ML20154Q077
| ML20154Q077 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/15/1998 |
| From: | DETROIT EDISON CO. |
| To: | |
| References | |
| PROC-981015, NUDOCS 9810230132 | |
| Download: ML20154Q077 (6) | |
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DETROIT EDISON - FERMI 2 j..
-AUTOMATED RECORD MANAGEMENT DISTRIBUTION CONTROL LIST 10/15/98 Tor.00935 US.NRC PAGE 3
. DOCUMENT CNTRL DESK l
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WASHINGTON, DC 20555 Media: 8 1/2 X 11' i
Number Cnt Issue i
DTC Doc. Serial Number Page Rev Copies Lvl Date Sec Status TMTRM TRM VOL I 26 11 IR 10/13/98 AFC i
J i
0\\
r n n > m r..
s'.UU Please destroy or mar).; all revised, superseded, or cancelled documents -
4
.cs such.
CONTROLLED stamps must be voided by lining through and initialing.
.....................................................=.................=.......
1 Detroit Edison EF2,. C/O Info Mgmt 140 NOC, 6400 North Dixie Highway,
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LNewport MI 48166.
734) 586-4338 OR (734) 586-4061 for questions or concerns.
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Ref: E51833 i,
98102301?F 981015 I
.PDR-ADOCK 05000341
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LICENSING DOCUMENT TRANSMITTAL
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TECHNICAL REQUIREMENTS MANUAL, VOLUME 1 Instructions for Revision 26 dated 10/13/98 Immediately upon receipt of the item (s) below, please insert and/or remove the documents indicated. Destroy the removed documents. Be sure Revision 25 has been placed in TRM Vol I prior to inserting these pages.
Location Remove Insert Title Page Title Page Title Page Rev 25 10/9/98 Rev 26 10/13/98 List of Effective Pages LEP-1, Rev. 25 10/98 LEP-1, Rev. 26 10/98 LEP-2, Rev. 25 10/98 LEP-2, Rev. 26 10/98 Section 3.3 Page 3/4 3-9 Rev 19 05/98 Page 3/4 3-9 Rev 26 10/98 t' '
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IO Fermi 2 Technical
. Requirements Manual O
Volume I Detroit Edison ARMS-INFORMATION DTC:TMTRM l File: 1754 DSN: TRM VOLI l Rev: 26 Date 10/13/98 Recipient
(/ _ fsf' J
FERMI'2"- TECHNICAL REOUIREMENTS MANUAL 7
-LIST-OF EFFECTIVE PAGES j
Page
. Revision' Page Revision 1:
- 19 -
3/4 6-1 19 2
19 3/4 6-2 19
.i 23x 3/4 6-3 19 Lii '
20 3/4 6-4 19 lii 23-3/4 6-5 19 iv' 20' 3/4 6-6
.19-v' 20-3/4 6-7 19 l
3/4 6-8 19 TECHNICAL REOUIREMENTS-
~3/4-6-9 19 3/4 6-10.
19
.1-1_
-19
_3/4-6-11 19
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1-2' 19 3/4 6-12 19 1-3 19.
3/4 6-13 19 p
'l-4 19 3/4-6-14 19 2-1 Blank 3/4 6-15 L19 4
3/4-0-1 19 3/4 6-16 19, 3/4-0-2 19 3/4 6-17 19 3/4f0 19 3/4-6 19 3/470-4 R19
~3/4 6-19' 19 3/4 0-5 19 3/4 6-20 19
.3/4-0-6_
19_
3/4 6-21 19
~3/4 0-7' 19-
.'3/4 6-22 19 3/4 1-1.-
Blank 3/4 6-23 19 1
'L 3/4;2-1 Blank 3/4 6-24 19
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3/4 3-1
_19 3/4 6-25 19-
.3/4,3-2 25-3/4 6-26 19 3/4 3-3' 19 3/4 6-27 19
'3/4 3-4 19
- 3/4 6-28 19 13 / 4 : 3 - 5.
22 3/4 6-29 19 3/4 3 19f 3/4 7-1 Blank
.3/4 3-7 19 3/4 8-1 19 3/4 3-8 19 3/4 8-2 19.
