IR 05000269/1980015
| ML19332A640 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/15/1980 |
| From: | Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19332A630 | List: |
| References | |
| 50-269-80-15, 50-270-80-10, NUDOCS 8009160552 | |
| Download: ML19332A640 (9) | |
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UNITED STATES
1, NUCLEAR REGULATORY COMMISSION
g a
REGION II
g*****[[ o, 101 MARIETTA ST N.W SUITE 3100
ATLANTA, GEORGIA 30303 MAY 2 21980 Report Nos. 50-269/80-15 and 50-270/80-10 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: Oconee Nuclear Station Docket Nos. 50-269 and 50-270 License Nos. DPR-38 and DPR-47 Inspection at Oco e ne - eca, South Carolina . , 5///[ ' Inspector: - m. c-2/ N. Eco p s D4f.e Sfgned Approved by: / ' A. R. Herdt, Section Chief, RCES Branch Date Signed ~ < , SUMMARY j , Inspection on April 15-17 and 21-23, 1980 . Areas Inspected This routine, announced inspection involved 60.5 inspector-hours on site in the
areas of IE Bulletins 79-13 and 79-17 (Unit 2); low pressure turbine rotor UT examination (Unit 2); Inservice inspection, (Unit 2); safe shutdown facility pipe welding.
Results Of the five areas inspected, no items of noncompliance or deviations were identi-fied in four areas; one item of noncompliance was identified in one area (Infrac-tion - Improperly designed ISI calibration blocks, paragraph 6).
. 8.0091605. _ . . .. -.... . . . . DETAILS 1.
Persons Contacted Licensee Employees
- J. E. Smith, Station Manager
- J. M. Davis, Superintendent of Maintenance
- R. J. Brackett, Senior QA Engineer
- T. C. Mathews, Technical Specialist
- A. Grunsky, Associate Engineer
- R. T. Bond, Licensing & Projects Engineer
- B. Calhoun, Associate Project Engineer
- B. Millsaps, Assistant Engineer D. Smith, Technical Specialist J. Donald, QC Inspector, Welding J. D. Norton, ISI Engineer Other licensee employees contacted included construction craftsmen, tech-nicians, and office personnel.
_, , Other Organizations Babcock & Wilcox Construction Company (B&W) F. J. Sattler, Manager Inservice Inspection H. W. Stoppelman, ISI Coordinator G. Dunkle, Level II (UT) J. Jacobs, Level II (UT) F. Nichols, Level II (UT) General Electric Company (G.E.)
- F. Ammirato, Engineer Schenectady
- J. Packard, Engineer Installation and Service
- E. Scales, Level II Examiner (UT)
NRC Resident Inspector
- F. Jape
- Attended swit interview 2.
Exit Interview The inepection scope and findings were summarized on April 17 and April 23, 1980, with those persons-indicated in Paragraph I above. The inspector identified the areas-inspected which included welding, nondestructive examinations and record review of: safe shutdown in facility piping, low
. . .. .. - ., . -2- ., . pressure turbine rotor; ISI activities as applicable and IE Bulletins 79-13 and 79-17. The finding described in paragraph 6 was discussed in detail.
The licensee concurred with the inspection findings.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. New unresolved items identified Juring this inspection are discussed in paragraphs Sa. and 5b.
5.
Independent Inspection Effort a.
Low Pressure Turbine Rotor Examination Unit 2 ' At the' time of this inspection, GE was performing an ultrasonic exami-nation on the low pressure (LP) "A" turbine rotor for possible presence of cracks in the keyway and bore areas of the rotor. This work was being performed pursuant to GE's technical information letter and IE Information Notice 79-37.
On April 17, 1980, the inspector discussed the examination program with the licensee representative and requested a copy of GE's ultrasonic inspection procedure _along with related personnel and equipment certifi-cations for review.
In response the licensee stated that GE had rejected the inspector's request for the aforementioned documents.
Since. meetings on turbine inspections had been held between GE and NRC, the inspector made an inquiry to ascertain whether IE and/or NR2 had reviewed, and was satisfied with, GE's procedures and method of examination. This could alleviate the need for the inspector's review and work observation. The inspector was informed that a review of the requested documents and work observation was in order since no agreement i-had been made with GE to prevent such an effort. The inspector subse- ) .quently met with the licensee and again requested to review the afore- ' mentioned documents. The licensee representative agreed to persue this matter further with corporate management and report back as socm .as possible. This matter was identified as unresolved item 50-270/80- 't 10-02 " Low pressure turbine Rotor Examination Procedure". On April 23, 1980 GE agreed to: (1) furnish the licensee a copy of the requested documents for _RII review and, (2) discuss details of the ongoing ultrasonic examination of LP "B" rotor to the inspector. On April 23 the GE level II UT examiner-in-charge of the. inspection discussed the equipment used for the examination, calibrated the system and conducted
several scans on the hub of wheel 3 of Unit 2 low pressure "B" rotor.
