ML20084M080
| ML20084M080 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/03/1984 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| NJK-84-157, NUDOCS 8405150205 | |
| Download: ML20084M080 (4) | |
Text
c D Commonw:alth Edison g y) 22710 206 Avenue North f, 's-Quid Citlis Nucliar Power Station
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/ Cordova,!!!inois 61242 Telephone 309/654-2241 So-g S L/
266 NJK-84-157 May 3, 1984 Mr. Edson G. Case, Deputy Director Office of Nuclear Reactor Regulation U. S, Nuclear Regulatory Commission Washington, D, C, 20555
Dear Mr. Case:
Enclosed please find a listing of those changes, tests, and experi-ments completed during the month of April 1984, for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30.
A summary of the safety evaluation is being reported in compliance with 10 CFR 50.59.
Thirty-nine copies are provided for your use.
Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION p
N. J, Kallvianakis Station Superintendent bb Enclosure cc:
B. Rybak' I4s\\
8405150205 840503 m
gDRADOCK 05000254 PDR
\\\\
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i SPECIAL TEST.1-63'
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- Special Test I-63 was completed on March 17, 1984. The purpose of this test was'to change instrument setpoints so as to close the A0 l-4799-221 valve to eliminate the source of oily Service Air into the i
instrument Air System.-
f Safety Evaluation:
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The probability of an occurrence or the consequence of an
-: accident, or malfunction of equipnent important to safety as previously evaluated in the Final Safety Analysis Report
'Is not increased because the Instrument Air System is not m
safety related. The Integrity of the system is still maintained as there will be no excessive load placed on the system. The Service Air back-up is still available. No j
safety rel~ated equipnent is adversely affected by this test.
j 2.
The possibility for an accident or malfunction of a different type = than any previously evaluated in the Final Safety Analysis Report. ls not ~ created because although the margin to low air i
pressure problems (Feedwater Regulating Valve lock-up, MSIV
. closure, Control Rod drift) is reduced. the fact that A01-4799-221 is a pressure control valve mitigates these consequences.
Sufficient margin will still exist to allow i
A0 1-4799-221 to open and prevent entry'into low air pressure
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situations.
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3.
The margin of. safety, as defined in the basis for any Technical i
Specification,-is not reduced because no instrument setpoints j
for technically specified instruments are altered.
This test only reduces the nominal operating pressure of the system in i
order to eliminate. useless Control Room alarms and keep oily Service Air out.of the Instrument Air System.
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5 SPECIAL TEST I-73 Special Test 1-73 was completed on April 17, 1984. The purpose of this test is to; l) perform visual Inspection and special measurements (NDT -- Eddy Current Testing, Ultrasonic Testing, etc.) on selected Unit One fuel (4 Barrier Lead Test Assemblies), 2) replacement of one water rod from each of four Barrier Lead Test Assemb11es.
Safety Evaluation 1.
The probability of an occurrence or the consequence of an accident, or malfunction of equipnent important to safety as previously evaluated in the Final Safety Analysis Report is not increased because all fuel handling will be performed within the confines of the Spent Fuel Storage Pool using standard, reviewed, and approved fuel handling procedures.
Generic procedures will also be used by General Electric personnel that have been reviewed under the Special Test Review ard are found acceptable.
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 all fuel maneuvers will be standard operations such as bundle transfers between racks, dechanneling and channeling and are within the assumptions of the FSAR evaluation. The other activities do not 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 during the test would cause release rates greator than those assumed for j
the Technical Specification basis.
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quad-Cities Unit-1 l
Cycle 8 Safety Evaluation Summary A review of DPR-29 and its appendices was conducted to determine whether changes to the. Quad-Cities Unit i Technical Specifications are l
required for Cycle 8 operation. The results of the quad-Cities Unit 1 i
Cycle 8 licensing analyses comply with and are conservatively bounded by the Technical Specifications as modified by QlC8 preparatory Technical Specification' changes.
Once the preparatory changes have been implemented, the following provisions of 10 CFR 50 59 will be satisfied for Cycle 8:
A.
Neither the probability of an occurrence nor the consequences of an accident nor the malfunction of safety related equipment, as previously evaluated in the safety analysis report,' is increased.
B.
The possibility for an accident'or malfunction of a dif ferent t
type than previously evaluated in.the safety analysis report is not created.
.i C.. The margin of safety, as defined in the basis for any i
Technical Specification, is not reduced..
in conclusion, the QlC8 reload as described in the cycle specific licensing document (23Al718) does not raise any unreviewed safety l
questions, nor does it require'any revisions to the Technical Specifications
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provided that the preparatory changes are approved by the NRC.
Based on the preceding discussion, NFS recommends approval by On-Site and Off-Site of the QlC8 reload and supporting analyses under the provisions of 10 CFR 50.59 t
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