IR 05000318/1979018
| ML19257C917 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/12/1979 |
| From: | Lester Tripp, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19257C916 | List: |
| References | |
| 50-318-79-18, NUDOCS 8001310082 | |
| Download: ML19257C917 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-318/79-18 Docket No. 50-318 License No. DPR-69 Priority Category C
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Licensee: Baltimore Gas and Electric Comnanv P. O. Box 1475 Baltimore, Maryland 21203 Facility Name: Calvert Cliffs, Unit 2 Inspection at: Lusby, Maryland Inspection con cted:
November 8-9, 1979 Inspector :
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'. A. Wal Mn, Reactor Inspector date signed i
date signed date signed Approved by: /,
/2[/2/79 (/L. E. Tri6%, Chief, Engineering Support dat'e signed Section No.1, RCSES Branch Inspection Summary:
Inspection on November 8-9, 1979 (Recort No. 50-318/79-18)
Areas Inspected:
Routine, unannounced inspection of inservice inspection activi ti es.
The inspection involved 12 inspector-hours onsite by one NRC inspector.
Resul ts :
No items of noncompliance were identified.
1843 Ob7 O g g 131 O O $k Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Baltimore Gas and Electric Crwny B. Denton, Operations Engineer
- L. Russell, Plant Engineer W. Gibson, Nuclear Plant Engineering Performance
- T. Snydnor, ISI Coordinator Southwest Rer_earch Institute T. Inaycas, Senior Technician 2.
Inservice Inspection Activities The inspector audite ? the following activities related to inservice in-spection.
a.
Eddy Current Inspection of Steam Generator Tubes The licensee had completed the eady current examination of 6 percent of steam generator number 21.
The data analysis by a qualified inter-peter from Ietec Inc., indicated no tubes required plugging.
Essentially, no evidence of tube wastage was detected.
The examinations were done in accordance with BG&E procedure NDE-5.500, dated August 28, 1978.
The data was evaluated in accordance with regulatory guide 1.83 and the Facility Technical Specification.
No items of noncompliance were identified.
b.
Data Review and Evaluation The inspector selected the following items for review:
Reactor Pressure Vessel 7.5", Longitudinal Weld - Lower Head - 1-204A,1-204F
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1-19 Holes, Circumferential Welds - Flange to Upper Shell Outlet
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Nozzle 1800 Nozzle Inside' Radius
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10" Closure Head - Meridional Weld
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180" Closure Head - Circumferential Weld
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Pressurizer 15.5" Longitudinal Weld 2-401 A
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Steam Generator No. 21 Extension Ring Longitudinal Weld 21-104-05A, 21-104-05B, 21-104-
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05C Reactor Coolant Pipe Nozzle to Transition Piece 42-RC-21-1, 2
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flass 2, Steam Generator No. 21 Derieub; Assembly To Upper Head Dome,19" length
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Class 2 Piping Main Steam - Branch Connection 36-MS-2001, 30.5" length
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The inspector audited the preliminary data identified above to ascertain:
(1) performance of examinations by properly certifieo personnel; (2)
equipment calibration perfonned periodically; (3) use of specified equipment; (4) recorded test data sufficient to provide basis for evaluation; and, (5) evaluation and dispositioning of examination findings.
No items of noncompliance with regulatory requirements were identified.
c.
Personnel Qualification Records _
The inspector audited qualification records of six nondestructive examination personnel performing examinations during the current outage.
The records identified the discipline in which the individual had been certified.
Additionally, these records indicated the level of expertise to which the individuals were qualified.
Also, physical examination records indicated when visual aids were required. No departures from SNT-TC-1 A were identified.
No items of noncompliance with regulatory requirements were identified.
1843 0b9
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3.
Steam Generator Feedwater Nozzles The licensee has completed the radiography of the main and auxiliary feedwater to pipe welds as required by IE Bulletin 79-13 on both Units 1 and 2.
The inspector reviewed the radiographic procedure, NDE 5-300, Revision 2, and the radiographic film to ascertain compliance with the bulletin.
The welds were examined by radiography using a thru-wall technique, film side penetra-meter, 16 inch source to film distance, 95 curies of Iridium-192.
The 2T hole was visible on each film, and the densities were in an acceptable range.
The inspector reviewed all film from Unit 1 and 2 and no unacceptable defects were noted.
No items of noncompliance were identified.
4.
Exit Interview The inspector met with the licensee representatives shown with an asterick in Paragraph 1 at the conclusion of the inspection on November 9,1979.
The inspector summarized the scope and findings of the inspection as described in this report.
1843 070