ML20042B109
| ML20042B109 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/13/1972 |
| From: | Brunner E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James Keppler US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20042B110 | List: |
| References | |
| NUDOCS 8203240580 | |
| Download: ML20042B109 (3) | |
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UNITED ST ATES S h[*,
ATOMIC ENERGY COMMISSION
// ^ 3 OlHECTO R ATE OF REGULA TO RY OPEH ATIONS
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f4CW ARK, f4CW JERSEY 07192 (201) 645-3942 e
JUL 131972 J. G. Keppler, Chief, Reactor Testing & Operations Br.
- Division of Regulatory Operations, HQ R0 INSPECTION REPORT NO. 50-247/72-08 CONSOLIDATED EDISON REPORT INDIAN POINT 2 The subject inspection report is forwarded for your action.
This inspection covered only specific repair performed on IP-2 fuel.
The rod malfunction at IP-2 may be generic to other facilities.
Our inspectors were informed that Ginna, Conn Yankee, and San Onfre have similiar fuel assemblies and similiar clearances between the rods and guide thimbles. An evaluation should be made of the design characteristics, and the fuel fabrication techniques and to determine if the QA Program is properly implemented at the Westinghouse Fabri-cation Facility.
The Con Ed and Westinghouse decision to unload the core is considered to be a responsive action. The rework of the control rods is com-plete and is considered by the inspector to be acceptable. The control rod guide thimbles are undergoing an additional repair which is not expected to be complete before July 7, 1972.
Con Ed will submit a report on the control rod and fuel assembly problem to the Directorate of Licensing.
Con Ed also have committed themselves to again performing the control rod drop preoperational test.
The Con Ed schedule for completion of construction activities and completion of fuel repair for initial criticality by August 1, 1972 is considered optimistic. Any problems encountered will extend their schedule beyond August 1, 1972.
An updated outstanding items list is attached.
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.a E. J. Brunner Chief, Reactor Testing & Startup Br.
Enclosure:
Subject Inspection Report (18 cys) cc:
J. B. Henderson, RO P. A. Morris, R0 H. Thornburg, R0 R. Engelken, R0 RO Files 2 [Sb 8203240580 720713 PDR ADOCK 05000 G
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_ CONSOLIDATED EDISON COMPANY INDIAN POINT NO. 2 f
OUTSTANDING ITEMS LIST J
1.
Verify instcilctici, of IOdciu-fuel fullute Cetection instrumentation.
2.
Verify that all preoperational test results are being reviewed, analyzed.and approved by applicant and appropriate contractors.
I 3.
Perform independent anal'ysis of selected preoperational test data, t
4.
. Complete resolution of deficiencies in design and installation of.
stach monitoring uhen compared to ANSI Standard N13.1 - 1969.
1 5.
Verify that the additional continuous stack monitor has been installed.
3 6.
Complete the review of the power ascension test procedures. Three additional procedurcs required, t
7.
Verify that scheduled training programs have been completed and that the plant organization is fuactioning in preparation for plar.t operation'.
8.
Revicu of primary system expansion test results for pipe hanger loadings and piping clearat3ces.
9.
Verify coupletion of punchlist items associated with the pipc hanger, scismic restraint and pipe whip restraint installation.
10.
Verify that the contingency plan has been implemented, 11.
Verify that the security program has been implemented.
12.
Verify completion of subcritical testing master punchlist items.
4 13.
Complete review of NYU llospita1 Emergency Plans.
14.
Complete review of fire damage componcut testing.
15.
Complete review of accumulator check valvo cverlay activitics.
I 16.
Complete review of main steam safety valve modification.
17.
Verify completion of RHR heat exchanger repair.
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18.
Complete revicu of control rod malfunctions.
19.
Compicte reuork of fuel assembly guide thin 51cs.'
20.
Revicu resulte 0.' reactor coolant system cicanup program.
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