ML19319A904

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Discusses 760219-20 Site Visit for Familiarization W/Inservice Insps at Reactor Coolant Pressure Boundary
ML19319A904
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 03/17/1976
From: Nehemias
Office of Nuclear Reactor Regulation
To: Kreger W
Office of Nuclear Reactor Regulation
References
NUDOCS 7912300125
Download: ML19319A904 (2)


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4-VAR 1 7 B76 Docket No. 50'269 and 50 5 /287l

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William E. Krager, Chief, Radiological Assessment Branch, DSE

. THRU "' T. D. Murphy, Leader, Radiation Protection Section, RAB/k OCONEE SITE VISIT On February 19th and 20th, 1976 I visite'd the Oconee Nucicar Station near Seneca, South Carolina, operated by the Duke Power Company. At the time of my visit, Unit I was in a refueling outage, with extensive QA inservice inspections in progress; Unit 2 was down for minor repairs; and Unit 3 was operating routinely. Each unit is a PUR, licensed to operate at 871 IfW(e).

The purpose of my visit was principally to familiarize myself witti the kinds of operations and radiation levels associated with inservice inspections at the reactor coolant pressure boundary, and thereby to improve my capability to evaluate, in the licensing review process, whether the associaLted occupational radiation exposures are as loV SR is reasonably achievable (ALARA). My particular interest, therefora, was focussed on those inspections involving higher radiation levels and longer occupancy times, e.g., volumetric examination of longitudinal and circumferential welds, and inspection of the steam generator tubes.

I also took the opportunity to observe some of the fuel transfer opera-tions in progress during my visit.

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}fy guide for the visit was Mr. Douglas Norton, QA Engineer, who had come to Oconee from the Duke main office for the QA inspections.

I also spoke briefly.about the health physics aspects of the QA inspections with Mr. Charles Younge,11ealth Physicist at Oconen.

Mr. Norton and I climbed around and over the equipment in the containment, i

fron three Icvels above the fuel pool (which is above the reactor) to the lowest basement floor. The panoramic view from the higher levels provided a useful perspective of plant and equipment layout. He also 4

climbed from top to bottom of the pressurizer, the sten:n generators, and

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the reactor coolant pumps. I'saw the various configurations in which welds nust be inspected and observed. inspections in process at a numb of locations.

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d Except for the steam generator;and a few isolated hot spots, radiat4,n

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levels were for the most part less than 100 millirema per hour, and' not

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high enough to constrain the inspection process. For the most part, there was adequate space in which to place and move the test equipment,

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and to conduct the inspections expeditiously.

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102 17 D76 2-W. Kroger-The~ inspection of the steam generator tubes was the principal source of

. occupational radiation exposure during inservice inspections; the dose rate at the tube sheet'was up'to 19 rems / hour. In order to keep these exposures Ar. ARA,iths' sensor is moved from tube to tube and inserted in each tube to be tested by a remotely controlled master / slave apparatus.

. The slave unit is designed to be quickly installed and removed, and nec de ' to be observed and adjusted occasionally. Entries into the steam

. generator planum are thus minimized.

In addition, the individuals involved in the actual in-plantaa aspects of the inspection are briefed in detail on the installation and removal of the apparatus and practice the operations repeatedly on a full-size mockup.-

m nf, The individuals I met were knowledgeable, helpful, and cooperative. I was taken everywhere I wanted to go and shown everything I wanted to see.

From my point of view, the visit prov6d very worthwhile. I have a much better notion of what is involved _ in actual insarvice inspections,

-where and how they are performed, and the range of dose rates that may be expected.

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