ML20106D707
| ML20106D707 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/04/1992 |
| From: | Tietz G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GCT-92-38, NUDOCS 9210130284 | |
| Download: ML20106D707 (10) | |
Text
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. Commonwealth Edison :
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[ou:d Ciths Nuctsar Powsr Station 22710 206 Avenue North
' Cordova, Illinois 61242 it Telephone 309/654-224i GCT-92-38
-September 4,1992 4
-U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk
-I Washington, D.C. 20555
SUBJECT:
Quad Cities Nuclear Stttion Units I and 2 Cham 9s, Tests, and Experiments Completed -
MC_&cket Nos 50-21LADL50-lfi5-1 Enclosed please find a listing of those facility and procedure changes, tests,
-and experiments.equiring safety evaluations' completed during the month of
-August-1992, far Quad-Cities Station Unif; 1 and 2, DPR-29 and DPR-30. A summary of the safety. evaluations are being reported in compliance with
.10CFR50.59:and 10CFR50,71(e).
Respectfully, COMMONHEALTH EDISON COMPANY OUAD-CITIES NUCLEAR POWER STATION
$, w f)^ V '
Gerald Tietz Technical Superintendent' GCT/dak Enclosure cc: A B. Davis, Regional Administrator T.~ Taylor, Senior Resident Inspector DD0023 TS 92' 0]gQ $$
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SE-92-149 Temporary Alteration DESCRIPTION:
A Formanite clamp is installed on the 2-2301-IP valve in order to stop the leak.
The clamp will remain installed on the valve untti an outage of sufficient duration allowing maintenance persornel to repair the leak.
This valve is located on a 3/4" pressure test tap line between the A02-2301-7 valve and M02-2301-8 valve.
SAFETY EVALUATION SlM4ARY:
1.
The change described above has been analyzed to determine each accident or anticipated transient described in the UFSAR where any of the following is true:
The change alters the initial conditions ustd in the UFSaR analysis.
The changed structure, system or component is explicitly or implicitly assumed to function during c* after the accident.
Operation or failure of the changed structure, system, or component could lead to the accident.
The accidents which meet these criteria are listed below:
LOCA UFSAR SECTION 6.1, 6.3, 15.0 For each of these accidents, it has been determined that the change described above will not increase the probability of an occurrence or the consequence of the accident, or malfunction of equipment important to safety as previously evale3t > in the UFSAR.
2.
The possibility /or an accident or malfunction of a different type than any previously evaluated in the UFSAR is not created because the installation of the furmanite clamp on the 3/4" HPCI test tap line to stop the 2-2301-18 valve from leaking will not reduce the ability for HPCI to fulfill its intended safety function during a LOCA.
The weight and location of the furmanits clamp has been analyzed and satisfactorily meets all seismic and pipe stress design allowables in the UFSAR and code requirements and therefore, is acceptable for HPCI operation.
In the event of the clamp failing the release of radioactive coolant would be L
directed into the Radwaste system where the flow would be monitored and I
processed.
This would maintain the MSIV room from flooding and reduce contamination area.
3.
The margin of safety, is not defined in the basis for any Technical Specification, therefore, the safety margin is not reduced.
TS 112
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SE-92-151 Component Replacement C04-0-92-033 DESCRIPTION:
Th' component replacement replaces the two existing.100, and one.050 kva cc. trol power transfoaers in MCC 18-4 cubicles IC, 2B and 2C with.300 kva control power tr ansformers.
The design of the new transformers is similar to that of the existing transformers.
The new transformers have a lower impedance because the etze of the wire in t.e transformer windings is larger in diameter than that of the ex: sting.
This makes the new transformers more reliable Lecause less heat will be generated in the transformers during normal and degraded voltage conditions.
The new
'ransformers do not change the power requirements of the Control Room AfD Booster Fan A, Control Room AFU Booster Fan B, or the Control Room HVAC Heater because no additional loading is being cdded to the control circuit.
In addition, the new transformers are being purchased Safety-Related to meet the requirements of the existing transformer.
SAFET( EVALUATION SthMARY:
1.
The change described above has been analyzed to determine each accident or anticipated transient described in the UFSAR where any of the following is true:
The change alters the initial conditions used in the UFSAR analysis.
The changed structure, system or component is explicitly or implicitly assumed to function during or af ter the accident.
Operation or failure of the changed structure, system, or component could lead to tne accident.
The accidents wk cn meet these criteria are listed below:
LOCA UFSAR SECTION 15.6.5 MAIN STEAM LINE BREAK UFSAR SECTION 15.6.4 i
REFUELING ACCIDENT UFSAR SECTION 15.7.2 For each of these accidents, it has been determined that the change described above will r.ot increase the probability of an occurrence or the nsequence of the accident, or malfunction of enulpment important to
.c ety as previously evaluated in the UFSAR.
