ML20127F122
| ML20127F122 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/04/1985 |
| From: | Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20127F041 | List: |
| References | |
| 50-269-85-06, 50-270-85-06, 50-287-85-06, NUDOCS 8505200332 | |
| Download: ML20127F122 (7) | |
See also: IR 05000269/1985006
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UNITED STATES
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NUCLEAR RE ULAT!RY COMMISSION
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101 MARIETTA STREET, N.W.
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ATLANTA, GEORGI A 30323
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Report Nos.:
50-269/85-06, 50-270/85-06, and 50-287/85-06
Licensee: Duke Pcwer Company
422 Sout5 Church Street
Charlotte, NC 28242
Docket Nos.: 50-269, 50-270, and 50-287
License Nos.: DPR-38, DPR-47, and
Facility Name: Oconee 1, 2, and 3
Inspection C
e.
March 10-21, 1985
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Inspect r:
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N. Fe4mo
Date Signed
Approv d by.
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J/ f./ 31ake, Section Chief
D' te Signed
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Engineering Branch
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Jivision of Reactor Safety
SUMMARY
Scope: This routine, unannounced inspection entailed 31 inspector-hours in the
areas of Unit 2 inservice inspection (ISI), work observation, review and record
evaluation, main feedwater flow-nozzle modification, closing of open items, and
high pressure injection (HPI) thermal sleeve examination.
Results:
One violation was identified - Failure to implerr.ent design specifi-
cation requirements, paragraph 6.
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8505200332 850409
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ADOCK 05000269
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REPORT DETAILS
1.
Persons Contacted
Licensee Employees
M. S. Tuckman, Station Manager
- T. B. Owen, Superintendent, Maintenance
- J. N. Pope, Superintendent, Operations
R. J. Brackett, Senior QA (Quality Assurance) Engineer
- R. H. Ledford, QA Technical Support Supervisor
W. R. Hunt, ISI Coordinator
J. M. Crowe, Technical Support QA
C. R. Hensen, Welding /NDE (Nondestructive Examination) Inspector QC
(Quality Control)
- T. C. Matthews, Compliance
Other Organizations
Babcock-and Wilcox (B&W), Special Products and Integrated Field Services
W. J. Persinger, ISI Coordinator Level II Examiner
R. A. Mechalski, Supervisor, ARIS Operations
Bruce Goranowski, Level II U/T (Ultrasonic Test) Examiner
R. G. McMillan, Level II U/T Examiner
NRC Resident Inspectors
- J. C. Bryant, Senior Resident Inspector
- K. Sasser, Resident Inspector
- L. King, Resident Inspector
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on March 21,1985, with
those persons indicated in paragraph 1 above. The inspector described the
areas inspected and discussed in detail the inspection findings listed
below. No dissenting comments were received from the licensee.
(0 pen) Violation 270/85-06-01, Failure to implement design specification
requirements, paragraph 6.
The licensee did not identify as proprietary any of the materials provided
to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters
Not inspected.
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4.
Unresolved Items
Unresolved items were not identified during this inspection.
5.
Inspector Followup Items (IFI)
(Closed) 269/83-19-01, Core Barrel Bolt Calibration Block Certifications and
Thermal History
The licensee provided a written response from B&W's Level II U/T Examiner
addressing this matter. The inspector reviewed the submittal and found that
the information provided in the material certification along with the above
mentioned submittal demonstrate the calibration block and material from
which it was produced were adequate for the job.
(Closed) 269/84-27-01, U/T Level III Approval for QCL-13, QCL-14, and QCL-15
U/T NDE Procedure
The licensee provided revised copies of the subject procedures with
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Level III Examiner approval indicated.
(Closed) 269/84-27-01, Adequate Preservation and Storage of U/T Calibration
Blocks
The licensee has designed a fixture which protects calibration blocks
against damage while providing easy access for calibration and is suitable
for storage purposes between fuel outages.
(Closed) 287/84-10-01, Corrective Measures on Nonconforming Items (NCIs)
1031'and 1033
This IFI was identified when a review of subject NCIs disclosed that certain
Code violations had occurred during the repair of reactor coolant pump 3Al
bolting ring (flange). These violations included failure to apply preheat
prior to welding and failure to perform NDE (surface examination) upon
completion of the weld repair.
The licensee provided for review the resolution to subject NCIs, and the
justification for leaving the flange as-is. The justification was based on
results of a U/T examination performed by B&W and stress analysis by
Dominion Engineering.
Results of the U/T examination showed no detectable
cracking and the stress analysis calculations showed the repaired section
was under compression and therefore not subject to cracking.
6.
Independent Inspection Effort, Unit 2(92706)
At the time of this inspection, work on replacement of the main feedwater
flow nozzles was complete. The inspector observed the completed welds #85,
- 86, #87, and #88 on 150-16, Rev.19, which had been approved on March 8,
1985, by Station Engineering and QA. This portion of the system has been
classified as Class G, and would normally be under ANSI B31.1 requirements;
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however, the licensee elected to invoke ASME Section III, Class 3 require-
ments for the installation of piping. Discussions held with cognizant QA/QC
personnel on the fabrication, inspection and testing of these welds
disclosed that, although the ASME Code had been invoked, none of the Code
required inspections were performed. That is, there was no issuance of weld
cards, or miscellaneous NDE forms (QCI-1A), QA did not perform fitup
inspections, or final visual. Also, there was no objective evidence to
verify that the appropriate preheat temperature was attained and that
interpass temperature requirements were adhered to.
Further discussions
disclosed that the decision to install the piping under ASME Code require-
ments was based on the fact that under this Code, postweld thermal treatment
(stress relief) was not required, instead radiography could be used as the
acceptance criterion to verify weld integrity.
