IR 05000328/1981027
| ML20009G675 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/15/1981 |
| From: | Economos N, Herdt A, York J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20009G668 | List: |
| References | |
| 50-328-81-27, NUDOCS 8108040541 | |
| Download: ML20009G675 (7) | |
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o,, UNITED STATES ! NUCLEAR REGULATORY COMMISSION n O E REGION 11 [[ 101 MARIETTA ST., N.W., SUITE 3100 o, ATLANTA, GE ORGIA 30303
b ' Report No. 50-328/81-27 Licensee: fennessee Valley Authority i 500A Chestnut Street l Chattanooga, TN 37401 , Facility Name: Sequoyah Docket No. 50-328 . License No. DPPR-73
Inspection at Sequoy Si e a rSoddy Daisy, Tennessee t , ! Inspectors: f' mm_ _ 7-/3- //
N. Econ 6fnos Date Signed M w LO, % 8- ,//s/8/ " , York ' Date S'igned . Approved by: b6 7/N 8/ , A. R. Herdt, Section Chief Oate' Signed Engineering Inspection Branch Engineering and Technical Inspection Division i SUMMARY , I Inspection on June 2-4, 1981 Areas Inspected This routine, unannounced inspection involved 44 inspector-hours on site in the areas of safety-related pipe supports and restraints; licensee identified items; inspector identified items.
Results r
Of the areas inspected, no violations or deviations were identified.
I i 8108040541 910716S PDR ADOCK 05000320 G PDR, . - - _. _,. - . 1 . -.-. . _ _ - _. _... _.. -, .. . - - -.. . - . - - .
, - .. . REPORT DETAILS 1.
Persons Contacted Licensee Employees
- T. B. Northern, Construction Engineer
- J. M. Munns, Jr., QA Supervisor
- K. G. Galloway, M&WIU Supervisor
- D. W. Kelley, QCRU Supervisor
- E. Burke, EIIU Supervisor
- S. B. Miller, Engineering Aide QCRU
- D. P. Roberts, Nuclear Engineer Compliance
- R. C. Miles, Assistant Construction Engineer J. W. Beason. Civil Engineer (EN-DES)
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 4,1981 with those persons indicated in paragraph 1 abcve. The inspector described the areas inspected and discussed in detail the inspection findings listed below: (0 pen) Inspector Followup Item 328/81-27-01: " Revise UT Procedure W-SQN-1 and provide transducer certification", paragraph 5.b.(1).
(0 pen) Inspector Followup Item 328/81-27-02: " Baseline Inspection Report of Nozzle 2RC-17 Repair", paragraph 5.b(2).
(0 pen) Inspector Followup Item 328/81-27-03: Commitment to Reinspect 2RC-17 and One Additional Unit-2 Nozzle", paragraph 5.b.(3).
3.
Licensee Action on Previous I' pection Findings I (C:osed) Unresolved Item (328/81-14-04), Repair Damaged Fire Barrier for Pressurizer and Steam Generator Instrumentation Circuits (Unit-2).
The j ! inspectors, accompanied by the licensee's cognizant engineer, conducted a I walk through inspection from the auxiliary building to the containment l penetration at the 734' elevation and observed the Q line conduits wrapped with "Kaowool" insulation. The inspectors noted that the designated Q lines were insulated and that there was no evidence of damaged insulatior on those , l lines.
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Unresolved Items Unresolved items were not identified during this inspection.
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Licensee Identified Items 30.55(e)
a.
(Closed) 328/81-02-18 Faulty Fillet Welds NCRs 2398 and 2630.
The - inspectors reviewed the licensee's final report dated April 3,1981 and e discussed the programmatic aspects of the ccrrective action with - cognizant licer.see personrel. Three welds which require disposition by i ! ENDES are listed below: l Weld Size Condition
i ! 2SG-1333 2" sch 160 These welds are inaccessibic for r i 2SG-1338 inspection because of penetration I and location of split-anchor j sleeve.
! 2SI-2088 2" sch. 160 This weld is undersize but inacces-j s1ble to weld.
t , A sample of inspected and accepted welds were selected at random for ! observation in order to ascertain whether fillet size was consistent ' with procedural / code requirements. The selected welds were as follows: l l Weld System Size Drawing No.