TS 112-
l SE-92-151 CONTD 2.
-The possibility for an accident or malfunction of a-different type than.
any previously evaluated in the UFSAP is not created because the component j
replacement has no adverse effect on plant operating modes or equipment R
functions.
The installation of the new ccntrol power transformers enhances the reliability of the B Train of Control Room HVAC, because it improves the control power voltace under degraded voltage conditions.
The l
new trarsformers have a lower impedance because the size 0/ the wire in the transformer windings is larger in diameter than that of the existing transformers.
Thie askes the new transformers more reliable because las:
heat will-be generated in the transformers during normal and degraded voltage conditions,-ensuring adequate-voltage to the control circuits.
The new transformers are being purchased Safety-Related to meet the requirements of the existing transformers.
Therefore, the component replacement will not create the possibility of an accident or malfunction of a type different from those evaluated in the UFSAR.
3.
The margin of safety, is not defined in the basis for any Technical Specification, therefore, the safety margin is not reduced.
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l TS 112
SE-92-153 ALARA Dose Reduction Request 92-095 (Loading Evaluation 92-019)
DESCRIPTION:
Mechanical Maintena ce is performing work on the waste collector ft!ter in the radioactive wr,te building.
They have constructed a temporary platform that will allow them to work on the top of the filter.
In order to minitaize the dose the maintenance personnel receive, lead shielding will be placed on the platform.
SAFETY EVALUATION St# NARY:
1.
The change described above has been analyzed to determine each accident or anticipated transient described in the UFSAR where any of the following is true:
The cnange alters the initial conditions used in the UFSAR analysis.
The changed structure, system or component is explicitly or implicitly assumed to function during or after the accident.
Operation or falli re of the chang:e structure, system, or component could lead to the accident.
The cccidents which meet these criteria are listed below:
I
- None,
~or each of these accidents, it nas been determined that the change described above will nct.ncrease the probability ot' an occurrence or the consequence of the accident, or malfunction of equipment important to safety as previously evaluated in the UFSAR.
2.
The possibility for an accident or mc1 function of a different type than any previcusly evalulted in the UFSAR is net created because the waste collector filter does not perform any function in any of the UFSAR 2crident analyses.
Such that if the maintenance platform fails, the plant r
l will not be placed in an unsafe condition.
Loading Evaluation 92-019 calculates the minimum weight the filtar vault plug supports can handle is 12,407 pounds.
The Height that the maintenance platform can safely support was calculated to be 9,256 pounos.
The weight of the platform, lead shielding and personnel was l
determined to be 5,600 pounds.
Because this weight is less th&n both the weight the supportt can handle and the weight the platform can support, this has been determined to be an acceptable load.
3.
The margin of safety, is not defined in the basis for any Technice)
Specifica".'on, therefore, the safety margin is not reduced.
TS 112 1
4 SE-92-154 UFSAR Chans0 DESCRIPTION:
Change two sections of the UFSAR from _" supply air vsmpers" to exhaust fan dampers'.
Sections to be revised are 6.2.3.2.2.
Secendary containment Isolation and Control and 9.4 Ventilation.
SAFETY EVALUATION StM4ARY:
1.
The change dcscribed above has been analyzed to determine eacn accident or anticipated transient described in the UFSAR where any of the following is true:
The change alttrs the initial conditions used in the UFSAR analysis.
The changed structure, system or component is explicitly or implicitly assumed to function Juring or after the accioeat.
Operation or failure of the changed structure, system, or component could lead to the accident.
The accidents whicl, meet thesa criteria are listed below:
None For each cf these accidents, it has been determined that the change described above will not increase the probability of an occurrence or the consequence of the accident, or malfunction of equipment important to safety as previously evaluated in the UFSAR.
2.
The possibility for an accident or malfunction of a different type than any-previously evaluated in the UFSAR is not created because no phystral change is being made to the plant the Reactor Building Ventilation System will function the same.
Therefore, tbc FSAR change does not create the possibility of an accident of a type different from those previously evaluated.
The as-built configuration is that the Reactor Building Exhaust fan dampers modulate to control DP in the building.
The UFSAR stated that the supply air dempers controlled DP in the building.
3.
The margin of safety, is not defined in the basis for any Technical Specification, therefore, the safety margin is not reduced.
1 TS 112 i
4 SE-92-155 Procedure Change Request for QCOP 202-14 DESC0!rTION:
This procedure change request (PCR) develops a new procedure to bypass Group I Isolation signals on the 1(2)-220-44 and 1(2)-220-45 Recirculation (recirc) System Sample Valves to allow for the extraction of a reactor coolant sample when required by a GSEP event.
SAFETY EVA1.UATION SlM4ARY:
1.
