions taken as specifiec cin drawings 2FW-001-AB through '18 entitled, " Containment Spray Heat Exchangers - zA, 28, Tube Modifications". Co^ ective
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l actions taken were discussed with the responsible mechanical engineer j
inspector and pictures taken during various phases of the tube staking i
modification were examined.
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(Closed) LII 328/80-03-03 - Omitted Supports in the CVCS, NCR CEB t
l 79-38.
This item was previously discussed in RII inspection report
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50-328/80-09.
The inspector reviewed the TVA final report dated l
January 31, 1980, related ECN 2829 which provided for adding supports i
MK Nos. 2CVCH-616 and 617.
The inspector examined the installed f
subject supports and found the support assemblies installed in accor-
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l dance with approved drawings.
(Reopened and Closed) LII 328/80-03-04 - Copes - Vulcan Valve Weights
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Incorrect, NEB 80-1 and NEB 8020.
Based on the corrective actions j-specified in TVA's final report dated February 11, 1980, the subject i
deficiency was closed in RII report 50-328/80-03. Subsequent to this i
l item's closure, TVA found that additional valves were affected by this nonconformance. TVA has since issued supplemental information reports dated August 15, 1980 and September 2,1980 specifying the location, valve ID number, correct and incorrect listed weights of the additional
l affected valves. TVA had the piping system load analysis rerun using l
the correct valve weights. The resulting new loads were then applied in the support calculations and the existing supports were found to be
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adequate to absorb the new loads.
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(Closed) LII 328/80-03-01 - Bettis Valve Actuators, NCR 19P.
The inspector reviewed the TVA final report dated January 17, 1980, related work plan No. S-1257, closed ECN 2804,-and document control QC inspec-tion records that verified the valve actuators identified on work item i
l No. 10509 were reworked and equipped with retainer bushings if
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required.
The inspec+or selected auxiliary building valve actuator l
2-FCV-30-61= (Purge Mr Exhaust Unit A Sunction Valve) to be visually examined to-insu?e that its spacer bushing had been installed as QC records indicated.
The work was found accomplished as stated in inspection recoros.
I (Closed) LII 328/81-02-38 - Spray Header Attachment Lug Re-evaluation, SWP 8009.
The subject deficiency was initially reported to P.II on Jub 9,1980 and TVA : submitted a' final report on this matter dated
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August 7, 1980. The support lug attachments located in the containment dome for the containment spray and residual heat removal system headers j
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l were found to be not ' properly evaluated when the subject--supports were l
reanalyzed for steel containment vessel dynamic movements during a
design basis accident (DBA). :TVA's recent reanalysis of the subject support lug attachments verifies that they perform their designed functions. This item was opened and closed during this inspection.
(Closed) LII 328/80-02-39 - Sensing Line Connections to Process Piping
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SWP 8010.
TVA initially reported -the subject deficiency to RII on l
July 9,-1980 and the licensee-subsequently submitted interim and final
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reports c,d the matter dated AJgust 7,1980 and October 16, 1980 respec-
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tively.
The original piping analysis assumed the sensing lines to be tubing when they were actually piping.
The stress imposed on the process piping due to less flexible sensing lines and the inertial effects of the increased weight of the sensing line pipes and connec-tions were not included in the seismic analysis; therefore, it was possible that supporting hardware was not adequate to carry the design loads.
TVA has since reanalyzed the affected process using proper weights and found that no hardware changes are necessary to carry the additional loads. This item was opened and closed during this inspec-tion.
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(Closed) LII 328/80-02-40 - Def'ective Containment Vacuum Relief Isola-tion Valve Pneumatic Operators, NCR 2292R.
The licensee initially reported the subject deficiency to RII on September 23, 1980 and submitted a final report on the matter dated October 23, 1980. An excessive corrosion problem was identified in all three of the con-tainment vacuum relief isolation valve pneumatic operators.
The pistons, piston seals, return springs, and cylinders of the operators were damaged by corrosion to the point that operation of the operators
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was inhibited. Repair parts or suitable replacements for the operators were not available so the entire valves and operator assemblies were replaced by valves that were transferred from Hartsville Nuclear Plant in accordance with ECN 2928.
This was handled under contract No.
788256 and shipping ticket No. G178095. The inspector accompanied by a'n instrumentation engineer verified that the three presently installed valve serial numbers corresponded with those that appear on the
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Hartsville shipping ticket.
Inspection records, specifically II80 l
(stroking inspection) and II85 (tubing check) were examined for the three valves to ensure their proper operability. This item was opened and closed during this inspection.
(Closed) LII 328/80-02-41 - Seismic Analysis of 3-inch Check Valve in t
CVCS, CEB 8028. TVA initially reported the subject deficiency to RII on October 2, 1980 and submitted interim progress reports dated
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l October 31, 1980 and January 6, 1981. During a design review, it was discovered that a 3-inch check valve was overlooked in a piping analysis of the CVCS for unit 2, thereby creating the possibility of inadequate pipe supports due to unknown seismic loading.
Subsequent TVA reanalysis of the subject deficiency has determined that the t
additional loads due to -the 3-inch check valve are not significant and
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no hardware changes are required.
This item was opened and closed l
during this inspection.
(Reopen) LII 328/79-16-04, Containment Piping Support Design Basis, CEB 79-19. TVA has issued a supplemental information report dated June 18, 1980. The residual heat (RHR) spray header piping was not reanalyzed for the design basis accident movement of the steel containment vessel.
This reanalysis should have been accomplished as a part of the response to nonconforming report CEB 79-19.
Based on the above, LII 328/79-16-04 is reopened; it was previously closed in RII report 50-328/79-55.
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New supports and some changes to the existing supports are required for the RHR spray header line. This item was not inspected.
