ML20234C872
| ML20234C872 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/22/1987 |
| From: | Kahn G PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20234C672 | List: |
| References | |
| OL-1, NUDOCS 8801060353 | |
| Download: ML20234C872 (6) | |
Text
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UNITED STATES OF AMERICA
' UNITED STATES NUCLEAR REGULATORY' COMMISSION
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before the ATOMIC SAFETY AND LICENSING BOARD l
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In the Matter of
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PUBLIC SERVICE COMPANY
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Docket Nos. 50-443 OL-1 NEW HAMPSHIRE, et al.
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50-444 OL-1
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(Seabrook Station, Units 1
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(On-site Emergency and 2)
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Planning Issues)
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AFFIDAVIT OF GREGORY A.
KANN I,
GREGORY A.
KANN, being on oath,. depose and say as follows:
1.
I am the Program Support Manager at Seabrook Station.
I am responsible for the Inservice Inspection Program, the Inservice Testing Program, and the Test Control Program.
A statement of my professional qualifications is attached hereto and marked as "A".
2.
Following hot functional testing the internals of the steam generators were inspected during the week of April 21-25, 1986.
These inspections were performed to satisfy the Class "C" cleanliness requirements of ANSI N.45.2.1-1973, for the secondary side steam generator internals.
8801060353 880104 PDR ADOCK 05000443 0
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The inspection locations were based on the areas that have historically been shown to be natural collection areas for foreign objects.
The following areas were inspected:
lower tube sheet area, separator area and downcomer annulus area.
4.
The accessible areas of the lower tube sheet were inspected by inserting the sub-miniature camera (probe) through opened handholes in each of the four steam generators.
5.
Probe positioning during inspection of the center lane area was facilitated by the use of a guide tube; electrical conduit with a 90 degree bend at the distal end.
Probe articulation controls were used to steer the camera head to provide the best view.
6.
The tube sheet annulus area and adjacent tube lanes were inspected by first inserting (pushing) the probe around the circumference while viewing forward.
On retraction, the articulation controls were used to provide a view down the tube lanes.
All inspections of the tube sheet area were recorded on \\" VHS video tape.
Pertinent data (e.g.,
distances or general identification) was entered onto the recordings though the use of an alpha-numeric character generator with time /date output.
7.
The separator area and related components were inspected during a " walk through" examination of each generator.
Entry was through a 16" manway opened for this purpose.
The U
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surface conditions of various internal components were photographed using a 35mm SLR camera equipped with a flash and color print film.
8.
Disposable protective clothing was worn during the walk through examinations to reduce the possibility of carrying contaminants into the generator internals.
In addition, material / equipment inventory control was maintained by access control logs to preclude introduction of foreign objects into e
the general internals.
9.
The downcomer annulus areas were also directly viewed at this time; no irregularities were-noted.
10.
The areas viewed in each of the steam generators meet the requirements for Class "C" cleanliness under ANSI N.45.2.1-1973.
11.
All debris located during these inspections was removed.
The slight amount of material removed (estimate 3 to 4 ounces) was determined to be construction debris (e.g.,
pieces of wire).
Each of the four generators is considered to be free of any and all materials in areas inspected, which might be harmful to their useful service life. No structural abnormalities were noted.
12.
In addition to the above visual examination a loose parts monitoring system as described in Section 4.4.6.4 of the Seabrook FSAR is employed at Seabrook Station to detect a loose part on the steam generator tube sheet during plant operation.
This equipment is required to be operable during i
.k' Modes 1 and 2 and if an alert level is exceeded, diagnostic i
steps will be taken within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to determine if a loose part is present.
The safety significance of any identified loose part will be determined.
13.
Based.on the above there is no need to re-examine the steam generator internals for foreign object unless and until an entry is made.into the steam generators.
No entry into the steam generators is expected to occur until the first periodic inspection.
Operating at 5% power will not preclude performing additional inspections, if required.
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Grep
.'Kann STATE OF NEW HAMPSHIRE Rockingham ss.
December {, 1987 The above-subscribed Gregory A. Kahn appeared before me and made oath that he had read the foregoing affidavit and that the statements set forth therein are true to the best of his knowledge.
Before me, b d b N n y u.u Notary P$ lic A
My Commission Expires: 3/6/90...
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~i GREGORY A KANN PROGRAM SUPPORT MANAGER EDUCATION B.S.
Nuclear Engineering, Lowell. Technological Institute, June 1969.
M.A. Management and Supervision, Central Michigan University, August 1974.
PROFESSIONAL AFFILIATIONS American Society of Mechanical Engineers American Nuclear Society LICENSE USNRC Senior Operator License, License No. SOP-3349, North Anna Power Station, Unit No.
1, 1978.
Mr. Kann has participated in startup test programs and operation of commercial nuclear power facilities since 1974.
Mr. Kann joined Virginia Electric and Power Company (VEPCO) as a test enaineer at the North Anna Power station following his separation from the U.S. Air Force.
During his time with VEPCO Mr. Kann participated in preoperational and initial startup testing required by Regulatory Guide 1.68 for North Anna Units 1 and 2.
Mr. Kann's participation included the development of detailed test procedures, performance of tests, and the review and approval of test results.
At North Anna Power' Station Mr. Kann held the position of Test Engineer, Lead Preoperational Test Engineer, Startup Test Engineer, Design Control Engineer and Engineering Supervisor.
As Engineering Supervisor, Mr. Kann was responsible for the Reactor Engineering Section, Technical Specification Surveillance Test Section, and the Design Control Section.
As a Staff Engineer at the corporate office for VEPCO, Mr. Kann developed design change packages for implementation at both North Anna Power Stations and Surry Power Stations.
Since joining Yankee Atomic Electric Company in 1981, Mr.
Kann has participated in the preoperational and initial startup test program in accordance with Regulatory Guide 1.68 (Revision 2) for Seabrook Station.
"A" l
Mr. Kann transferred to Public Service Company of New Hampshire (PSNH) in 1984 and continued to participate in the preoperational and initial startup test program at Seabrook Station.
Presently Mr. Kann is the Program Support Manager at Seabrook Station.
In this position Mr. Kann is responsible for the Inservice Inspection Program, the l
Inservice Testing Program, the Test Control Program and other various technical programs.
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