ML20063H814
| ML20063H814 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/11/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-940211, NUDOCS 9402220219 | |
| Download: ML20063H814 (6) | |
Text
4
^
OCAP 500-4 UNIT l'(2 )
REVISION 2 ATTACHMENT E (Page 1 of 2) d QUAD CITIES NUCLEAR POWER STATION-PROCEDURE MANUAL REVISION RECEIPT FORM NRC -C0py 223 DOC CONTROL DESK' D'C. 3 COVERSHEET
- S"I""
...anual Holder REMOVE-INSERT:
1 Document -
Rev.
Document Rev.
02P
/2a-6 J6 (DEP /26 -O
/6
'~
/2n -776 A
,/ p n - 7 / 6 3
O l
I Continued on other side.
181103
'\\
' Manual Update Completed:
- Return to Quad Cities Station Procedure Distribution Clerk **-
jsR'*"o8clo*y2y4 l
i s
=n
-,a QEP 120.
Revision 16-O February 1994 TECHNICAL DIRECTOR
(
OEP 120-0 Technical Director Rev._16.
02-11-94 OEP 120-1 l
Technical Director Implementing Procedure Rev. 9-03-16 OEP 120-2 Core Damage Assessment Rev. 5 12-09-92 OEP 120-S1 Technical Director Alert Checklist Rev. 5 03-16-92 OEP 120-S2 Technical Director Site Area Emergency Checklist
-Rev. 3 03-16 ;
OEP 120-S3 Technical Director General l
Emergency Checklist Rev. 4 09-11.-92 OEP 120-S4 Technical Director Downgrade, Termination, and Recovery Checklist Rev. 2 03-01-91 OEP 120-55 Core Damage Assessment Worksheet Rev. 3 09-21 OEP 120-S6 Drywell Radiation Monitor Time Dependent Correr. tion Worksheet Rev. 4 02-26-92 OEP 120-T1 Shift Turnover Briefing Rev. 3 03-01-91 OEP 120-T2 Sequence of Analysis for Estimation of Core Damage Rev. 1 08-04-88 OEP 120-T3 Table of ratios of Isotopes in Core Inventory and Fuel Gap Rev. 1 08-04-88 OEP 120-T4 Table of BWR Plant Parameters Rev. 1 08-04-88
- XppnovED FEB 111994' INDEX 58 1
QEP_120-0'.
'Rev'ision 16' O
OEP 120-T5 Relationship Between Fission Product Concentration and Core Damage Rev. 1 08-04-88 OEP 120-T6 Sample Calculation of Fission Product Inventory Correction Factor Rev.
l.-
08-04-88 OEP 120-T7 Quad Cities Station, Percent Core Damage Versus Containment Radiation Readings (Uncorrected)
Rev. 2 L09-27-91 OEP 120-T8 Hydrogen Concentration for Mark I/II'and III Containments as a Function of Metal-Water Reaction Rev. 1 08-04-88 OEP 120-T9
.4 Time Dependent Drywell Radiation 08-04 "
Correction Factors
.Rev. 1 1
~
OEP 120-T10 Key Point History Listing
<Rev.'3 02-11-94 0EP 120-T11 Core Inventory of Major Fission Products j
in a Reference Plant Operated at
.I 3651 MW, for Three Years Rev. 1 08-04-88 q
OEP 120-T12 Quad Cities Station Percent Clad Damage Versus Containment Radiation Readings (Uncorrected)
Rev. 1 09-21-92
{
ApppovED Q
FEB 111994 (final)'
INDEX 58 2
i i
PROCEDURE:
QEP 120-1 QEP 120-T10 Revision 3 KEY POINT HISTORY LISTING February _1993 1
l Point History ID #-
System Range Unit 1 Unit 2 A.
fuel Claddina Integrity / Reactor Coolant System 1.
Peactor Water Level Indicators.
a.
Narrow GEMAC A 0 to 60 in C100 C200 b.
Narrow 0 to 60 in C101 C201 4
c.
Yarway A
-60 to 60 in, C102
'C202 d.
Yarway 8
-60 to 60 in C103' C203 e.
Refuel Zone
-42 to'358 in C104 C204 f.
Fuel Zone A
-243 to 57 in C105-C205 g.
Fuel Zone B
-243 to 57 in-C106 C206 2.
Reactor Water Temperature Indicators a.
Reactor Metal Point 1 0 to 6000F C113 C213-b.
Reactor Metal Point 2 0 to 6000F C114 C214 c.
Reactor Metal Point 3 0.to 600of C115 C215-d.
Reactor Metal Point 4 0 to 600oF
'C116 C216-e.
Reactor Metal Point 5 0 to 600of C117 C217 f.
Reactor Metal Point 6 0 to 600oF C118 C218 g.
Reactor Metal Point 7-O to 600of C119 C219 h.
Reactor Metal Point 8 0 to 600oF C120 C220 1.
Rx CLUP Discharge Temp 0 to 600oF-C124-C224 O
j.
RHR Heat Exchanger A 0 to 600oF C183-C283 Inlet Temp k.
RHR Heat Exchanger B 0 to 600of-C184 C284 Inlet Temp 1.
Recire Water Temp A1 420 to 570oF W126 W226 m.
