IR 05000346/1990006
| ML20043B415 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/23/1990 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20043B414 | List: |
| References | |
| 50-346-90-06, 50-346-90-6, NUDOCS 9005300003 | |
| Download: ML20043B415 (6) | |
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- D V. S. NUCLEAR REGULATORY COMMISSION REGION 111
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ReportNo.'50-346/90006(DRS)
Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company Edison Plaza 300 Edison Plaza Toledo, OH 43652 Facility Name: Davis-Besse Nuclear Power Station Irispection At: Davis-Besse Site, Oak Harbor, OH 43449 Inspection Conducted: April 9-12, and May 14-16, 1990 Inspector: k M [d JMVro K. D. Ward Date Approved By e vm fMJ/9c D. fl Danthlson, Chief V Date te ( and Processes Section Inspection Summary inspection on April 9-12, and May 14-16,1990(ReportNo. 50-346/90006(0RS))
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Areas Inspected':
Routine, unannounced safety inspection of inservice inspection (151) activities including review of program (73051), procedures (73052), observation o' work activities (73753), data review (73755), and modifications (37701).
j Results: No violations or deviations were identified.
Based on the results
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of the inspection, the NRC inspector noted the following:
The inservice inspection program was adequately planned with appropriate
priorities assigned by the licensee.
The remote ultrasonic examination of the reactor vessel was performed
by qualified personnel and found to be acceptable.
The HPl/ Makeup Nozzle program was completed using well stated and defined
procedures.
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DETAILS 1.
Persons Contacted ToledoEdison(TE)
- E. Caba, Performance Engineer Manager
- A. Rabe, Quality Verification
- G. Homma, Compliance Supervisor
- M. Shepherd, Senior Performance Engineering Advisor
- R. Gaston, Licensing Technologist M. Parker, Performance Supervisor P. Smith, Nuclear Licensing Supervisor S. Singer, 151 Technologist U. S. Nuclear Regulatory Commission (U. S. NRC)
- P. Byron, Senior Resident inspector D. Kosloff, Resident inspector K. Walton, Resident inspector Hartford Steam Boiler inspection and Insurance Company (HSB)
M. Ferguson, ANil The NRC inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit interview on May 16, 1990.
2.
InserviceInspection(151)
a.
Review of Program (73051)
Babcock and Wilcox (B&W) personnel performed the 151 program in accordance with ASME Section XI, 1977 Edition, Summer 1978 Addenda.
There was sufficient organizational staff to ensure that acceptable 151 work was performed. Where ASME requirements were determined to be impractical, specific relief requests were submitted to NRR in writing. The NRC inspector reviewed the specific telief requests including the requested correspondence between the licensee and the NRC.
The NRC inspector reviewed audits /surveillances of ISI activities conducted by qualified personnel to verify compliance with the 151 program, b.
Review of Procedures (73052)
All applicable ISI procedures were approved by the ANil and were reviewed by the NRC inspector. Manual pulse echo detection instruments and transducers of various angles, sizes, and MHz were used. The nondestructive examinations (NDE) were performed in accordance with ASME Section V, 1977 Edition, Summer 1978 Addenda.
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Data Review (73755)
' General
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The. data for the following examinations was wit.hin the criteria
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<as-outlined in the applicable NDE procedures and ASME Code requirements.- -
The NRC inspector's review included; examination of documents relating p-
-to NDE equipment, data' and evaluations.
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Eddy Current Examinations (ET)
- The ET covered ~100% of all; accessible tubing within the steam n
generators using the MlZ 18A and the 360_ probe. The results-
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.were as follows:
L Steam-Tubes Plugged Total Tubes
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Generator This Outage Plugged li h
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45
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B
16
- All of the new steam _ generator tube plugs were -type W Inconel
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- 690..Also, 19 Inconel #600 upper tube sheet rolled plugs were.
replaced with type W Inconel 690_ plugs.
No sleeving has ever been performed.
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Pressurizer Manway Studs and Nuts Replacement b
b LDuring the' magnetic particle examinations of the studs, two studs
'were found to be unacceptable. TE replaced all 12 studs and nuts
with ASTM SA 320, Grade L43, material.
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. Inspection of Reactor Vessel F
Due to high radiation of the reactor vessel, the ultrasonic examination was performed by B&W remotely)via the Automated
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Reactor Vessel Inspection; System (ARIS 11. This activity -
P completed the_ ten-year ultrasonic examination of the vessel.
The ARIS 11 inspected the remaining 75% of the nozzle to shell
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welds, b
d.
