IR 05000247/1979011
| ML19254E647 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/05/1979 |
| From: | Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254E645 | List: |
| References | |
| 50-247-79-11, NUDOCS 7911020120 | |
| Download: ML19254E647 (8) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-247/79-l'
Docket No.
50-247 License No. DPR-26 Priority Category e
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Licensee:
Consolidated Edison Company of New York, Inc.
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4 Irving Place New York, New York 10003
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Facility Name: Indian Point Nuclear Generating Station, Unit 2 Inspection at:
Buchanan, New York Inspection conducted:
June 20-22 and Ju?y 23-27, 1979 Inspectors:
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R.A.McBrearty,Reacto/ Inspector ate signed date signed date signed Approved by:
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!N (d..E. Trip /,' Chief,EngineeringSupport
' date signed Section No. 1, RC&ES Branch
Inscection Summary:
Inspection on June 20-22, 1979 and July 23-27, 1979 (Report No. 50-247/79-11)
Areas Inspected:
Routine, unannounced inspection of the licensee's inservice inspection activities and the eddy current examination of the steam generator tubes. This included review of ISI Program and NDE procedures, observation of work in progress and review of ISI data and eddy current examinat Nn data. The inspection involved 59 inspector-hours onsite by one regional based NRC rn;pector.
Results: No items of noncompliance were identified.
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Region I Form 12 791102 0 / h O (Rev. April 77)
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DETAILS 1.
Persons Contacted Consolidated Edison Company of New York, Inc.
- W. Ferreira, QA Engineer
- L. J. Kawula, Acting Plant Manager R. LaBott, Senior Engineer, Metallurgical Group
- J. M. Makepeace, Technical Engineering Director, NPG
- W. A. Monti, Manager, NPG
- J.
L. Schwartz, ISI & Files Coordinator
- G. Wasilenko, Manager, QA Others
- T. Rebelowski, Resident Reactor Inspector, USNRC
- denotes those present at the axit interview.
- contacted by telephone.
2.
Inservice Inspection (ISI) Activi'ies a.
ISI Program The examinations scheduled for the current refueling outage initiate the second 40 month period of the first 10 year interval for inservice inspection at Indian Point, Unit 2.
The program has been revised as required by 10 CFR 50.55a(g) and is intended to meet the requirements of the ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition through Summer 1975 Addenda with exceptions which are stated in the program. The revised program has been submitted to the NRC for review and approval.
b.
Nondestructive Examination (NDE) Procedure Review The inspector selected the following NDE procedures for review to ascertain compliance with ASME code requirements and technical ade-quacy:
ISI 5, Revision 12," Manual Ultrasonic Examination of Circumferen-
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tial and Longitudinal Butt Welds" 1260 025
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ISI 8, Revision 7, " Visual Examination Procedu"r"
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ISI 11, Revision 9 " Liquid Penetrr.nt Examination Procedure"
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ISI 15, Revision 6, " Ultrasonic Examination of Studs, Bolts
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and Nuts" ISI 47, Revision 2," Manual Ultrasonic Examination of Circumferential and Logitudinal Butt Welds in Ferritic Vessels 2 1/2 inches Thick
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and Greater" ISI 205, Revision 2, " Manual Ultrasonic Examination of Full
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Penetration Circumferential and Longitudinal Butt Nelds" The inspector's review for technical adequacy included, but was not limited to, the parameters 'iisted below for the ultrasonic and liquid penetrant examination techniques:
Ultrasonic Exam _inations (a) The type of apparatus including frequency range is specified.
(b) The extent of coverage including beam angles and scanning surface is specified.
(c) Calibration requirements including frequency and size of transducer and calibration reflectors are specified and consistent with the applicable ASME code.
(d) The reference level for monitoring discontinuities is defined and the scanning level is specified and consistant with the applicable ASME code.
(e) Acceptance limits are specified or referenced and are consistent with the applicable ASME code.
Liquid Penetrant Examination (a) The examination method is consistent with ASME code requirements.
(b) Penetrant materials used for nickel base alloys and austenitic stainless steel are required to be analyzed for compliance with allowable residual sulfur and halogen content.
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(c) Examination surface requirements, including temperature limitations, are specified and consistent with ASME code requirements.
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Methods for removal of solvent removable penetrant are specified and consistent with the applicable ASME code.
No items of noncompliance were identified.
c.
Observation of NDE in Progress The inspector observed a portion of the 'titrasonic examination of the following it?ms in order to ascertain compliance with the applicable NDE procedure:
Weld #6, 12" diameter pipe weld in auxilliary coolant line 9
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Weld #7, 12" diameter pipe weld in auxilliary coolant line 9 Reactor vessel studs number 7, 17, 19, 21, 23, 25, 27, 28,
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31, 33, 35, 38, 39 and 41.
The equipment used for the above examinations included a Sonic MARK I flaw detector, serial number 784522.