'3/413-9 26 3/4 8-3 19 3/413-10 19 3/4 8-4 19
.3/4-3-11 20 3/4 8-5 23 3/4 3 21-3/4 8-5 19 3/4:3-13 20-3/4.9-1 Blank
- 3/4.3-14 20 3/4 10-1 Blank l
3 /4 -: 3 -.15 20 3/4 11-1 Blank l3/4J3-16 20 3/4 12-1 Blank 3/4 3-171 20 5-1 Blank E
-3/4 3-18 20 6-1 Blank
'3/4 3-19 20
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'3/4 3-20' 20 3/413 '
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3 /4 :-3'-2 2 20-2 3/413-23
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Blank
.TRM-Vol. I:
.LEP-1 REV '26 10/98 i.
l
- s FERMI 2 - TECHNICAL REOUIREMENTS MANUAL
. LIST OF EFFECTIVE PAGES 7_q)
Pace Revision Page Revision
-CORE OPERATING LIMITS REPORT 9A.6-26
'TRM REV 15
'COLR 7, Revision 0 9A.6-27 3
9A.6-28 3
Notation Page
-1.
0 2
0-3 0
4 0
5 0
.6 0
7 0
8 0
9 0
10 0
11 0
12 0
13 0
14 0
15 0
FIRE PROTECTION LIMITING f'"
CONDITIONS FOR OPERATION (3/
AND SURVEILLANCE REOUREMENTS 9A 6-1 3
9A.6-2 6
9A.6-3 5
9A.6-4 5
9A 6-5 TRM REV 17 9A.6-6 TRM REV 17 9A.6-7 TRM REV 17 9A.6-8 6
9A.6-9 TRM REV 17 9A.6-10 6a 9A.6-11 6a 9A.6-12 6
'9A.6-13 6
.9A.6 3 9A.6-15 3
9A.6-16 3
9A.6-17 3
9A.6-18 3
9A.6-19 6
9A.6-20 3
9A.6-21 TRM REV 7 9A.6-22 3
9A.6-23 TRM REV 8
[,')
9A.6-24 TRM REV 8 v
9A.6-25 TRM REV 15 TRM Vol. I LEP-2 REV 26 10/98
a e
4*
TRM - TABLE 3.3.3-3
.~s
/
)
(UFSAR TABLE - 7.3-11)
\\s /
EMERGENCY CORE COOLING SYSTEM RESPONSE TIMES TRIP FUNCTION.
RESPONSE TIME (Seconds) 1.
CORE SPRAY SYSTEM a.
Reactor Vessel Low Water Level - Level 1 s 30**
b.
Drywell Pressure - High s 30**
c.
Reactor Steam Dome Pressure - Low NA*
d.
Manual Initiation NA 2.
LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.
Reactor Vessel Low Water Level - Level 1 1 72**
b.
Drywell Pressure - High s 72**
c.
Reactor Steam Dome Pressure - Low NA*
d.
Reactor Vessel Low Water Level - Level 2 NA e.
Reactor Steam Dome Pressure - Low NA f.
Riser Differential Pressure - High NA g.
Recirculation Pump Differential Pressure -
NA High h.
Manual Initiation NA 3.
HIGH PRESSURE COOLANT INJECTION SYSTEM a.
Reactor Vessel Low Water Level - Level 2 s 30**
b.
Drywell Pressure - High NA
,~g c.
Condensate Storage Tank Level - Low NA
/
d.
Reactor Vessel Water Level - High, Level 8 NA
\\-
e.
Suppression Pool Water Level - High NA f.
Manual Initiation NA
+
4.
AUTOMATIC DEPRESSURIZATION SYSTEM a.
Reactor Vessel Low Water Level - Level 1 NA b.
Drywell Pressure - High NA c.
ADS Timer NA d.
Core Spray Pump Discharge Pressure - High NA e.
RHR LPCI Mode Pump Discharge Pressure - High NA f.
Reactor Vessel Low Water Level - Level 3 NA g.
Manual Initiation NA h.
Drywell Pressure - High Bypass Timer NA 1.
Manual Inhibit NA 5.
LOSS OF POWER a.
4.16 kV Emergency Bus Undervoltage (Loss i
of Voltage)
NA l
b.
'4.16 kV Emergency Bus Undervoltage (Degraded Voltage)
NA These are permissive signals only.
They do not activate ECCS initiation.
- ECCS actuation instrumentation response time need not be measured and r~N may be assumed to be the design instrumentation response time.
Prior
)
to return to service of a new transmitter or following refurbishment of a transmitter (e.g., sensor cell or variable damping components),
a hydraulic response time test will be performed to determine an initial sensor-specific response time value.
TRM Vol. I 3/4 3-9 REV 26 10/98