IR 05000293/1980003
| ML19309C933 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/09/1980 |
| From: | Lester Tripp, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19309C927 | List: |
| References | |
| 50-293-80-03, 50-293-80-3, NUDOCS 8004090401 | |
| Download: ML19309C933 (6) | |
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V U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-293/80-03 Docket No. 50-293 C
License No. DPR-35
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Priority Category Licensee:
Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199
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Facility Name: Pilgrim Nuclear Power Station Inspection at: Plymouth, Massachusetts Inspection conducted:
January 22-24, 1980 Inspectors:
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$b T 1910 G. A. Walton, Reactor Inspector date' signed
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date signed date signed J '.
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Qflfh0 Appraved by:
A k.E.Tripd,Ichief date signed Engineerir.g Support Section #1, RC&ES Branch Inspection Summary:
I_n_spection on January 22-24, 1980 (Report 50-293/80-03)
Areas Inspected:
Routine unannounced inspection of activities associated with the torus modification and intervice inspection.
The inspection involved 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> or site by one regional based NRC inspector.
Resul ts: No items of noncompliance or deviations were identified.
Region I Form 12 (Rev. April 77)
8004090 Yd/
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DETAILS 1.
Persons Contacted Boston Edison Company B. Cox, Inservice Inspection Supervisor
- F. Famulari, Senior MechanicL1 Engineer
- R. Machon, Assistant Station Superintendent P. McGuire, Station Superintendent
- J.
Nicholson, Staff Assistant Southwest Research Institute W. Flach, Field ISI Manager Graver Energy Systems Inc.
D. Mills, Project Manager
- Denotes those present at the exit interview.
2.
Inservice Inspection Activities The inspector reviewed the following detailed vork procedures for nondestructive examination on safety related ',ystems to ascertain compliance with the ASME Section XI,1974 Edition and Summer 75 Addenda.
SWRI-NDT-700-5 Revision 3, Mechanized Ultrasonic Examination
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of Vessel Components, Vessel Welds, and Piping Welds Peabody No. 22.A.15, Ultrasonic Examination Vessel Welds,
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Nozzle to Vessel Welds, Vessel Head and Nozzle to Head Weld Peabody No. 22.A.16 Revision 1. Ultrasonic Examination of
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Piping Welds Peabody No. 22.A.19, Ultrasonic Examination of Full Penetration
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Dissimilar Metal Welds Peabody No. 23.A.3 Revision 3, Penetrant Examination Sdivent
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Removable Visible Dye Penetrant
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The reviews included, but were not limited to the considerations listed below:
The type of apparatus including frequency range is specified.
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The extent of coverage, beam angles, nominal frequency and
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transducer size are specified.
Recording, evaluation and acceptance criteria for flaw indications
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are specified and consistent with the ASME Code requirements.
No items of noncompliance with regulatory requirements were identified.
3.
Ultrasonic Examination of Reactor Pressure Vessel Weld N2B Ultrasonic inspection of the nozzle to vessel weld of recirculation inlet nozzle N2B which was performed in 1974 disclosed a crack-like indication in the weld. Based on fracture mechanic analysis it was determined that there was adequate safety margin for reactor vessel structural integrity during further operation provided the flaw was re-examined during successive refueling outages, the results analyzed, evaluated and reported to the NRC after each inspection.
The reinspections had been perfomed in 1976, and 1977, reviewed by the licensee, NRC and NRC consultants.
It was concluded that there was no evidence that the flaw grew significantly in the intervals between 1974,1976 and 1977.
The inspector reviewed the data for the third reinspection which was conducted during the current refueling outage.
The examination was performed utilizing a mechanical inspection technique, and recording devices and all associated equipment the same as that used in 1976 and 1977.
The examinations were conducted using 45 and 60 degree angle beam transducers coupled to both flat and curved wedges. The calibration was perfomed utilizing the code acceptable calibration block PIL-5,
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The indications were plotted by the licensee's inspection contractor using a 50 percent distance amplitude curve level for comparison to previous examinations.
The results of the examination disclose no significant defect growth has occurred.
The signal amplitudes responses are generally smaller than those received during the 1977 inspection.
Based on the licensee's evaluation for three consecutive refuelings without any indicated flaw growth the inspection of N2B nozzle weld is being returned to the normal inspection frequencies established by ASME Section XI.
No items of noncompliance with regulatory requirements were identified.
4.
Structural Modifications to the Mark I Containment System The inspector audited select areas of modifications of the wetwell torus and associated supports.
The review was made to ascertain compliance with " replacements" as defined by IWA-7110 or " repairs" in accordance with IWA-4000 of the ASME Boiler and Pressure Vessel Code, Sec. tion XI with Addenda through Summer of 1978.
The inspector reviewed the torus column support system which is being modified by the addition of saddles. A butterhead/temperbead welding technique is used to connect the saddles to the outside of
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the torus.
All welding is perfonned with the torus empty of water.
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The inspector reviewed the following documents.
Torus Modification Quality Plan Rev. 0
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Fabrication Specification FS-2255-1, Rev.1
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Owners Specification 0S-2255-1, Rev.1
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Drawing 22800NA-MA-001, Rev.1
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Welding Procedure BE-FCB-TN, Rev. O Flux Core Automatic Welding
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Weld Procedure Qualification FC 77
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Certain " draft" rules for IWE 4XX0 for MC components and ASME Code Case N-236 for repair and replacements of MC components is being used on the modifications being made to the wetwell.
These rules, although not specifically approved by NRC were reviewed by the inspector to ascertain compliance with the commitments of the licensee to comply with the original construction requirements.
The " draft" rules are specific for containment repairs and modification and equal or exceed the original construction requirements.
No items of noncompliance with regulatory requirements were identified.
5.
Interior Examination of Reactor Pressure Vessel
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The inspector reviewed the plan for visual examination by remote control and video camera for the following areas of the reactor
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vessel internals.
Vessel sealing surface
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Vessel wall
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Nozzle inner radius surfaces
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(a) steam nozzles (b)
instrumentation nozzles (c) core spray nozzles (d)
feedwater nozzles (if accessible)
Core spray lines, nozzles and attachments
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Upper core plate
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Lower core plate (fuel removed)
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Core Shroud (fuel removed)
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Bottom inside surface of vessel
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Jet pumps
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Steam dryer and separators and their attachments
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The inspector requested the licensee add the core spray spargers to the visual inspection program.
This was requested because of defects found on the core spray spargers at another nuclear facility.
The licensee agreed and included it in his program.
The plan was reviewed for compliance with ASME Section XI, Summer 1975 Addenda.
No items of noncompliance with regulatory rquirements were identified.
6.
Exit Meeting At the conclusion of the inspection on January 24, 1980, a meeting was held at the Pilgrim Nuclear Station with representatives of the licensee organization.
The attendee's names are asterisked in paragraph 1.
The inspector summarized the results of the inspection as described in this report. The licensee representatives acknowledged the inspector's summarization.