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The following LII's were reported to RII during the period April, 1980 through January, 1981.
The dates listed below correspond to TVA's initiai telephone (T) notification of the subject LII to RII and subsequent dates thereafter relate to various licensee written reports (I - interim, F - final, RF - Revised Final) received by RII on the subject matters. The below listed LII's are opened in this inspection and given the fellowing RII item numbers.
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Item No.
Title Reports Received 328/81-02-01 Incorrect Insulation Weights 4/24/80 T (CEB 8008)
5/23/80 I 10/16/80 I i
328/81-02-02 Environmental Effect On Main 4/25/80 T (MEB 8002)
Stream Safety Valve Set Points 5/27/80 F 6/11/80 RF 328/81-02-03 Omitted Pipe Rupture Protective 4/30/80 T (NEB 8009)
Devices 5/29/80 F (NEB 8010)
l 328/81-02-04 Spent Fuel Pool Gates 5/01/80 T I
(NEB 8012)
5/29/80 I l
6/18/80 F 7/02/80 RF 9/08/80 2RF 10/15/80 3RF 328/81-02-05 Secondary Side Pipe Breaks -
5/16/80 T (CEB 8012)
Design Criteria Change 6/11/80 I
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9/04/80 I 10/29/80 F
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328/81-02-06 Chemical Volume Control System 5/20/80 T
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(NEB 8017)
Centrifugal Charging Pumps 6/18/80 F i
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328/81-02-07 Nonconservative Baron Oilution 7/10/80 T (NEB 8023)
Indication 8/08/80 I 10/08/80 I 328/81-02-08 Seismis Supports for Auxiliary 7/21/80 T l
(EEB 8017)
Feedwater Control Valves '
8/20/80 F
328/81-02-09 Incorrect Valve Weights In 8/01/80 T l
(CEB 8023)
Auxiliary Feedwater Piping 9/04/80 I
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10/22/80 F i
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328/81-02-10 Piping Support Df crepancies 8/05/80 T (NCR 2246 &
At ERCW Pumphouse 9/04/80 F 2259 i
328/81-02-11 Safety Injection Train B 8/22/80 T (NEB 8025)
Flow Deficiency 9/22/80 I 10/23/80 F 11/26/80 RF 328/81-02-12 Auxiliary Feedwater Recirculation 8/27/80 T (SWP 8014)
Line 9/25/E0 F 328/81-02-13 Analysis of Inteu -diste Break 9/18/83 T (CEB 8027)
Locations 10/16/80 I 12/02/80 I 328/81-02-14 ERf W Pump Motor Relays 10/06/80 Y (EEB 8022)
11/05/80 F 328/81-02-15 Environmental Qualification of 10/24/80 T (EEB 8023 Electrical Equipment 11/25/80 I thru 8039 excluding.
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EEB 8034)'
(EEB 8008, 8040, 8041, 8042, 8044)
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-328/81-02-16 Non-reinforced Masonry Walls 10/17/80 T l
(CEB 80-31)
11/14/80 I
l 328/81-02-17 Offsite Power Supply Fluctuations 10/20/80 T
(EEB 8034)
11/19/80 I 328/81-02-18 Faulty Filet Welds 11/07/80 T (NCR 2398)
12/03/80 I 328/81-02-19 Auxiliary Feedwater System 10/07/80 T (EEB 8021)
Design Deficiency 11/05/80 F 328/81-02-20 Broken Spring In Pressurizer 10/29/80 T (NCR 2397)
Safety Valve 11/26/80 t'
328/81-02-21 Inadequate Cladding Thickness 11/17/80 T (NCR 28P)
On 2BB Centrifugal Charging Pump 12/17/80 F
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328/81-02-22 U-derpressurized Hydrostatic 11/28/80 T (NCR 2436)
Tests 12/29/80 F 328/81-02-23 Thermon Heat Transfer 11/26/80 T
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(CEB Br36)
Cement 12/29/80 I
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328/81-02-24 Stress Corrosion Cracking 12/02/80 T
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In Tubing of Reactor Coolant 1/02/81 I Pump-I 328/81-02-25 Discrepancies In The Field 11/28/80 T i
(SWP 8023)
. Installation of Pipine Syscems 12/29/80 I and Supports Versus Design Isometric Drawings
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328/81-02-26 Discrepancies In As-Built Versus 12/03/80 T (CEB 8037 =
As-Analyzed Piping Anchor 01/05/80 I i
81-01 Locations 328/81-02-27 ASCO Solenoid Valves 12/08/80 T EEB 8044 RI
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328/81-02-28 Diesel Interlock Design Error 12/09/80 T SWP 8026 328/81-02-29 Faulty Fillet Weld-12/10/80 T SWP 8025 Specification 328/81-02-30 Inadequate Handling of 12/11/80 T Audit JA800-Engineering Design -
Engineering Procedure Changes l.
'28/81-02-31 Retrievable Tcformation From 12/12/80 T
'(CEB8035)
_ Valve Tag Numbers
'328/81-02-32 ASCO Solenoid Valves 12/16/80 T SWP 8028
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328/81-02-33 Unconservative Loads On Pipe 12/17/80 T C, ES *'39 Support Design Modifications l
328/81-02-34 Analysis of Steel Containment 12/19/80 T CEB 8041 Penetration Assemblies 328/81-02-35 Corrosion of Carbon Steel'
12/30/80 T NE8 8035
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328/81-02-36 Failure to Comply With 01/02/81 T
- Audit SN-M-Procedures
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F 80-17
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t 328/81-02-37 Failure of Generator System 01/05/81 T
i EEB 8054 To Supply Adequate Voltage To The Safety-Related Boards
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