Recirc Water Temp A2 420 to 570oF W127 W227 n.
Recire Water Temp B1 420 to 570oF W128.
W228 o.
Recirc Water Temp B2 420 to 570oF W129 W229 3.
Reactor Water Flow Indicators a.
Total Recirc Flow 0 to 43.55 m#/hr C127 C227 b.
Total Jet Pump Flow 0 to 125 m#/hr.
C128 C228 c.
RHR Flow to Reactor 0 to 22,000 GPM C179 C279:
Loop A d.
RHR Flow to Reactor C ds 22,000 GPM C180 C280 Loop B e.
. Core Spray Loop A Flow 0 to 6000 GPM C192 C292 f.
Core Spray Loop B Flow 0 to 6000_GPM C193 C293-g.
HPCI' Discharge Flow 0 to 6000 GPM C195
.C295-h.
RCIC Flow 0 to 500 GPM C197 C297 i.
Reactor Feed Water 0 to 6 m#/hr F122 F222 Flow A j.
Reactor Feed Water 0 to 6 m#/hr F123 F223 Flow B k.
Reactor Feed Water
-0 to 6 m#/hr F124 F224 O
Flow C ApppovEd FEB 111994 1-
QEP 120-T10 Revision 3 Point History ID #
p System Ranae Unit 1 Unit 2 B.
Reactor Coolant System Intearity 1.
Reactor Pressure a.
Intermediate O to 1200 psig C109 C209 b.
Intermediate Range B 0 to 1200 psig-C110 C210 c.
Wide Range 0 to 1500 psig C111 C211 d.
Narrow Range 950 to 1050 psig C112 C212 2.
Torus Water Level a.
Narrow Range
-25 to 25 in C171 C271 b.
Wide Range A 0 to 30 ft. Wtr C172 C272 c.
Wide Range B 27.45 to 384.75 in C173 C273 3.
Torus Water Temperature a.
Temperature A 0 to 400oF C169 C269 b.
Temperature B 0 to 400oF C170 C270 4.
Torus Radiation Monitor a.
Monitor A 1 to 10E6 R/hr R124 R224' b.
Monitor B 1 to 10E6 R/hr R125 R225 (O/
5.
Relief and Safety Valve Positions (203) a.
Valve 4G closed /open G511 G611 b.
Valve 4F closed /open G512 G612 c.
Valve 4E closed /open G513 G613 d.
Valve 4D closed /open G514 G614 e.
Valve 4C closed /open G515 G615 f.
Valve 4B closed /open G516 G616 g.
Valve 4A closed /open G517 G617 C.
Containment Integrity Indicators 1.
Containment Pressure a.
Narrow Range
-2.5 to 5 psig C161 C261 b.
Intermediate Range O to 75 usig C162 C262 c.
Wide Range
-5 to 250 psig C163 C263 d.
Containment Isolation Trip / Reset C593 C693-GP3 e.
Containment Isolation Trip / Reset C596 C696 GP2 f.
Containment High Reset / Trip W512 W612 Pressure A g.
Containment High Reset / Trip W513 W613 p
Pressure B
()
h.
Containment High Reset / Trip W514 W614 Pressure C ADPRbVED' FEB 111994 2
4 QEP 120-T10 Revision 3 Point History ID #-
System Range Unit 1 Unit 2 O
i.
Containment High Reset / Trip W515 W615-Pressure D 2.
Hydrogen Concentrations a.
Drywell H, Conc.
O to 20%
C167 C267 b.
Torus H, Conc.
O to 20%
C168 C268 3.
Drywell Radiation Monitor (Uncorrected. See QEP 120-S6 for correction factor.s.)
a.
Monitor A 1 to IE8 R/hr R123 R223 b.
-Monitor B 1 to IE8 R/hr R122 R222 4.
Release Point Monitoring a.
Rx Bldg Vent Stack Noble Gas (1)
Low Range (SPING) 2E-4 to 17.9 PCi/cc R127-R127 (2)
Interm. Rg(SPING) 1.4E-2 to.1.4E2 cpm R128 R128
-(3)
High Range (SA-9) 10'to IES cpm R129 R129-(4)
Stack Flow 0 to 400 KCFM' R135 R135 (5)
DW Vent V1v open/close F543 F643 (AO-1601-23) b.
Main Chimney (1)
Low Range 2E-4 to 17.9 pCi/cc-R130 R130 (SPING)
(2)
Interm Range 1.4E-2 to 1.4E2 Ci/cc R131 R131 (SPING)
(3)
Wide Range 10 to IES Ci/cc, R132
.R132 (SA-9)
(4)
Activity 0.1 to 10E6 cps R133 R233 Monitor (GE)
(5)
Stack Flow 0 to 440 KCFM R134 R134 (6)
Vent to SGTS open/close F533 F633 (AO-1601-63)
(7)
SGTS Train 0 to 5000 CFM R136' R236 A Flow (R236) B Flow (R136)
(8)
Charcoal Bed I to IE7 R/hr R110 R210 Vault Radiation c.
Radwaste Effluent 0.1 to IE7 cps R120-R120 Radiation d.
Service Water Effluent 0.1 to 1000 cps R119 R219 Radiation XPppp0VEd FEB 111994 -
(final) l l
_