The vessel studs were examined in accordance with procedure ISI 15, Revision 6, using a 1" diameter, 2.25 MHz straight beae transducer, serial number D17921. The portion of the stud examination observed by the inspector was done from the bottom end of each stud.
The required scan from the top end of each stud was completed at an earlier date.
The fire welds were examined in accordance with procedure ISI 205,iavision 2, using straight beam and angle beam techniques.
The straight beam scan was done with a 5.0 MHz, 0.375" diameter transducer, serial number H24829 and the angle beam scan was done with a 2.25 MHz, 0.5" diameter transducer, serial number H04504, which was fitted with a plastic wedge to produce a 45 degree entry angle in steel.
The stud examinations and the pipe weld examinations were done by a two man team made up of individuals qualified to Level I and Level II.
No items of noncompliance were identified.
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d.
NDE Personnel Qualification and Certification The inspector reviewed qualification and certification records for the individuals who performed the ultrasonic examinations listed in paragraph 2.c.
The records indicated that the NDE personnel were properly qualified and certified in accordance with the applicable sections of SNT-TC-1A, the governing document.
No items of noncompliance were identified.
e.
ISI Data Review The inspector reviewed selected NDE data sheets to ascertain that examinatOn results, calibration data and other required information was properly recorded on those sheets.
The following data sheets were selected for review:
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Studs, Bolts and Nuts Ultrasonic Examination Report, dated July 20, 1979 for RPV studs number 7, 17, 19, 21, 23, 25, 27, 28, 31, 33, 35, 38, 39 and 41 - scan from top end of studs and scan of associated nuts
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Weld 01..asonic Examination Sheet, dated July 24, 1979, fc.-
weld #10 and #11 in 14" diameter RHR line 57
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Weld Ultrasonic Examination Sheet, dated July 24,1979, for penetrant examination of support weld #H3 (SlH58) in 14" diameter RHR line 57.
The inspector found that the data sheets contained the required infomation based on the NDE method used.
No items of noncompliance were identified.
f.
Disposition of ISI Findings The inspector reviewed records associated with the evaluation and disposition of ISI findings during the current refueling outage.
The following Quality Control Inspection Reports (QCIR) were reviewed:
QCIR #79-2-42, dated July 9, IT 9
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QCIR #79-2-39, dated July 7, 1979
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QCIR #79-2-38, dated July 3,1979
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QCIR #79-2-54, dated July 23, 1979
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The inspector found that the above reports were in the licensee's review process and no dispositior. was mada at the time of this inspection. The inspector stated that this item would be reviewed during a subsequent inspection.
3.
Eddy Current Examination of Steam Generator Tubing The steam generator inspection planned for the 1979 refueling outage includes the eddy current e.2mination of selected tubes in all four of the Indian Point Unit 2 steam generators.
a.
Review of Implementing Procedures The inspector re'tiewed the following:
Specification No. QA-7601, Revision 1. " Eddy Current Examination
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of Incore Steam Generator Tubing" Amendment No. 1 to QA-7001
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Amendment No. 2 to QA-7601
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The inspector's review of the above included, but was not limited to, the following parameters:
A two channel examination unit is specified
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Criterion have been established for maximum sensitivity
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The method of examination is described
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Methods of calibration and calibration sequence is described
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Compilation of required examination records is specified
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No items of noncompliance were identified.
b.
Observation of Examination in Progress The inspector observed the eddy current examination of the following tubes in steam generator number 24:
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Row _
Column Row Co_lumn
3
6
4
7
5
9
10
53
12
55
13 The above listed tubes were examined for defects and for denting by one pass of the eddy current probe through each tube.
Data were collected for each type of examination by the use of a switching device which permitted simultaneous routing of the electronic signal to each of two sets of recording equipment.
Each set of equipment was individually calibrated for the type of data being recorded.
The examinations were conducted using a 700 mil probe at a frequency of 400 KHz.
Data were recorded as the probe was withdrawn from the tube under examination. The inspector noted that unusual conditions, such as obstruction of the probe in a particular tube were entered on the recording FM tape by voice. The inspector observed that tube identificati;n was entered on the strip charts and that system calibration was verified as required by Specification No. QA-7601.
The inspactor found that the examinations were conducted in accordance with the governing procadure and that examination results were properly recorded.
The inspector observed the method for data interpretation and evaluation which was done by three Zetec, Inc. personnel qualified to Level III, Level IIA and Level II, respectively.
The Level III individual evaluated the defect examination data and the denting examination data were evaluated by the Level II individuals.
The equipment used for data interpretation was similar to that used for data collection.
Calibration records associated with the examination and data interpretation equipment were reviewed and found to be complete and current for each piece of equipment.
The licensee stated that a report would be submitted to the NRC of the steam generator inspection results prior to start up of the unit 2 reactor.
No items of noncompliance were identified.
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4.
Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1)
on July 27, 1979, at the conc 10sion of the inspection. The inspector sumarized the purpose and scope of the inspection and the findings.
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