IR 05000029/1978018
| ML19270F001 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/24/1978 |
| From: | Ebneter S, Sanders W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19270E998 | List: |
| References | |
| 50-029-78-18, 50-29-78-18, NUDOCS 7901100470 | |
| Download: ML19270F001 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. c;n-?o /79-1 R Docket No. 50-29 License No. DPR-3 Priority Category C
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Licensee:
Yankee Atomic Electric Company 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name:
Yankee Atomic Power Plant Inspection at:
Rowe, Massachusetts Inspection conducted: October 30 - November 3, 6-9, 1978 Inspectors:
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/979 W. F. Sanders, Reactor Inspector date signed date signed date signed Approved by:
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S.D.Ebneter, Chief,En@neeri6gSuppo date si'gned Section #1, RC & ES Branch Inspection Summary:
Inspection on October 30 - November 3, 6-9,1978 (Report No. 50-29/78-18)
Areas Inspected: Routine, unannounced inspection of inservice activities, modification of oost LOCA recirculation system and eddy current examination of Steam Generator tubing.
The inspection involved 44.5 inspector-hours on site by one regional based NRC inspector.
Resul ts : Of the three areas inspected, no items of noncompliance or deviations were identified.
7 9 0110 0t70 Region I Form 12 (Rev. April 77)
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DETAILS
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1.
Persons Contacted
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Principal Licensee Employees
- Mr. H. Autio - Plant Superintendent YR
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- Mr. R. Aron - Technical Assistant YR
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Mr. S. Durfee - Maintenance Supervisor YR Mr. M. Ebert - Plant Reactor Engineer YR
- Mr. J. Lance - N.S.D. ISI Co-ordinator Y
- Mr. R. Laroue - Operations Quality Assurance Department Y
- Mr. L. Reed - Operations Quality Assurance Department Y
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Mr. R. Randall - ISI Co-ordinator YR
- Mr. J. Staub - Technical Assistant to Plant Superintendent YR
- Mr. N. St. Laurent - Assistant Plant Superintendent YR
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Nuclear Engineering Services
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R. Taylor - Site Supervisor
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Hartford Steam Boiler Inspection and Insurance Company
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W. Niedzwiecki - Authorized Nuclear Inspector
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- denotes those present at the exit interview.
2.
Plant Tour u
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During the course of the inspection, four general inspection tours were made to observe the work and test activities in progress, completed work and status of work and testing in several areas of the plant.
The inspector examined work and test items for any obvious defects or noncompliance with regulatory requirements.
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3.
Inservice Inspection Procram The inspector reviewed the inservice inspection program developed by the licensee to comply with the requirements of ASME B&PV Section XI code,1974 edition through Summer 1975 addenda, the governing requirement, pursuant to the requirements of the code of Federal
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Regulations Title 10 Part 50.55a.
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The Inservice inspection program for the forty month period stirting
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March 1,1978 through June 20, 1981 is the second period (40 months)
of the second interval and includes the following systems and
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components.
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Quality Group Class 1 Components Quality Group Class 2 Componcnts Quality Group Class 3 Components Pump Testing Value Testing Pursuant to 10 CFR 50.55a (8)(5), the licensee had submitted the current ISI program to the NRC and has requested relief from con-formance with certain code requirements which were determined to be inaccessable or impractical. An interim approval of this program has been given, pending a detail review by NRC, division of operating reactors (DOR).
During the review of the ':censee's program and its implementation, no substantive differences were noted.
4.
Eddy Current Examination of Steam Generator Tubing The steam generator inspection program was implemented during the current refueling outage, to inspect 100% of the tubes in the No.1 and No. 4 steam generators.
The inspector reviewed Procedure Z QA 301 " Eddy Current Testing of Steam Generator Tubing" which describes the equipment and methods and personnel qualification and calibration standards to be used for inspection.
The inspector examined the test equipment set up consisting of a EM-3300 eddy current instrument with the inspection bobbin coil probes design for inside of tubes performance was monitored by the use of an oscilloscope with a phase sensitive vector display and recorded for later review and evaluations by the TEAC magnetic tape recorder and a brush strip chart recorder. The probe insertion was monitored by closed circuit TV.
During the inspection tubes in No.
