IR 05000269/1978006
| ML19316A190 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/05/1978 |
| From: | Conlon T, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19316A179 | List: |
| References | |
| 50-269-78-06, 50-269-78-6, 50-287-78-06, NUDOCS 7911280725 | |
| Download: ML19316A190 (6) | |
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NUCLEAR REGULATORY COMMISSION
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230 PE ACHT RE E STR E ET. N.W. SUITE 1217 o
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ATLANTA, GEORGIA 30303
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Report Nos.:
50-269/78-6, 50-270/78-6 and 50-287/78-6 Docket Nos.:
50-269, 50-270 and 50.-287 License Nos.:
DPR-38, DPR-47 and DPR-55 Categories:
C, C, and C
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Licensee:
Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
Oconee Nuclear Station, Units 1, 2 and 3 Inspection at:
Oconee, Seneca, South Carolina
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Inspection conducted:
March 14-16, 1978 Inspector:
Nick Economos Reviewed b O e 77 t'YT
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T. E. Conlon, Chief
' J$a te Engineering Support Section No. 2 Reactor Construction and Engineering Suppert Branch Inspection Summarv
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Inspection on March 14-16 (Report Nos. 50-269/78-6, 50-270/78-6 and 50-287/78-6)
Areas Inspected:
Corrective action on unresolved item 76-12/1; ISI identified indication on main feedwater header of Unit 3; method of stabilizing plugged steam generator tubes; Unit 2 (June - July) refueling outage ISI data. The inspection involved 18 inspector-hours on site by one NRC inspector.
Results: Of the four areas inspected no apparent items of noncompliance were identified in three areas; one apparent item of noncompliance (infraction - failure to meet minimum Code requirements - paragraph 5.b)
was identified in one area.
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RII Rpt. Nos. 50-269/78-6, I-1 i
50-270/78-6 and 50-287/78-6 DETAILS I Prepared by:
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N.'fconomos Metallurgical Lagineer j/ pite Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspection:
March 14-16, 1978 Reviewed by w-mv Cf FE'
T. E. Conlon, Chief
' date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch 1.
Persons Contacted Duke Power Company (DPC)
- J.
E. Smith, Station Manager
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- D. Norton, QA Engineer, Charlotte
- R. J. Brackett, Station Senior QA Engineer
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- R. T. Bond, Station Technical Services Engineer
- Denotes those present at exit interview.
2.
Licensee Action on Previously Identified Inspection Findings a.
(Closed) Unresolved Item (76-12/1): Nondestructive Examination
Acceptance Criteria
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i Nondestructive examination procedures used during inservice inspections have been ?;rised to indicate applicable code editions and addenda. Procedures reviewed included:
QCI-2 Liquid Penetrant Examination Technique (Solvent Removable)
QCI-5, QC Yoke Method Magnetic Particle Inspection Technique L-IR General Radiography Procedure
b.
(Open) Unresolved Item (77-17Ul): ISI Calibration Block Evaluation The licensee provided the inspector B&W's calibration block
.I comparison data from tests conducted on calibration blocks #40301
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and 40340. The inspector informed the licensee that this item would not be closed at this time in order to allow for a more detailed evaluation.
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RII Rp t. Nos. 50-269/78-6, I-2 i
50-270/78-6 and 50-287/78-6 3.
Unresolved Items No new unresolved items were identified during this inspection.
4.
Independent Inspection Ef fort a.
Steam Generator Tube Stablization, (Unfcs 1-3)
Leaky steam generator tu,bes are removed from service by plugging the lower end of the tube, per approved plugging procedure number MP/0/A/ll30/01 and by stabilizing / sealing the tube from the top per maintenance procedure MP/0/A/1130/ll.
This technique was developed by Babcock and Wilcox (B&W) and now used by DPC under contracts number 620-0003. Design considerations for each plugging are provided by B&W's Power Generating Groups, Lynchburg. Authorization for the removal is implemented through a field change authorization (FCA)
notice issued by B&W.
DPC uses these documents to generate a nuclear station modification (NSM) document used to verify implementation of procedural requirements. Work materials, inspection and testing are controlled through nuclear station work requests. After the tube stabilizer is installed, the tube is capped and seal-welded with the TIG process.