No indications were observed at.this time. By agreement a copy of the , , - -
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examination procedure and personnel qualifications will be provided to j~. the_ licensee and NRC. This in addition to the inspection data will be reviewed by the NRC when submitted by-the licensee.
No items ' of ' noncompliance or deviations were identified.
. b.
Standby Shutdown Facility (SSF).
. ' ' At the time of this inspection concrete pouring was in progress on the lower elevations-and the walls. Welding on carbon and stainless , piping was in progress. The controlling document is entitled "Informa-tion in Support of Standby Shutdown Facility, GS-1014-5M-19".
It . identifies the structure as Seismic Category I and commits pipe design to ASME Section III. The project is being handled as Station Modifica-
. tion 1012 part H. Pipe and welding requirements are controlled by Pipe - Design Specification OS-27-A.1 and the Power Piping Quality Assurance- , Manual. The reactor coolant makeup' and the auxiliary service water systems are the two systems involved in the modification Within these areas.the inspector reviewed applicable isometric drawings and inspected j the following completed welds in the auxiliary service water supply ' l system for code and procedural compliance: . , ) . Weld Size ISO Type , j.
34-17 16" Schedule 20 34 Rev. 5 Pipe to Ell ' j - 34-14 16" Schedule 20 34 Rev. 5 Pipe to Ell
36-3' 12" Schedule 20
Pipe to Ell 36-10 12" Schedule 20
Pipe to Ell 213-4 6" Schedule 213 Pipe to Ell ' Within theselareas'the inspector observed / inspected workmanship, ID and OD .' ' -bead appearance, cleanliness, weld and welder identification.
In addition
the inspector reviewed welderiqualification records, consumable material receipt inspection records and quality certifications, pipe material quality records'and weld fabrication quality contro1' records. At this time the inspector advised the~ licensee representative that the stainless steel pipe L material which was fabricated to SA-312 specification was the' subject of IE Bulletin 79-03A " Longitudinal Weld Defects in ASME SA-312, Type 304 Stainless ~ Steel-Pipe".,This matter was discussed further with Duke Power Company (DPC). licensing who stated that a generic response to'the bulletin would be forthcoming. Also the inspector noted -that while the Power Piping Quality Assurance _(PPQA) Manual referenced the. applicable piping code and-class but
- it did'not specify the edition and addenda being envoked. 1This matter was - discussed with' site. personnel and DPC licensing who agreed to make this . $ .
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, - . . . -4- . information available for IE:RII review. The inspector stated this would ~be identified as unresolved item 50-269/80-15-01 " Safe Shutdown Facility Pipe Code Edition".
Within the area examined, no items of noncompliance or deviations were identified.
6.
Inservice Inspection Data Review and Evaluation (Unit 2) This work effort was related to the fourth refueling outage which began on/or about March 23, 1980 and was still in-progress at the time of this inspection. Nondestructive examination /ISI activities were conducted by B&W under contract with DPC. The controlling document is B&W's 1980 ISI Manual for Unit 2.
This manual and related ISI procedures had been approved by B&Ws Level III examiner and DPC's cognizant QA representative. The manual contains the current ISI scope and the projected ISI program over the first to a (10) year interval.
Section XI of the ASME Code 1974 Edition thrcugh the 1975 summer addenda controls NDE requirements.
Components / parts scheduled for ISI during this outage include the reactor vessel, pressurizer, once through steam generators (A&B), nozzles, pressure boundary piping, various Class 2 parts and components and hangers.
The inspector selected NDE records of the pressurizer, reactor vessel clad pa,tches, pressure boundary pipe welds and pressure retaining bolting.
These records were reviewed to ascertain whether they contained information on, or provided reference to; examination results, examination equipment data, calibration data sheets, evaluations of indications, extent of exami-nation,programatic deviations, disposition of findings and identification of NDE material e.g.
UT couplant. Records selected for this review were as follows: Component Figure Weld Area /Part Inspect Method-El.31.1 Closure Head Surface Cladding Patches B2.1.11.
Pressurizer shell to Volumetric upper head circle seam . B3.6 Upper head manway nuts Visual B4.1 Dissimilar welds - Volumetric and Surface RC discharge, B2 pressurizer spray i pressurizer relief High pressurizer Injection, B2 '
. . . -5- . -(Cont'd.)
. Weld No.
System Iso Size Bl.11.1 CRD housing bolts Visual Bl.11.2 CRD housing nuts Visual 'Bl.13.1 Closure head Visual and surface Cladding Patches, 2 and 4 B2.8.1 Vessel support lugs Visual B3.6.3 Upper head manway nuts Visual B3.6.7 Upper threaded stud Visual holes BU.1.35,.36 RC discharge B2 Volumetric and surface safe-end to elbow B4.1.43,.44 Pressurizer spray Volume * ric and sruface Noz. safe-end to spray line B4.5.24 RC Hot leg B circle Volumetric seam B4.5.25 Circle Seam Pipe to Volumetric i P Pe B4.2.26 Circle Seam pipe to Volumetric P1'Pe 5.59 Pipe to Elbow Volumetric j .B4.5.60 , Pipe to pipe Volumetric B4.5.61 El. to pipe Volumetric C2.1.24 El to pipe Volumetric C2.1.28 Reducer to El.
