ML20235Z353
| ML20235Z353 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/02/1987 |
| From: | Robey R COMMONWEALTH EDISON CO. |
| To: | Lieberman J NRC |
| References | |
| RAR-87-45, NUDOCS 8710210104 | |
| Download: ML20235Z353 (4) | |
Text
,
r L Commonwealth Edison
' ouad olties Nuclear Power Station
"'1"..'A*"."* " ""
ossac-os 1
Telephone 309/654-2241 I
F18100120- A 9 51 i
i RAR-87-45 I
.l October 2, 1987 o
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U.,S. Nuclear Regulatory Commission Washington, D. C.
20555 Attn:
J. Lieberman:
M/S MNBB-4100 Enclosed please. find a listing of those changes, tests, and experiments' completed during the month of September, 1987,.for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30.
A. summary of.the safety evaluation is-l being reported in compliance with 10 CFR 50.59.
Thirty-nine copies are provided for your use.
Respectfully, j
COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR P0HER STATION R. A 019 R. A. Robey Services Superintendent vk Enclosure cc:
I. Johnson J. Leider/E. Budzichowski 8710210104 071002 h-ADOCK0500g 0027H/00612 PDR g\\
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I SPECIAL TEST 1-94' t
Special test 1-94 was completed on August 14, 1986 and the off site review
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initiated on September 18, 1987. The purpose of this test was to verify-the i
presence of "Boraflex" neutron absorbing material in spent fuel racks. This will be done by. inserting a neutron source in the cell to be tested and using 4 neutron detectors to verify the presence of'"Boraflex".
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Safety Evaluation 1.
The probability of an occurrence or.the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not' increased because this test will not defeat.any safety systems,nor will'this test be tied into any plant equipment except.for the' normal movement of the refueling platform.
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The possibility for an accident or malfunction of a different type i
than any previously evaluated in the Final Safety Analysis Report is not created because the mode of failure would be the detector dropping in the fuel pool. This has been analyzed for a fuel bundle i
which is more massive and has a much high fission product inventory.
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3.
The margin of safety, as defined in the basis for any Technical' Specification is not reduced because this test will not effect the fuel pool water level, K,ff, nor the structual integrity of the fuel pool liner.
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SPECIAL TEST 1-97 1
Special test 1-97 was completed on August 20, 1987 and the off site review initiated on September 18, 1987. The purpose of this test was to confirm the
-l results of and to more accurately characterize the suspected defects in the "Boraflex" neutron absorbing material in spent fuel racks as identified in
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i special test 1-94, This test was similar to 1-94 except that the neutron detectors used were strongly geometry dependent in order to allow defect localization.
Safety Evaluation 1.
The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously.
evaluated in the Final Safety Analysis Report is not increased because any movement of fuel necessitated by this tast will be within H
the confines of the spent fuel pool and will be moved according to j
approved station procedures.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because no activities in conjunction with this test will create accident potentials greater than the dropped fuel bundl accident considered in the FSAR.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because no activities in conjunction with this test would cause releases greater than those assumed for technical specification bases.
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SPECIAL TEST 1-98 s
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-Special test 1-98 was performed August 21, 1987 and the off site review initiated on September 18, 1987.
The purpose of this test was to verify the l
results of test 1-94 and 1-97 and to produce a visual image of the defects in
.l the "Boraflex".
l This test was performed using neutron radiography. This technique allows
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the size, location, shape, and neutron absorber deficiency to be displayed on j
film as the size, location, shape, and film opacity.
This is caused by leakage of neutrons from the source thru defects in the "Boraflex" material impinging on the film cassete.
Safety Evaluation 1.
The probability of an occurrence or the consequence of an accident,
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or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because any movement of fuel necessited by this test will be within the confines of the spent fuel storage pool and will be moved according to approved station procedures.
2.
The possibility for an accident or malfunction of a different type I
than any previously evaluated in the Final Safety Analysis Report is not created because no activities in conjunction with this test I
will create accident potentials greater than the dropped fuel bundle accident considered in the FSAR.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because no activities in conjunction l
l with this test will create releases greater than those assumed for technical specification basis.
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