ML20205H509

Proposed Tech Spec Section 3/4.3.2.2,Table 3.3-13 Re Steam & Feedwater Rupture Control Sys Response Times & Bases Sections 3/4.3.1 & 3/4.3.2 Re Reactor Protection Sys & Safety Sys Instrumentation

ML20205H509
Person / Time
Site:	Davis Besse
Issue date:	03/23/1987
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20205H491	List: ML20205H487 ML20205H494 ML20205H509
References
1354, NUDOCS 8704010081
Download: ML20205H509 (4)

Text

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Dockst No,, 50-346 +

a Licensa NO. NPF-3 '-

l Serial Noh 1354 l':?"" lNc0RMATl0N ONI.Y l i

-3 INSTRUMENTATION STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION j LIMITING CONDITION FOR OPERATION 3.3.2.2 The Steam and Feedwater Rupture Control System (SFRCS) instrumen-tation channels shown in Table 3.3-11 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-12 and with RESPONSE TIMES as shown in Table 3.3-13.

,' APPLICABILITY: MODES p 2 and 3.

ACTION:

O a. With a SFRCS instrumentation channel trip setpoint less con-servative than the value shown in the Allowable Values column of Table 3.3-12, declare the channel ~ inoperable and apply the applicable ACTION requirement of Table 3.3-11, until the

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channel is restored to OPERABLE status withathe trip setpoint adjusted consistent with the Trip Setpoint value.

b. With a SFRCS instrumentation channel inoperable, take the

action shown in Table 3.3-11.

i SURVEILLANCE REQUIREMENTS -

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4. 3. 2. 2.1 Each SFRCS instrumentation channel shall be demonstrated <

I OPERABLE by the performance of the CHANNEL CHECK, CHANNEli CALIBRATION and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies shown in Table 4.3-11. '

74.3.2.2.2 The log'ic for the bypasses s rad be demonstrated OPCRABLE during the at power CHANNEL FUNCTl W , T of channels affected by bypass operation. The total bypass runcma shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CAllBRATION testing of each channel affected by bypass operation. j l

4.3.2.2.3 ..Tha STEAM AND FEE 0 WATER RUPTURE CONTROL SYSTEM RESPONSE TIME of ea~ch SFRCS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least 'one channel per function such3that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific SFRCS function as shown in the " Total No. of Channels" Column

( of Table 3.3-11. -

8704010081 870323 PDR ADOCK 05000346 l ps PDR i

ll DAVIS-BESSE, UNIT 1 3/4 3-23 x -- . .-. - - . - - - - - - -

'Dockret No. 50-346

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Licinr3 No. NPF-3 Stri 1 No. 1354 Attrchment 3

c. Pag 2 2 TABLE 3.3-13 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIMES s

ACTUATED EQUIPMENT RESPONSE TIME IN SECONDS

1. Auxiliary Feed Pump 5 40

2. Main Steam Isolation Valves 56

3. Main Feedwater Valves

a. Main Control < 8

b. Startup Control {13

c. Stop Valve 5 16

4. Turbine Stop Valves 5 /1 l

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l DAVIS-BESSE UNIT 1 3/4 3-29 Amendment No. I t

i. Docke't No. 50-346

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• i3/4.3 INSTRUSTA7101 ,

Attachment 3

, Page 3 * *

.. BASES J 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND -

l 5AtuI 5YMEM INSTRUMENTATION __

The OPERA 81LITY of the RPSt SFAS and SFRCS instrumentation systems ensure that 1) the associated action and/or trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint 2) the specified coincidence logic is maintained 3) sufficient redundancy is' maintained to permit a channel to be out of

service for testing or maintenance, and 4) sufficient system functional capability is avat able for RPS, SFAS and SFRCS purposes free diverse parameters.

The OPERASILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and altigation of accident and transient con- ,

dit. ions. The integrated operation of each of these systems is consistent with the ,ssumptions a used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests

' perfonned at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies i

provides assurance that the APS, SFAS, and SFRCS action function associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential.

overlapping or total channel test seasurements provided that such test demonstrate the total channel response time as defined. Sensor response 4

time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sehsors with certified response times.

An SFRCS channel consists of 1) the sensing device (s),2) associated logic and output relays (including Isolation of Main Feedwater Non Essential INsEET Valves and Turbine Trip), and 3) powe,r sources.

"A" M Safety-grade anticipatory reactor trip is initiated by a turitine trip (above 25 percent of RATED THERMANL POWER) or trip of both main feedwater pump turbines. This anticipatory tr.ip will operate in advance of the reactor coolant systen high pressure reactor trip to reduce the peaka reactor coolant systes pressure and thus reduce challenges to the power operated relief valve. This anticipatory reactor trip system was installed to satisfy Itas II.K.2.10 of NUREG-0737.

DAVIS-8 ESSE Unit 1 I3/43-1 Amendment No. 73

I Deckat No. 50-346 License No. NPF-3 Sarial No. 1354 Attachment 3 Page 4 Insert *A" The SFRCS response time for the turbine stop valve closure is based on the combined response times of main steam line low pressure sensors, logic cabinet delay for main steam line low pressure signals and closure time of the turbine stop valves. This SFRCS response time ensures that the auxiliary feedwater to the unaffected steam generator will not be isolated due to a SFRCS low pressure trip during a main steam line break accident.

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