Observation of Work Activities (73753)
i The NRC inspector observed work and had discussions with personnel.
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g during the observation of ISI activities. These observations included the
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following:-
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'(1) A.QA individual performing'his ISI related duties.
-(2).. A B&W individual performing a liquid penetrant examination on seismic restraint attachment weld fHCB-002-11031, 150
- 1SI-233A.
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(3) A B&W individual performing sisual examinations on hangers HCB-002-H031, 150 flSI-233A and HCB-002-H006, 150 #1SI-233A.
(4) A B&W individual performing ultrasonic examinations on weld
- EBB-004-007-FW52, 150# 206N.
The NRC inspector reviewed the qualifications and certifications of all inspection personnel on site to ensure conformance with SNT-TC-1A.
No violations or deviations were identified.
3.
HPl/ Makeup Hozzle Program (37701)
a.
Demonstration of Flaw Detection Capability on the Core Flood Hozzle to Safe-End Weld The NRC observed the flaw detection demonstration performed by B&W Special Products and Integrated Field Services (SPIS), Lynchburg, Virginia, on August 8, 1989.
In order to determine the opposite surface flaw detection capabilitiet, B&W fabricated a standard containing a series of axial circumferential EDM notches ranging in depth from 0.024" to 0.353".
The standard was fabricated duplicating the inlet / outlet nozzle base and weld materials and welding process.
This block was submerged in water to simulate the actual field application and was subsequently scanned with a contact 45 L-wave dual element transducer.
The test demonstration performed at the B&W Lynchburg facility utilized the PUMA robot in lieu of ARIS to scan the test standard.
The PUMA robot manipulator simulates the ARIS scanning motions.
Examination criteria such as scan direction and transducer were duplicated to the actual examination which will be performed with ARIS.
Scanning was performed in both the circumferential and axial directions to detect the EDM notches.
Data was acquired and analyzed using the B&W ACCUSONEX System.
The ultrasonic test instrument was calibrated using side drilled holes to establish a Distance Amplitude Correction Curve (DAC).
The gain was set to 24dB above the calibration gain. Data was collected above a threshold value set to 20% of full screen height.
Results of the test demonstration confirmed that opposite surface reflectors ranging from.92% (0.024") to 13.6% (0.353") through wall were detected.
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b.
Examination of Nozzles HP-59 and HP-58 The following are the results of the UT examinations performed:
HP-59 (Nozzle A1)
No service induced flaws detected.
Small volumetric inclusions were detected in nozzle to pipe
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weld. Three were recordable (greater than 20% DAC) - all were acceptable to ASME Section XI standards.
Base metal and clad thickness measuren+,cs were performed for
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use in the fracture mechanics analysis.
HP-58(NozzleA2)
No service induced flaws detected.
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Small volumetric inclusions were detected in nozzle to pipe
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welds. Four were recordable (greater than 20% DAC) - all were acceptable to ASME Section XI standards.
Dase metal and clad thickness measurements were per%rmed.
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The NRC inspector followed the HPI thermal sleeve modification / replacement (see NRC Inspection Report No.
50-346/88009(DRS)) and UT examinations performed during this outage.
No violations or deviations were identified.
c.
Presentation to NRC/NRR A final presentation by B&W and TE was given to NRR on May 10, 1990, it was demonstrated that the UT technique utilized for the nozzle inspection could reliably detect flaws in excess of 1/8" depth into a
the base material. A supporting fracture mechanics analysis
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concluded that flaws less than 1/8" were essentially stable and that flaw growth was not an issue.
Feed and Bleed Modification (37701)
Reference: HRC Inspection Reports No. 50-346/88005(DRS)andNo.
50-346/88009(DRS).
TE committed tu the NRC to modify the power operated relief valve, makeup system and supporting auxiliaries to provide enhanced feed and bleed capability. The final system additions and changes were made this outage. They will provide essential component cooling water to the makeup pumps so that they will remain operable after a loss of offsite power. The system will then continue to function.af ter a single failure.
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=The NRC inspector reviewed NDE and welding reports and other related-documents and found them to be acceptable.
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'No violations or deviations were identified.
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Exit' interview (30703)-
The NRC inspector met with licensee representatives (denoted in Paragraph'
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L1) at the conclusion of the inspection on May 16._1990.
The NRC' inspector
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summarized.the scope.and' findings ofuthe_ inspection noted in this report.
The NRC inspector also discussed ~the likely informational content of the'
inspection. report:with regard to documents or processes reviewed by the
.NRC inspector during the inspection. :The licensee did not-identify.any-si such' documents or processes as proprietary.
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