The inspector reviewed the welding process specification, procedure qualification record, field weld data sheets and welder qualification weld data sheet. Records for the following plugged tubes were reviewed:
Tube Row 109 114 110 113
75 Within the areas inspected, no items of noncompliance or deviations were identified.
b.
Feedwater Ring Header, End Cap Weld Indication - Unit 1 On September 9, 1977, the licensee notified Region II (RII)
that during the inservice inspection of Unit 1, B&W had identified an indication in the 1B steam generator feedwater header end cap weld No. 3-X27 which was interpreted as in-complete penetration.
The indication had a length of approx-imately two inches.
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On October 3, 1977, the licensee notified RII that because of difficulties involved with rehydroing the system, they would l
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RII Rpt. Nos. 50-269/78-6, I-3
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50-270/78-6 and 50-287/78-6
avoid repairing the veld at this time and instead perform further evaluations in accordance with the 1977 Edition of ASME, Section Article IWA-3000 and Table IWB-3514-2.
A review of the evaluation data disclosed that the size of the indication was well within accpetable limits.
In discussing this item with the licensee, the inspector requested and the licensee agreed to reexamine this weld over the next three successive inspection periods.
Within the areas inspected, no items of noncompliance or deviations were identified.
5.
Inservice Inspection Data Review and Evaluation Julv 1977 Refueling Outage - Unit 2 a.
NDE Data Review The ISI was performed by B&W to comply with the 1970 Edition of Section XI of th ASMI Code, including Winter 1970 addenda ('
and NRC Guide 1.83Rl.
All examinations were performed with
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NDE procedures written to comply with ASME Section XI and the referenced portions of ASME Section III, 1968 Edition, through the 1970 Winter addenda.
The examinations were performed by personnel qualified to ASNT Recommended Practice SNT-TC-1A, 1968 Edition.
The following Records of pressure retaining welds and bolting were selected for a detail review:
Component Weld Examination Method Reactor Vessel Figure 1.3.3 Volumetric Closure Head Position 19-26
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to Flange 2B2 Suction Line Figure 4.1.13 to Volumetric, Figure 4.2.38.1 Surface, Visual Mark to Mark as applicable
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RII Rpt. Nos. 50-269/78-6, I-4 50-270/78-6 and 50-287/78-6 Component Weld Examination Method Pressurizer Heater Figure 2.5.4 to Visual and Volumetric Bundle Studs and Figure 2.5.6.1 Examined as installed Nuts 75 Studs 76 Nuts QA/QC records for the above items were reviewed to ascertain whether they described or referenced examination results, equipment and system calibrations, evaluation of NDE data, coverage, disposition of findings, repair and reexamination as applicable. Certification of NDE personnel were in accordance with SNT-TC-1A, Recommended Practice 1968 Edition.
b.
Evaluation of NDE Data Records with results from nondestructive examinations conducted during this ISI on reactor vessel closure head to flange circumferential weld and welds on safety-related piping larger than 2 inches were evaluated to ascertain whether calibration
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sheets were in order, identified indications were properly
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documented and evaluated in accordance with applicable require-ments and that evaluations were performed by properly qualified Level II examiners.
In response to the inspector's request for objective evidence to verify that the code prescribed minimum inspection completion requirements were being met, the licensee informed the inspector that this information would be provided as soon as it could be completed. Subsequently the licensee informed the inspector, by telephone, that their review indicated the minimum inspection completions as required by Article IS-242 and IS-261 of ASME Section XI had not been met for the following areas:
Item No.
Components and Parts to be Examined 1.3, C Vessel-to-Flange and Head-to-Flange Circumferential Welds 1.15, N Interior Surfaces and Internals and Integrally Welded Internal Supports
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1.14, I-l Vessel Cladding
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RII Rpt. Nos. 50-269/78-6, I-5
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50-270/78-6 and 50-287/78-6
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This findings represents a violation to 10 CFR 50.55a(g)(4)
as implemented by the Technical Specification Paragraph 4.2 which specifies that inservice inspections be performed in accordance with methods and intervals indicated in 15-242 and IS-261 of ASMI Section XI.
This was identified as a noncompliance and assigned number 270/78-06-01.
7.
Exit Interview The inspector met with licens'ee representatives (denoted in para-graph 1) at the conclusion of the inspection on March 16, 1978.
The inspector identified the areas inspected.
The licensee was advised that one noncompliance was identified.
The licensee acknowledged the inspection findings.
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