The change described above has been analyzed :; determine each accident or anticipated transient described in t:m IWSAR where any r.f the following is true:
The change alters the initial :onditions used in the UFSAR analysis.
The changed structure, system or component is explicitly or implicitly assumed to function during or after the accident.
Operation or failure of the changed structure, system, or component could lead to the accident.
The accidents which meet these criteria are listed below:
Dual Recirculation Pump Trip UFSAR SECTION 15.3.1.1 Recirculation Pnmp S91zure UFSAR SECTION 15.3.1.3 Recirculation Flow Controller
- Dec Flow UFSAR SECTION 15.3.2 Feedwater Controller Failure
- Zero Flow UFSAR SECTION 15.2.7 feedwater-Controller failure
- Max Flow UFSAR SECTION 15.1.2 Turbine Trip w/ Bypass UFSAR SECTION 5.2.2.2 Turbine Trip w/o Bypass UFSAR SECTION 15.2.3.1 Pressure Regulator Failure
- Full Closed UFSAR SECTION 15 2.1 Pressure Regulator Failure
- Full Open UFSAR SECTION 15.1.3 Loss of Condenser Vacuum UFSAR SECTION 15.2.5 Generator Load Rejection UFSAR SECTION 15.2.2 Loss of Offsite Power UFSAR SECTION 8.3 Loss of Feedwater Neater (s)
UFSAR SECTION 15.1.1 MSL Break Outside Containment OffAR SECTION 15.6.4 Large Break LOCA UFSAR SECTION 15.6.5 t
i for etch of these accidents, it has been determined that the change described above will not increase the probability of an occurrence or the consequence of the accident, or malfunction of equipment important to safety as previously evaluated in the UFSAR.
TS 112
z, SE-92-155 CONTD 2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the L;fSAR is not created because the procedure-is written as a response action to an event (including UFSAR accidents and transients) that result-in GSEP classification.
The procedure bypasses Group ! lsolation logic for the recirc sample valves.
The valves can.then be opened to draw a reactor coolant sample.
After the jumpers are pla.ed, the valvas can > manually openeu to take a sample or manually closed h.
the event cond)hons d1< :te.
Performanc.e of this procedt're will not degrade or negatively inepact the operation or integrity of any otaer structure, system, or component (SSC) assumed to. perform a tad to mitigate UFSAR postulated accidents 3,
The margin of safety, as defined in the. basis for any TLhnical Specification, is not reduced because the valves being operable under normal circumstances.
In a GSEP event with a Group I Isolation in place, these valves will be opened to obtain a Reactor coolant sample. After sampling, th: valve logic will be returned to normal and the valves reclosed. At all times during this procedure, these valves can be manually closed as required by plant conditions.
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TS 112-c _.
SE-91-383 Modification M04-0-88-006 DESCRIPTION:
Install a time delay relay in the first floor turbine building to reactor buildino interlock doors circulty and the 1/2 Diesel Generator Room.
SAFETY EVALUATION StM4ARY:
1.
The change described above has been analyzed to determine each accident or anticipated transient described in the UFSAR where any of the following 1s true:
The change alters the initial conditions used in the UFSAR analysis.
The changed structure, system or coanonent is explicitly or implicitly L
assumed to function during or after the accident.
Operation or failure of the changed structure, system, or component could lead to the accident.
The accidents which meet these criteria are listed below:
Instrument Line Break UFSAR SECTION 5,3.4.1 Refueling UFSAR SECTION 14.2.2 i
Loss of Coolant UFSAR SECTION 14.2.4 For each of these accidents, it has been determined that th? change described above will not increase the probability of an occurrence or the ccnsequence of the accident, or malfunction of equipment important to safety as previously evaluated in the UFSAR.
2.
The possibility for an accident or malfunction of a different type than any previously evaluated in the UFSAR is not created because the new relay is replacing the existing one with no change in function except the addition of a time delay to prevent two doors opening simultaneously.
No new accidents or malfunctions exist.
3.
The margin of safety, is not defined in the basis for any Technical Specification, therefore, the safeiy margin is not reduced.
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l TS 112 l
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M04-1-84-36G L H04-2-84-36G Fire Suppression and Detection DESCRIPTION:
Install fire suppression and detection systems in several areas of the plant.
LVALUATION:
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 fire suppression and detection is not classified as Safety Related in the FSAR.
Seismic installation of equipmer.t ensuies adequate operation of existing safety equipment and safety related equipment in the immediate trea of installation.
2.
The possibility for an accident or malfunction of a different type than any prev',ously evaluated in the 71nal Safety Analysis Report is not created because the installation does not interfere with any existing safety systems.
3.
The margin of safety, as defined in the basis fvr any Technical Specification is not reduced because suppression and detection is not Safety Related.
The reliability of the Fire Protection system is increased by providing this aoditional suppression and detection.
i TS 112
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