IR 05000397/1981020
| ML17276A169 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/23/1981 |
| From: | Dodds R, Haist D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17276A167 | List: |
| References | |
| 50-397-81-20, NUDOCS 8111050681 | |
| Download: ML17276A169 (8) | |
Text
Report No. 50-397 81-20 Docket No. 50-397 Licensee:
Wa hi t n P b
'
968 U. S.
NUCLEAR REGULATORY CONMISSION OFFICE OF INSPECTION AND ENFORCEtlENT REGION V
License No.
Safeguards Group Faci1ity Name:
Inspection at:
Inspection conducted:
Inspectors:
D. P.
H ist, Reactor Inspector Date S gned Date S gne Approved by:
R. T.
Dod s, Chief, Reactor Projects Section No.
Reactor Construction Projects Branch Summary:
Ins ection on Se tember 14-18 1981 Re ort No. 50-397 81-20 ate S gne Areas Ins ected:
Routine, unannounced inspection by regional based inspector o
qua sty records generated by the preservice inspection contractors.
The inspection activities invo1ved 13 inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
Siii0506Si Sii026 PDR ADQCK 05000397
PDR RV Form 219 (2)
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1n DETAILS':
'I Persons Contacted a.
Washin ton Public Po'wer'Su
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Crisp, Deputy Project Manager", 'Constructi'on,'"
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- R. Johnson, Project;,gual.ity'ssurance'an'ager
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R. Krowlicki,Senior,'goal ity','s'surcance'Engineer'.,'"-'evel III D. Ramey, Lead gSI 'En'giyeer..
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Welch, Maintenance Specialist T. Hoyle, Supervisor"-, Genereation" Eiigineeriqg'.
Burns and Roe Inc.
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- H. R. Tuthill, gual;ity Assurance Supervisor."
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Lambert - Mac ill - Thomas LMT Inc.,
E. Wood, Level III d.
Bechtel Power Cor oration
- M. Jacobson, Project guality Assurance Engineer E
- Denotes those attending the exit interview on September 18, 1981.
2.
Preservice Ins ection
'a e Data Review and Evaluation The inspector examined the organization and storage of nondestructive examination records for pr eservice examination activities.
The records system provides for ready retrieval of examination records for each ASME Section XI Code category and item number.
Data from the manual ultrasonic examination of the reactor vessel is contained in a separ ate report.
The inspector examined the following records which document various portions of the preservice examination:
Examination 1977 Preservice Examination of WNP-2 Boiling Water Reactor Final Report, April 1977
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Manual ultrasoni c examination of reactor vessel at sit "hi'>- f"
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Magnetic particle examination No items of noncompliance or deviations were identified.
Manual reactor vessel examination data was taken in compliance with the ASME Code Section XI, Appendix I 1974 Edition including addenda through Summer 1976 without conflict with the 1971 Edition of ASME XI including Winter, 1971 addenda.
The acceptance criteria was based on recording and evaluation of data in accordance with the 1971 Edition through Winter, 1971 Addenda with an additional data evaluation to the 1974 Edition through Summer, 1976 Addenda for information.
The inspector indicated to the licensee that the Sumer, 1976 addenda to ASME Section XI has not been approved for use in 10 CFR 50.55a and that an explanation of the impact of its use will be required in the final preservice examination report.
Licensee representatives committed to address this issue in the Final Report.
The inspector noted that a completed Form NIS-1 "Owner's Data Report for Inservice Inspections" had not been completed and attested by the authorized inspector for the manual reactor vessel examinations.
The licensee comitted to ensure that the proper attestations are included in the Final Report of Pr eservice Examination for WNP-2.
Licensee representatives reported that the mechanized device to be used for examination of circumferential and longitudinal vessel shell welds was damaged when it disengaged from the pole track and fell to the floor.
The licensee has not yet determined the failure mechanism but plans to repeat the examination with the mechanized device tethered.
The failure mode will be determined prior to completion of the mechanized examinations,
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The inspector examined;the results of initial efforts to correlate manual and mechanized reactors'vessel examinations.
The licensee has compared spot-type indications resultin~ from mid-plate segregates in the base metal arou'nd the nozzle N2A (30 ),nozzle-to-vessel weld during the base metal
scans.
The manual examination had disclosed 21 indications.
The mechanized examination disclosed 120 indications.
The difference i'n these results can be attributed to (1) the indications were recorded during the manual examination when the indication signal reached the amplitude of the remaining back reflection, whereas the indications were recorded during the mechanical examination whenever the signal exceeded 20K of full screen height and (2) mid plate segregates are spot-type reflectors and are difficult to reproduce.
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to 170 around the nozzle by both methods.
The licensee will continue efforts to establish correlation between manual and mechanized methods on reflectors which exhibit some definite size.
These efforts will be examined during subsequent inspections.
The inspector questioned the ability of the mechanized equipment to traverse vessel shell thickness transitions without loss of coupling.
The licensee committed to examine this aspect of operations during the mechanized examinations.
The inspector noted that mechanized examination procedures had not been provided to licensee site personnel.
The licensee committed to correct this situation within one week.
No items of noncompliance or deviations were identified.
3.
Mana ement Meetin A meeting was held with the Project guality Assur ance Manager at the conclusion of the inspection on September 18, 1981.
The scope and findings of the inspection were discussed.
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