I 2UH 1441 Upper Head Injection 2" sch. 160 2VPI-007W R3
, j 2VH 1448 Upper Head Injection 2" sch. 160 2VPI-007W R3 l 2VH 1117 Upper Head Injection 3/4" sch. 160 2VPI-005W R6 ' 2VH 1126 Upper Head Injection 3/4" sch. 160 2VPI-005W R6 ' 2VH 1161-2 Upper Head Injection 3/4" sch. 160 2VPI-005W R6 l 2SI 1721, 38 Safety Injection 3/4" sch. 160 2SI-76W R6
1CX 3731-5, Chemical Volume Control 1" sch. 160 CVC-037 R3 l ICX 3737 Chemical Volume Control 1" sch. 160 CVC-037 R3 ICX 3738 Chemical Volume Control 1" sch. 160 . CVC-037 R3 ' 1CX 3738A Chemical Volurr.e Control 1" sch. 160 CVC-037 R3 1CX 3742 Chemical Volurne Control 1" sch. 160 CVC-037 R3 1CX 3742 Chemical Volume Control 1" sch. 160 CVC-037 R3 l ICX 3744 Chemical Volume Control 1" sch. 160 CVC-037 R3 . ICX 3749 Chemical Volume Control 1" sch. 160 CVC-037 R3 l 1CX-3738B Chemical Volume Control 3/4" sch. 160 CVC-037 R3 ( 2SI-2164-5 Safety injection 2SI-5091W R/3
2GI-2164-21 Safety Injection 2" sch.160 2SI-5091W R/3 ! 2SI-2164-83 Safety Injection 2" sch.160 2SI-5091W R/3 j 2SI-2164-85 Safety Injection 2" sch. 160 2SI-5091W R/3 i
2SI-2164-86 Safety Injection 2" sch. 160 2SI-5091W R/3 ' 2SI-2164-7 Safety Injection 2" sch. 160 2SI-5091W R/3 2SI-2164-8 Safety Injection 2" sch. 160 2SI-5091W R/3 l 2SI-2164-8A Safety Injection 2" sch. 160 2SI-5091W R/3 2SI-2164-89 Safety Injection 2" sch. 160 2SI-5091W R/3 l 2SI-2180 Safety Injection 3/4" sch. 160 2SI-5091W R/3 l !
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These welds were found to be accept 21e as indicated on the licensee's records.
b.
(Closed) 328/81-20-06 Reactor Vessel Field Weld Indications SQRD - 50-328/81-15.
The inspectors reviewed the licensee's final report to NRC RII dated May 28, 1981 and a metallurgical investigation / evaluation report entitled "Sequoyah Nuclear Plant Unit 2 Evaluation of Cracking in Reactor Vessel Nozzle Stainless Steel Buttering", May 29, 1981.
Discussions and interviews with cognizant licensee personnel disclosed the work had been completed, that the nozzles had been covered and the reactor cavity saaled in preparation for a leak test which precluded i observation of ',ne repair at this time.
The inspectors reviewed welder and repair welding procedure qualffica-tion records, welding material certification records, preheat and postweld heat treat strip charts and fabrication records, UT proce-dures, test results, calibration standards, instruments and probe certifications, personnel qualifications.
Within these areas the inspectors noted the following: (1) Procedure W-SQN-1, Rev. O, " Ultrasonic Test Procedure for Examination of Half-Bead Repairs to Safe End Welds", which had been approved by Westinghouse (W) Level III UT examiner and TVA-ENDES cognizant engineer exhibited several discrepancies in that the sketch of the calibration block was not properly labeled - calibration holes were not identified on the sketch and, the thickness dimension did not agree with that of the block, e.g., 1-1/2" sketch versus 1-3/4" actual. Also the inspectors i noted that the certifications of the 70 and 0 transducers used by W to perform the UT examination of the.mzzla(s) were not l-l incTuded in the data package. The inspector requested and the licensee agreed to make the necessary corrections and provide the i transducer certifications for RII review on a future inspection.
l This matter was identified as inspector followup item 328/81-27-
01, " Revise UT procedure W-SQN-1 and provide transducer certifi- ! cations".
(2) As stated above the inspectors reviewed results of liquid pene- , trant examination and the ultrasonic examination performed from
the outside diameter by W.
In addition to the above, the repair
area was ultrasonically examined from the inside diameter by TVA i in order to establish baseline data. This data was not available
for review at this time and the inspectors stated that this matter
would be identified as inspector followup item 81-27-02, " Baseline l 17spection report of nozzle 2RC-17 repair".
l (3) In the final report to RII dated May 28, 1981, TVA stated that at the first regularly schedulcd cold shutdown of sufficient dura-j tion, nozzle 2RC-17 and one additional Unit 2 reactor vessel
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nozzle would be reinspected. This matter was discussed in detail with the licensee and the inspectors stated that this would be regarded as a commitment and would be identified as inspector followup item 81-27-03 " Commitment to reinspect 2RC-17 and one additional Unit 2 RV nozzle".
Within the areas inspected, no violations or deviations were identi-fled.
c.