It is the inspector's
understanding that the licensee's reasoning for not generating the appro-
priate forms and documenting / performing the required inspections was based
on the fact that this piping was classified as part of a Class G system and
therefore subject to ANSI B31.3 requirements which do not require this type
of documentation.
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In response, the inspector's position was that, in so far as this modifica-
tion was concerned, electing to invoke ASME Section III Class 3 requirements
gave this Code and its requirements precedence over ANSI B31.1 Code and,
therefore, the documents and inspections required by ASME Section III Class
3 should have been adhered to. Moreover, the inspector stated that failure
to assure that the appropriate forms had been issued and QA inspection
requirements determined and implemen+ed indicates an apparent flaw in the
QA/QC program which permitted the welds to be fabricated without the
required inspections being performed and two of the four welds being radio-
graphed before issuing a nonconformance for failure to follow Code require-
ments.
In a similar event involving repair of reactor coolant pump 3A1,
identified as Inspector Followup Item (IFI) 287/84-10-01 and discussed in
paragraph 5 of this report - a failure to apply preheat and perform surface
examination subsequent to welding went undetected until after the pump had
been assembled.
This failure to determine inspection requirements affecting quality prior to
implementation of the modification is in violation of 10 CFR 50, Appendix B,
Criterion III as implemented by Duke-1-A, Section 17.2.3.
This violation
was identified as 270/85-06-01, Failure to implement design specification
requirements.
7.
Inservice Inspection - Observation of Work Activities (Unit 2)
The inspector observed the ISI activities described below to determine
whether these activities were being performed in accordance with regulatory
requirements and licensee procedures.
The applicable code for the ISI is
the ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition, with
Addenda through the Winter of 1980.
a.
Personnel qualification records for two Level II examiners were
reviewed.
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b.
The inspector observed the in process UT inspection of the following
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Reactor Vessel Head
B01.021.001
0* to 120' closure head cap to
closure head ring
B01.040.001
0* to 120' closure head flange to
closure head ring
Core Flood Tank 2CF-TIA
C1.02.003/
Pump valve
O' to 360'
E05/001.001
flange to
head weld
The inspection was compared with applicable procedures in the following
areas:
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(1) Availability of and compliance with approved NDE procedures
(2) Use of knowledgeable NDE personnel
(3) Use of NDE personnel qualified to the proper level
(4) Recording of inspection results
, 5) Type of apparatus used
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(6) Extent of coverage of volume
(7) Calibration requirements
(8) Search units
(9) Beam angles
(10) DAC curves
(11) Reference level for monitoring discontinuities
(12) Method for demonstrating penetration
(13) Limits for evaluating and recording indications
(14) Recording significant indications
(15) Acceptance limits
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8.
Inservice Inspection, Data Review and Evaluation, Unit 2(73755)
Records of completed nondestructive examinations were selected and reviewed
to ascertain whether: the method (s), technique and extent of the examination
complied with the ISI plant and applicable NDE procedures; findings were
properly recorded and evaluated by qualified personnel; programmatic devia-
tions were recorded as required; personnel, instruments, calibrations blocks
and NOE materials (penetrants, couplets) were designated and qualifications /
certifications were on file.
The applicable Code for this activity was
discussed in the paragraph above. Records selected for this review were as
follows:
Radiographs
C05.021.054
2-03-FWD 64-C
14"x.750"
C05.021.055
2-03-18.2-36
20"x1.03"
C05.021.070
2-03-18.1-22B
24"x1.219"
- E04.01.001A
Nozzle for Pump
Thermal sleeve
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2-Al
- E04.01.003
Nozzle for Pump
Thermal sleeve
2-B1
- Radiographs showed both thermal sleeves were in position.
Weld C05.021.070 had been fabricated with a backing ring and the original
radiographs taken in March 1982, depicted burn-through in the 0-1 and 3-4
stations resulting in a violation of minimum wall acceptance criterion. The
weld condition was evaluated by Duke Power Company Design and the plant was
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permitted to resume operation with the weld in the as-is condition with the
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provision that it (weld) would be repaired when valve 2-FDW-46 adjacent to
the weld was disassembled on a regular refueling outage. Discussions with
cognizant licensee representatives disclosed that there were no plans to
repair the weld during this outage.
However, the inspector expressed
concerns over leaving the weld in its present condition and postponing its
repair for another refueling cycle when the physical appearance of the
defect, and the soundness of the affected material were unknown. Subsequent
to the close of this inspection, the licensee informed the inspector that it
had been decided to repair the weld in question during the current outage.
Ultrasonic Examination
B09.011.066
A Hot Leg, Circle Seam
42.75"x3.00"
B09.012.044
A Hot Leg Outside Long
33.5"x3.00"
Seam
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B09.012.046
A Hot Leg Outside Long
33.5"x3.00"
Seam
809.012.043
A Hot Leg Inside Long
33.5"x3.00"
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Seam
809.012.045
A Hot Leg Inside Long
33.5"x3.00"
Seam
805.05.002A
A 1 Discharge Pump S. E.
To Elbow
B05.05.002
A 1 Discharge Pump S. E,
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To Elbow
C01.03.004
S/G "B" Shell to Lower
Tube Sheet
E4.01.001
A 1 Discharge Make-up
Nozzle S. E.
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270' Outlook Nozzle Z to Shell; From Nozzle ID (ARIS)
B03.090.002A
B03.100.002
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B09.011.069
90' Outlet Nozzle to Shell; From Nozzle ID (ARIS)
B03.090.001A
B03.100.001
809.011.057
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805.051.002A
B05.050.00BB
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CO2.010.003
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C05.011.033
2-538-19.1-59
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Within the areas inspected, no violations or deviations were identified.
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