4 Steam Generator tubes testing was completed with a resultant of 12 tubes which were rejectable to a calibration standard of 3/16 flat bottom hole drilled through 40% of the wall thickness from the outside surface.
The inspector was informed that these would be plugged.
No items of noncompliance were identified.
5.
Observations The inspector witnessed the following listed activities to determine if the performance of testing activities were in accordance with the applicable procedures or specifications listed in the progra.
a.
Reactor Vessel Closure Head After the closure head was removed from the reactor vessel it was removed from the Vapor Container and placed on a flat car for ultrasonic examination.
The circumferential weld joining the closure head dome to the bolting flange for a distance of 25 percent to 41 percent of the circumference was selected in accordance with the approved program for the examination.
The test procedure used was UT-YA-2 and Calibration Standard YR6.
The inspector witnessed the calibration of the test equipment, the scanning technique and the signal display relative to the DAC curve.
No items of noncompliance were identified.
b.
Pre-Service Inspection Ultrasonic examination of four welds (62-76)(62-77)(62-78)
(62-81) which were part of the Post Loca Recirculation system modification were tested to establish base line data for future inservice inspections.
The welds are austenitic stain-less joining 6" schedule 40 pipe.
The tests were performed to the requirements of YA-UT-10 using calibration block YA21.
The inspector noted that the transducer and test unit were rechecked to the calibration standard after the testing was completed and found that the reference signals would not relate to the DAC curve as originally established.
Inspection of the transducer revealed a mechanical failure in the transducer.
A new transducer was then obtained and the four welds retested which indicated compliance with the procedure.
c.
Steam Generator Support Lu_q The Yankee-Rowe ISI program lists one of the integrally w:lded steam generator supports on Unit 2 to have a surface type examination during this outage.
After removal of the insulation, it became apparent that there was insufficient space between the load bearing clevis and the lug to vessel weld to perform a magnetic particle examination and limited accessability around the full perimeter of the weld to perform a complete dye pentrant.
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Approximately 1/3 of the lower weld to the vessel was examined on a best effort basis be using magnifying mirrors and performing a dye pentrant examination in the limited space.
The dye penetrant results were also reviewed by mirror.
The area tested in this manner would represent the highest stressed part of the loaded support lug. The inspector examined the areas of interest by using magnifying mirrors on both of the described visual and surface examinations.
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No items of noncompliance were identified.
6.
Personnel Qualification Records The inspector audited the qualification records of the personnel involved with the performance of the nondestructive examination during the current outage.
The records for five N.D.E. technicians were examined for compliance to requirements of SNT-TC-1A and ANSI N45.2.6 for the disipline(s) in which the individual was trained and certified, resume of experience, level of certification including data certified.
The physical examination records were current, included visual acuity and color vision tests and included the necessary restrictions for individual examiners.
No items of noncompliance were identified.
7.
Post Loca Recirculation System Modification An inspection was made of a section of the piping system which is being modified to improve the long term cooling capabilities of the Emergency Core Cooling System (ECCS).
A review was made of Engineering and Design Change Request (EDCR 78-1) for details of the modification and evidence of required review and approvals.
The inspector selected a subassembly consisting of four (4) welds (62-76)(62-77)(62-78)(62-81) which joints 6" schedule 40 pipe to a value SI-V-697 on one end of the assembly and a forged tee on the other, for a visual inspection of the welds, fit up and general condition.
The NDE records for these welds were ' examined for liquid penetrant (LP) of weld preparation, LP of weld root, LP of final weld, radiographic examination of the final welds. The weld character of filler metal, type of welding, heat number, procedures used, identity of welders and review of qualification were examined for these welds.
In addition, the material certifications of the pipe and fitting were inspected to the requirements of ASME Section II Part A.
The following material certifications were examined:
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HT No. M1553 6" Schedule 40 Pipe A376 TP 304 HT No. JKMM 6" Schedule 40 45* Elbow A 403 Type 304 B&W HT No. JJYO 6" Schedule 40 Tee A403 Type 304 HT No. 20688 3/32 E308-16 HT No. 33528 3/32 ER308 No items of noncompliance were identified.
8.
Exit Interview At the conclusion of the inspection on November 9,'1978, a meeting was held at the site with representatives of the licensee.
Attendees at this meeting included personnel whose names are indicated in paragraph 1.
The inspector summarized the results of the inspection as described in this report.
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