(Closed) 328/80-09-04 Walworth Valve Weight Incorrect NCR CEB 8005.
l The inspectors reviewed the licensee's final report dated April 11, ' 1980, which indicated that only one hanger needed to be modified
because of a change in valve weights. The hanger number in this final ) report was H10-1338 for Unit-1.
The inspectors verified thru the appropriate drawing examinathn that the correct hanger number for Unit-2 was 20HPAB464-3-153. An inspection of the hanger showed that the modifications had been made.
This item is considered closed l pending receipt of a revised final report with the correct hanger j number.
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Sequoyah Nuclear Plant Unit 2, Preservice Examination i ! On June 11, 1981, TVA informeJ RII by memorandum that the preservice I examination of welds in the reactor coolant systems and components which consisted of Class 1 and Class 2 piping, steam generators and pressurizer , had been performed in accordance with ASME Section XI (74S75) and Sequoyah Surveillance Instruction 114 (SI-114). Those indications identified by this examination were repaired and reexamined as per requirements of the applic-able code. See paragraph 5. above for additional discussion in this area.
l Within the areas inspected, no violations or deviations were identified.
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IE t.111etin 79-13 " Cracking in Feedwater System Piping" Unit-2 Radiographs of feedwater steam generator nozzle welds, adjacent elbow and l transition spool piece welds radiographed in response ' IE Bulletin, 79-13 were selected for review in order to ascertain whether n.ographic quality and interpretations were consistent with ASME Section III, NC 5000 require-ments including the required 2T sensitivity. Radiographs of the following welds were reviewed: Loop 1 Weld No.
Type Size 2FDF-10 Elbow 16" sch. 80 2FDF-10/11 Trans. pce.
16" sch. 80 !' ' 2FDF-11 S. G. Nozzle 16"sch. 80 l l l t i
< . , .. .. i Loop 4 ) Weld No.
Type Size 2FDF-21 Elbow 16" sch. 80 2FDF-21/22 Trans. pce.
16" sch. 80 2FDF-22 S. G. Nozzle 16"sch. 80 , , Loop 3 Weld No.
Type Size 2FDF-130 Elbow 16" sch. 80 2FDF-130/131 Trans. pce.
16" sch. 80 2FDF-131 S. G. Nozzle 16"sch. 80 Loop 2 Weld No.
Type Size 2FDF-140 Elbow 16" sch. 80 2FDF-140/141 Trans. pce.
16" sch. 80 2FDF-141 S. G. Nozzle 16"sch. 80 In addition, the inspectors reviewed UT daca records for the above welds.
The UT examination was performed in accordance with Procedure N-UT-1, Revision 4 and ASME Section XI (74575).
Instrument calibration was performed on a block with 5% notches. The examination was conducted with a 45 probe from the ID and OD of the pipe.
Within the areas examined, no violations or deviations were identified.
(Closed) IE Bulletin 79-02: Pipe Support Base Plate Designs Using Concrete Expansion Anchors. A review of the various submittals and the results of a number of inspections that were performed regarding IEB 79-02, indicate that Sequoyah Unit 2 has complied with the requirements of this Bulletin. The Bulletin is considered closed.
9.
(0 pen) IE Bulletin 79-14: Seismic Analysis for AS-Built Safety-Related Piping Systems.
A rough draf t of the final report to be submitted for satisfaction of IEB 79-14 was discursed with a representative of TVA ENDES CEB engineering staff.
All the inspections have been completed and approximately 87 percent of the required modifications for Sequoyah 2 are completed.
The fcilowing table summarizes the progress made on the modifications: Reporting Date 5/27/81 6/3/81 Support Modifications (Total) 2168 2168 Completed Support Modifications 1933 1951
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6 Pipi.g Modifications (Total) 2458 2460 Completed Piping Modifications 1981 2068 Discussion with a licensee representative indicated that all of the modifications would not be completed before the fueling operation. A list is being compiled of those modifications that are expected to be incomplete by the time this operation is to be performed.
The following three completed hangers were inspected: a.
Hanger No. 2070 HPABA464-3-145 in the Component Cooling System b.
Hanger No. 2-CCH-456 in the Component Cooling System c.
Hanger No. 2070 HPABA464-3-153 in the Component Cooling System.
A fourth hanger (No. 2070 HPR247A464-3-155) in the process of being installed in the Component Cooling System was also inspected.
Within the areas inspected, no violations or deviations were identified.
10. (Closed) IFI 328/81-06-01: Axial Load on Collar Snubber From One Direction.
The inspectors reviewed ENDES correspondence in relation to this matter.
There are a total of six of the supports in Unit 2.
These supports were designed by EDS Nuclear Incorporated and they reaffirmed the correctness of this design.
In addition, TVA reanalyzed three of the analyses and con-firmed that this support configuration is acceptable. Therefore, this item is considered closed.
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