ML20234C482
| ML20234C482 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/02/1987 |
| From: | Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| RAR-87-42, NUDOCS 8709210308 | |
| Download: ML20234C482 (7) | |
Text
-
.,3 8. '
Commonwealth Edison 4
Quad Cities Nuclear Power Station
_ 22710 206 Avenue North Cordova ' illinois 81242 l'
l
' Telephone 309/654-2241 RAR-87-42 September 2, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk-Office of Nuclear Reactor Regulation l
Washington, D. C.
20555 Enclosed please find a listing of those changes, tests, and experiments completed during the month of August, 1987, 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.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION
$.A.R.A'Robey}
Services Superintendent vk Enclosure cc:
I. Johnson J. Leider/E. Budzichowski
,c.
J.
g921030ss70902 p
ADOCK 05000254 PDR
[
0027H/0061Z t
I
1-t 4
I s
89 i
t I
1 01:llA 81 PES ??
NOITALUGER ROT C.A.R.N.S.U ER R AELCUN C
1
7-se i
.i' SPECIAL TEST l'-102
.Special-test-1-102 was~ completed August 28, 1987. The purpose of this test was;.to monitor.-the. performance of the. service water strainers after
- modification of the existing strainer' sealing plates' The intent is to reduce
.the-amount-of.~ crud carry-over now present with the. strainers.
Saf ty 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'the design objective of the service water system is to.
supply strained river water to various plant locations.
The modification to the sealing plates will not hinder this design objective, but should act to increase the service water system reliability, as well'as strainer efficiency.
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 the modification to the sealing plates will not degrade the existing system, but should act to improve the service water system reliability.
3.
The' margin of safety, as defined in the basis for any Technical' _.
Specification is not reduced because the modification'to the sealing plates should act to improve strainer performance, thus improve service water performance. No degradation to the existing' system will be realized.
l i
n
t I
l SPECIAL TEST l-103 L
I
!~
Special test 1-103 was completed August 11, 1987. The purpose of this test was to verify that the drywell liner drain lines are not plugged in the sand pocket areas.
Safety Evaluation f
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 l
because the air pressure used for checking the passageway is less than the design for the concrete wall and any pressure buildup would be for a limited amount of time. Therefore there is no probability of an occurrence or consequences of an accident, or malfunction of important to safety as previously evaluated in the FSAR.
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 since a low pressure is being used to test the drainage path of the drywell' liner and this test only checks the normal operation of the drywell liner drain, there is no possibility for an accident or malfunction of a different type created.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because this test either will c-onfirm i
or allow passage of drainage water from the drywell liner to reduce l
potential corrosion, therefore the margin of safety is not reduced.
i l
/
SPECIAL TEST 1-104 and 2-73 Special test 1-104 was completed August 6, 1987-and special test 2-73 was completed August 3, 1987. The purpose of these tests was to determine the operation of the HPCI auxiliary oil pump during turbine operation following an auto-initiation.
4 Safety Evaluation l
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 the installation of a jumper in the control circuitry of the HPCI aux oil pump will prevent manual operation of the HPCI aux oil pump but will not prevent operation of the pump under an auto-initiation. Therefore, this test does not increase the probability of an occurrence or the consequence of an accident.
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 this test is intended to be done during normal monthly surveillance testing of the HPCI system. Therefore, no possibility of an accident or malfunction is created.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because this test will not affect the availability of the HPCI system.
Therefore, the margin of safety remains unchanged.
4 l
/
7-l SPECIAL TEST 2-74 Special test 2-74 was completed August 13, 1987.
The purpose of this test' was to hydrostatically test Residual Heat Removal (RHR) valve 2-1001-68A in order to determine the leak rate of this check valve.
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 the hydrostatic test pressure used for this test is same as normal operating pressure of this line, therefore, the probability of an occurrence or the consequence of an occurrence or the consequence of an accident, or malfunction of equipment important to safety, as previously evaluated in the FSAR, is not increased.
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 the test only measures the amount of normal leakage at normal operating pressure passing through the 2-1001-68A check valve, therefore, the possibility for an accident of malfunction of a different type than any previously evaluated in the FSAR is not created.
3.
The margin of safety, as defined in the basis for any Technical Specification is not reduced because since the pressure is at normal operating pressure and any leakage beyond the check valve it typical leakage the margin of safety as defined by Technical Specification is not reduced.
1 l
Y i
t, i
- SPECIAL TEST 2-77 Special test 2-77 was completed August 24, 1987.
The purpose of this test
. as'to determine the starting ~ current', running current, Land starting time for.
w the High Pressure Coolant Injection (HPCI) Emergency Bearing 011 Pump:(EBOP).
.n cSafety Evaluation I
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 the1HPCI system (including EBOP) are not necessary for any accident' protection when the reactor is 1n cold shutdown.
~
'2.
'The possibility for an accident or malfunction of a different type than any previously: evaluated in the Final, Safety JAnalysis Report is"not created because the HPCI system (including EBOP) does.not contribute'to reactor safety.when the unituis in cold shutdown.
3.
The margiri of safety, as defined in the basis for any Technical Specification is not reduced because Unit 2 is,in cold shutdown and is at less than 90 PSIG.
l l
s l
1
_ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _