ML20154Q077

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6 to Fermi 2, Technical Requirements Manual, Vol I
ML20154Q077
Person / Time
Site: Fermi DTE Energy icon.png
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

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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s'.UU Please destroy or mar).; all revised, superseded, or cancelled documents -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' '

i 1

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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

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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

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3/4 6-21 19

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Blank 3/4 6-23 19 1

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3/4 3-1

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.3/4,3-2 25-3/4 6-26 19 3/4 3-3' 19 3/4 6-27 19

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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

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.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

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)

(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

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d.

Reactor Vessel Water Level - High, Level 8 NA

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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