IR 05000455/1989003
| ML20235R985 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/27/1989 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235R973 | List: |
| References | |
| 50-455-89-03, 50-455-89-3, NUDOCS 8903030513 | |
| Download: ML20235R985 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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REGION III
Report No. 50-455/89003(DRS)
Docket No. 50-455 License No. NPF-66 Licensee:
Commonwealth Edison Company l
Post Office Box 767 l
Chicago, IL 60690 l
Facility Name:
Byron Station, Unit 2 Inspection At:
Byron Site, Byron, Illinois
.T.nspection Conducted:
January 18, 24-26, 31, and February 7, 9, 15 and 16, 1989.
hb Inspector:
avin D. Ward M7Nf Date h
Approved By:
D. H. Danielson, Chief M 7/f'9 _
Materials and Processes Section Date Inspection Summary Inspection on January 18, 24-26, 31, and February 7, 9, 15 and 16, 1989 (Report No. 50-455/89003(DRS))
Areas Inspected:
Routine unannounced inspection of inservice inspection (ISI)
activities including review of programs (73051), procedures (73052),
observation of work activities (73753), and data review (73755); modification i
activities (37701); and jacking studs removed from steam generators (73755).
I Results:
No violations or deviations were identified.
Based on the results of the inspection, the inspector noted the following strengths:
The licensee adequately demonstrated the ability to properly implement
the first ISI Program on Unit 2.
Personnel involved in the ISI effort appeared knowledgeable, well l
l trained, and competent.
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Applicable procedures were well stated and workable.
- Management was involved in the ISI activities in an effective manner.
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DETAILS
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1.
Persons Contacted Commonwealth Edison Company (Ceco)
- R. Pleniewicz,' Station Manager
- D. Winchester, QA Superintendent
- R. Flahive, Technical Staff Supervisor
- M. Snow, Regulatory Assurance Supervisor i
- J. Harkness, Technical Staff, ISI
'*M. Kennedy, Technical Staff, Engineer
- E. Zittle, Regulatory Assurance Staff G. Sorensen, Construction %perintendent E. Wolber, QC Supervisor Nuclear Regulatory Commission (NRC)
- N. Gilles, Resident Inspector P. Brochman, Senior Resident Inspector EBASCO Services (EBASCO)
J. Semgenberger, Supervisor Hunter Corporation (HC)
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D. Redell, Quality Control Weld Inspector Babcock and Wilcox Company (B&W)
R. Rawlings, QC Specialist E. Mayhew, Quality Programs Specialist (Auditor)
K. Hacker, Level III, ET Hartford Steam Boiler Inspection and Insurance Company (HSB)
J. Hendricks, ANII The inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit interview February 16, 1989.
2.
Inservice-Inspection (ISI Unit 2)
a.
Review of Program (73051)
The NRC inspector verified that the licensee's program pertaining to the ISI was complete and conformed to regulatory requirements and the licensee'r commitments.
The program was in accordance with ASME Section XI, 1983 Edition, Summer 1983 Addenda.
There was a sufficient organizational staff, both in number and training,.to
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ensure that acceptable ISI work was performed.
. here ASME W
requirements were determined to be impractical, specific relief from NRR was requested in writing.
The NRC inspector reviewed specific relief requests and related documentation. lThe NRC inspector also reviewed audits / surveillance of ISI activities conducted by qualified QA personnel to verify compliance with the ISI program.
b.
Review of Procedures (73052)
The NRC~ inspector ascertained that the licensee's ISI procedures adequately covered all required aspects of the approved ISI program.
All ISI procedures were approved by the ANII and reviewed
.by the NRC inspector.
The methods of ultrasonic (UT), magnetic particle (MT), liquid penetrant (PT), visual (VT), and eddy current (ET) examinations and techniques were adequately described and in conformance to the requirements and guidance of ASME Section V, 1983 Edition, Summer 1983 Addenda.
c.
Data Review and Evaluation (73755)
The NRC inspector ascertained that the reported data covered the scope of the examinations required during this inspection period as described in the ASME Code, technical specifications, and the ISI program.
This included the review of documents' relating to UT, MT, PT, VT, and ET equipment, data, and-evaluations. 'The NRC.
inspector reviewed the ET reports and the results were as follows:
j Steam Tubes Plugged Tubes Plugged Total Tubes Generator This Outage Previously Plugged 2A
'4
2B
2
2C
4
2D
1
TOTAL II II T2
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l The examination data was within the acceptable criteria as outlined
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in the applicable NDE procedures and Code requirements.
d.
