ML20086U163
| ML20086U163 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/08/1967 |
| From: | Sears J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20086U000 | List:
|
| References | |
| FOIA-95-36 50-219-67-01, 50-219-67-1, NUDOCS 9508030295 | |
| Download: ML20086U163 (4) | |
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!L U. S. ATOMIC ENERGY COMMISSION-i l
..l REGION-I DIVISION OF COMPLIANCE
'1-March 8,-1967 CO REPORT-NO.-219/67-1
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Title:
- JERSEY CENTRAL POWER & LIGHT COMPANY i
LICENSE NO.
CPPR-15 f
9 M'
. Dates of-Visit:
. February 23 and 24,1967-
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.&oA Q. R. Sears, ctdr Inspector t.
By 1
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SUMMARY
The concrete floor slab for the operating floor of the.
reactor building was being poured during the inspection visit to the Oyster Creek Facility.
The reactor vessel is scheduled'~to i
be installed in April:1967.
t An'on-site meeting was attended by DRL, Jersey Central Power-f
& Light Company and General Electric representatives, at which the DRL representatives stated that they needed more I
in formation.
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I DETAILS l
I.
' Scope of Visit I
f' A visit was made to the Jersey Central-Powe r & Light Company (Jersey Central) reactor site at Oyster Creek, New Jersey, on February 23 and 24, 1967, by Mr. John R. Sears, Reactor Inspector, Region I, Division of Compliance.
The
,k purpose of the visit was to accompany the following members of the Division of Reactor Licensing on a familiarization tour:
Mr. R. J. Tedesco Mr. A. Rizzo 1
Mr. V. Stello
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? Scope of visit (continued) a 4
l-l The visit included a tour of the facility under-con-struction and a meeting with representatives of the Power l
company and its principal' contractor, General Electric : (GE).
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Results'of Visit
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Tour The USAEC-representatives toured the facility in company with the following Jersey Central representatives:.
Mr. Thomas McCluskey, Plant Superintendent t
Mr. Ivan Finfrock, Project Engineer l'
Mr. James Neeley, Proj ect Engineer The concrete floor slab for the main operating floor of the reactor building was being poured during the visit.
concrete construction of the rest of the reactor building is
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complete.
No mechanical equipment has been installed as yet?
in the reactor building.
The airlock has been unbolted from the dry well and removed for easy access.
The dry well is empty except for.the foundation for the reactor vessel.
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The reactor vessel is on a skid at ground level next to.
E the reactor building.
A concrete plug has been poured to test the hoist which will be used for installing the reactor vessel.
Installation was said to be scheduled for April 1967.
.j concrete and the metal siding for.the turbine building is complete.
Main components for the turbine are in the i
F building but not installed.
Some primary piping is in place.
l-Welding was said to be scheduled for some time after the reactor vessel and the loop piping are installed.
The con-denser shells are in place but tubing has not commenced.
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- 4, Results of Visit (continued)
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. The main transformers are in place. The discharge canal is complete up to the site perimeter but not cut through to the ' location of pump intake and discharge.
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Meeting t
In addition to the people mentioned above, the following attended a meeting held on February 24, 1967:
Mr. Donald Reese, Jersey Central Project Manager Mr. Donald Huggins, GE Project Manager Mr. Thomas-Bloom, GE Project Engineer l
Mr. George Ritter, Jersey Central Chief Mechanical l
Engineer attended for a short while l
The DRL representatives emphasized that the meeting was preliminary in nature and that they were nct prepared-to ask j
many specific questions on safety analysis.
Mr. Huggins stated that the initial license re, quest is i
for a rating of 1600 Mwt.
The turbine has been designed for 1860 Mwt.
Safety analysis has been made with the specification that scram occurs at 120% of normal operating level, i.e.,
1920 Mwt.
The DRL representatives outlined a number of general 4
areas in which they needed more information:
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The designer's approach to uncertainty analysis.
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T 2.
Fabrication reports on containment and the reactor
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vessel.
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The core cooling problem.
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Blowdown forces on core internals.
5.
Details of what happens in the maximum credible accident.
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Results of Visit (continued) ~
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a Mr. Huggins repliedfthat answers to many questions k
will be made in the forthcoming topical reports.. These reports l
will describe various systems of the' GE product line of ' standard "i-power reactors.
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['1 The inspector urged the Jersey Central r,epresentatives-f to document the activities of their Safety Committee.
Mr.
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Huggins. stated' that the writing of the preoperational test procedures has started.
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Exit Interview Due to'the nature of this visit, a specific exit i
interview was not held.
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