ML20154M461

5 to Vol 1 of Fermi 2 Technical Requirements Manual

ML20154M461
Person / Time
Site:	Fermi
Issue date:	10/09/1998
From:	DETROIT EDISON CO.
To:
References
PROC-981009, NUDOCS 9810200298
Download: ML20154M461 (6)

Text

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DETROIT EDISON - FERM3 2 AUTOMATED RECORD MANAGEMENT DISTRIBUTION CONTROL LIST l 10/09/98 i To 00935 I

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Please destroy or mark all revised, superseded, or cancelled documents

-as such. CONTROLLED stamps must be voided by lining through and initialing.

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Detroit Edison EF2, C/O Info Mgmt 140 NOC, 6400 North Dixie Highway, Newport MI.48166. (734) 586-4338 OR (734) 586-4061 for questions or concerns.

Reft E51833 9810200298 981009 o' .

PDR ADOCK 05000341 e P pg ,

t LICENSING DOCUMENT TRANSMITTAL TECHNICAL REQUIREMENTS MANUAL, VOLUME 1 Instructions for Revision 25 dated 10/9/98 Immediately upon receipt of the item (s) below, please insert and/or remove the documents indicated. Destroy the removed documents. Be sure Revision 24 has been placed in TRM Vol I prior to inserting these pages.

Location Remove Insert Title Page Title Page Title Page Rev 24 10/8/98 Rev 25 10/9/98 List of Effective Pages LEP-1, Rev. 24 10/98 LEP-1, Rev. 25 10/98 LEP-2, Rev. 24 10/98 LEP-2, Rev. 25 10/98 Section 3.3 Page 3/4 3-2 Rev 19 05/98 Page 3/4 3-2 Rev 25 10/98 END O

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l FERMI 2 - TECHNICAL REOUIREMENTS MANUAL l LIST OF EFFECTIVE-PAGES

( Page U. Revision Page Revision l- CORE OPERATING LIMITS REPORT. 9A.6-26 TRM REV 15 COLR 7, Revision 0- -9A.6-27 3 9A.6-28 3 Notati'on Page

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,Y TRM - TABLE 3.3.1-2 l

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{v _(UFSAR TABLE 7.2-4)

REACTOR PROTECTION SYSTEM RESPONSE TIMES

-FUNCTIONAL UNIT -RESPONSE TIME (Seconds)

1. Intermediate Range Monitors:

a. Neutron Flux - High NA

j. b. Inoperative NA

2. . Average Power Range Monitor *:

a. Neutron Flux - Upscale, Setdown NA

b. Simulated Thermal Power - Upscale NA

c. Neutron Flux - Upscale HA

d. Inoperative NA e; 2-out-of-4 Trip Voters s0.05*

3. Reactor Vessel Steam Dome Pressure - High s 0.55'

4. Reactor Vessel Low Water Level - Level _3 s 1.05'

5. Main Steam Line Isolation ~ Valve - Closure s 0.06

6. ~ Main Steam Line Radiation - High NA

7. Drywell Pressure - High NA

.p-i 8.

~

w V Scram Discharge Volume Water Level - High

'a. Float Switch NA

b. Level Transmitter NA

9. Turbine Stop Valve - Closure s 0.06

10. Turbine Control Valve Fast Closure s 0.08***

11. Reactor Mode Switch Shutdown Position NA

-12. Manual Scram NA

13. Deleted

• Neutron detectors, APRM channel and 2-out-of-4 Trip Voter digital electronics are exempt from response time testing. Response time shall.be measured from activation of the 2-out-of-4 Trip Voter output relay.

• • • Measured from deenergization of K-37 relay which inputs the turbine control valve closure signal to the RPS.

1. .The sensor response time need not be measured and may be assumed to be the design sensor 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

.t'~N response time value.

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TRM Vol. I 3/4 3-2 REV 25 10/98