Observation of Work and Work Activities (73753)
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The NRC inspector verified that the.following ISI was performed in accordance with the technical specifications, licensee procedures and the applicable ASME Codes:-
l (1) Ebasco personnel performing MT on LNe No. 2FW81AA-6", Weld No. C-4.
(2) Ebasco personnel performing calibrations and UT on Line No. 2FW86AA-16", Weld No. C-1, and on Line No. 2FW81AA-6",
Weld No. C-4.
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(3) Ebasco personnel performing PT on Line No. 2CVA7AA-2", Weld No. W-1.
(4) B&W personnel performing UT on the fuel assemblies and also performing UT using automated equipment on the "A" and
"D" reactor vessel nozzle welds.
(5) B&W personnel performing ET on several steam generator tubes.
(6) B&W personnel using the following equipment for the evaluation of ET data from the steam generator tubes:
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(a) The Zetec Model DDA-4 analysis equipment.
(b) Automated data screening equipment.
(c) Data management software system.
(7) During the ISI activities, Weld No. W-1, Line No. 2CVA7AA-2, was PT'd and found to be unacceptable.
The unacceptable weld area was blended, re-examined and found to be acceptable.
The NRC inspector observed the PT and reviewed the traveler, PT report, and other related NDE documentation to ensure conformance with ASME Section XI requirements and the approved ISI program.
The NRC inspector reviewed the qualifications and certifications of all inspection personnel on site in accordance with SNT-TC-1A.
i Several personnel were trained and qualified by EPRI in detecting intergranular stress corrosion cracking.
3.
Jacking Studs Removed From Steam Generators (73755)
During the sludge lancing reinspection of the steam generators (SGs),
two jacking studs were found and removed.
In SG 2B one stud was found next to the blow down line on the tube sheet and removed through a sludge lancing port that was enlarged from 2" to 2.3".
In SG 2D a stud was also found next to the blow down line on the tube sheet and removed from the opposite side where there was an enlarged sludge lancing port.
This enlarged sludge lancing port was made when a jacking stud was found during preservice inspection.
Westinghouse and CECO believe that all foreign objects have now been removed.
Eddy current examinations showed no damage to the tubes by these studs.
One hundred percent eddy current examinations were made on all four SGs.
Westinghouse and CECO concluded that the two studs were fabrication " remnants" and were never installed or intended to be installed in any of the SGs.
The dimensions (2 " x 3") and material (carbon steel) conk. n to the type of jacking studs used during the wrapper barrel and support plate structuring of the SGs. The particular studs required for assembly of the SGs were nominally 3/4" longer with a 3/4" longer threaded length than the jacking studs extracted.
No weldment material was found on the stud shank, head, toe, or threads as required by the normal fabrication
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sequence, indicating that the studs were fabrication remnants. The
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jacking stud remnants had noticeable oxidation and rust. Since the
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foreign objects were found and removed from the SGs during planned inservice inspections, Westinghouse and CECO concluded that no further action was required.
The NRC inspector reviewed the program, procedure, and data and visually examined the two jacking studs that were found and removed.
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No violations or deviations were identified.
4.
Facility Modification (37701) -- Addition of Nitrogen Charging / Pressure Testing Manifolds to each of the Main Steam Isolation Valve Nitrogen Accumulators.
The purpose of this modification was to reduce the difficulty and eliminate the hazard associated with the surveillance, maintenance, and charging of the Unit 2 main steam isolation valve (MSIV) nitrogen accumulators. The modification provides individual nitrogen charging / pressure testing i
manifolds for each MSIV. Each manifold consists of two pressure gauges for verifying proper precharge pressure, nitrogen charging taps,
accumulator supply piping with flexible hose connections and pipe supports.
j A nitrogen supply line runs from the nitrogen bottle station through the i
main steam tunnel to the Unit 2 safety valve rooms.
This nitrogen supply can be used to charge the MSIV nitrogen accumulators or other valve
accumulators in the area by utilizing temporary piping and appropriate regulating valves.
Piping added to the safety valve rooms was seismically designed and supported.
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This modification was performed in accordance with ANSI B31.1, 1973 Edition, i
Summer 1975 Addenda.
The NRC inspector reviewed the 10 CFR 50.59 safety evaluation report, drawings, procedures, and NDE and welding related documentation. The NRC inspector observed welding and a selected portion of the installation, including fit-ups being checked by a Hunter QC inspector.
The NRC inspector also visually examined numerous completed
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No violations or deviations were identified.
5.
Exit Interview (30703)
I The inspector met with site representatives (denoted in Paragraph 1) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report.
The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection.
The licensee did not identify any such documents / processes j
as proprietary.
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