Volumetric 8" x 6" Within these areas the inspector noted that certain dimensions, size and location, of notches and holes shown on calibration block drawings No.
PC-24602-4 PC-24603-4, reflecting as built dimensions for calibration blocks numbers 40303/40304, were not consistent with figure I-3131 of ASME Section XI (74S75). For example notch depth in both blocks exceeded the 2%
T-requirement and some of the holes were not accurately located. These .
... . . -6- . ,, blocks were'used for the. examination,of the pressurizer shell to upper head weld figure number B2.1.11.
This matter was discussed in detail with the licensee representative and the B&W Level III examiner.
In response to questioning the B&W Level III examiner stated that the seven (7). inch block No. 40304 was fabricated to meet the 1970 code requirements and the five . (5) inch block No. 40303 the present code (74S75) requirements.
Both blocks are used jointly to examine and monitor certain indications in the . aforementioned pressurizer head to shell weld. These indications were discovered during'the baseline inspection.
B&W stated that the reflector discrepancy had been reported by letter last fall but DPCO stated that no corrective action was taken. This item is considered to be in noncompli-ance with 10 CFR 50.55(a) as implemented by the Technical Specification . paragraph 4.2.
This noncompliance'is categorized as an infraction-and is identified as item 50-270/80-10-01, Improperly designed ISI calibration ~ blocks.
7.
Inservice Inspection - Observation of Work Activities (Unit 2) e Except for a few welds'inside "B" cavity, ISI examination of welds was complete. The applicable Code and addenda is discussed in paragraph 6 Labove. Of the remaining welds to be examined the inspector observed the
-ultrasonic examination of OTSG "A".Shell to Shell weld fig. C1.1.1.
The weld was scanned with a 45 degree shear wave transducer as required by Code and ISI procedure ISI-130 Rev. 12.
Calibration was performed on block number 40339. The aforementioned examination including instrument / system calibration, documentation of results and evaluation of data was performed as required by the applicable Code and procedure.
Within the areas inspected, no items of noncompliance or deviations were identified.
8.
IE Bulletin No. 79-17, Pipe Cracks in Stagment Borated Water Systems at Power Plants (Unit 1) This work effort was a followup to earlier inspections in this area docu-mented under IE:RII Report Nos.'50-269/80-03, 50-287/79-21. Welds selected - for observation of ultrasonic examination were as follows: Weld No.
System Iso Size 59A High Pressure 51A Sketch 6" x.260" Injection
58A High Pressure 51A Sketch 6" x.260" Injection
64AE High Pressure 51A Sketch 6" x. 260" Injection
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Weld No.
System Iso Size 49A High Pressure 51A Sketch 6" x.260" Inj ection
Surface examinations were performed per procedure ISI-240 Rev. 5, " Penetrant Examination of Welds and Base Materials". Records of completed weld examina-tions selected at random were reviewed for completeness and accuracy.
These were as follows: Weld No.
System Iso Size A15 Low Pressure 53B 14" x.250" Injection SK Low Pressure 53B 10" x.250" Injection 86C Building spray 54A 8" x.250" 85C Building spray 54A 8" x.250" For these welds the inspector reviewed persennel qualification and liquid penetrant material certifications. All examinations observed at this time were performed in accordance with procedural requirements by personnel who appeared to be adequately qualified to perform their assigned tasks.
Equipment, material and personnel certifications were found to be in order.
Records of completed examinations were reviewed for completeness and accuracy.' Within the areas examined, no items of noncompliance or deviations were observed.
9.
IE Bulletin 79-13 Cracking in Feedwater System Piping (Unit 2) This work effort was a followup to the on going review of radiographs taken to verify the integrity of certain auxiliary feedwater pipe welds. This . matter was discussed in RII Report Nos. 50-269/80-01 and 50-269/80-03. The following radiographs were reviewed to determine whether they met applicable code, ASME Section III (77S78) NC-5000 and to the 2T sensitivity level.
The radiogtaphic procedure was identified as NDE-10A Rev. 4.
Once Through Steam Generator #2A Weld #. Location Type 1.
DOC 2F Header #1 Flange to 90' EL - 2.
DOC 2F' Header #1 Pipe-to pipe 3.
DOC 2F Header #3 90 to EL 4.
-D00 2F Header #7 90* to flange
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. ... . -8- - Once Through Steam Generator #2B Weld # Location Type 5.
DOC 2F Header #6 Pipe to pipe 6.
DOC 2F Header #6 El to flange . Items 1 and 5.
exhibited rejectable fabrication type indications which had been identified by the licensee and will be reported to RIIuas requested by the aforementioned Bulletin.
Within the areas inspected, no items of noncompliance or deviations were identified.
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