Text

Proposed Tech Specs Revising Section 3/4.3.2, Safety Sys Instrumentation,Steam & Feedwater Rupture Control Sys Instrumentation & Table 3.31-1, Steam & Feedwater Rupture Control Sys Instrumentation
	ML20196G218
Person / Time
Site:	Davis Besse
Issue date:	02/29/1988
From:	; TOLEDO EDISON CO.
To:	;
Shared Package
ML20196G207	List: ML20196G201; ML20196G210; ML20196G218;
References
	NUDOCS 8803070083
	Download: ML20196G218 (9)
	v • d • e

- . . _ _ .._. _

~ _ __

nockst No.,50-346' Licinin No. NPF-3 Strimi yo'. 1461 3 ge i

FORINFDMilDN DN!Y :

INSTRUMENTATION STEAM AND FEE 0 WATER RUPTURE CONTROL SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.2 The Steam and Feedwater Rupture Control System (SFRCS) instr' amen-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 1, 2 and 3.

ACTION:

i

" (

a. With a SFRCS instrumentation channel trip setpoint less con-servative than the value shown in the Allowable Values column .

1 of Table 3.3-12, declare the channel inoperable and apply- the applicable ACTION requirement of Table 3.3-11, until the channel is restored to OPERABLE status with-the trip setpoint adjusted consistent with the Trty Setpoint value. .

b. With a SFRCS instrumentation channel inoperable, take the '

action shown in Table 3.3-11. i i

SURVEILLANCE REQUIREMENTS

i l 1

4. 3. 2. 2.1 Each SFRCS instrumentation channel shall be demonstrated j' OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION '

and CHANNEL FUNCTIONAL TEST during the MODES and at the frequencies

{ shown in Table 4.3-11.

4 4.3.2.2.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by i

bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing l of each channel affected by bypass operation.

4.3.2.2.3 The STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME of each SFRCS function shall be demonstrated to be within the limit at l 1 east once per 18 months. Each test shall include at least one channel I l per function such that all channels are tested at least once every N l i

times 18 months where M is the total number of redundant channels in a j specific SFRCS function as shown in the "Total No. of Channels" Column i

of Table 3.3-11.

8803070083 880229 DR ADOCK 0500 6 l ll DAVIS-BESSE, UNIT 1 3/4 3-23

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~7W we TA8LE ..> .a h STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION G .

4 .

G MINIMINI M

TOTAL NO. CHANNELS CHANNELS FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE ACTION E

Q 1. Main Steam Pressure

- Low Instrument Channels

2 1 2 13#

a. PS 3689A Steam Line 1 Channel 1 PS 36898 Steam Line 1 Channel I

b. PS 3689C Steam Line 2 Channel 1 m ,q PS 36890 Steam Line 2 Channel 1 y ,;l @g

<= e . g =

$I "llClg ==3

c. PS 3689E Steam Line 1 Channel 1 g _ C#

g PS 3689F Steam Line 1 Channel 1 i g?! I g

2%$ 75 N Y d. PS 3689G Steam Line 2 Channel 1 e 8 c, @>

2 PS-3689H Steam Line 2 Channel I w 8 g. ym m

mo FT=2

e. PS 3687A Steam Line 2 Channel 2 ,[G G@N PS 36878 Steam Line 2 Channel 2' ggg mm Qq

.. ~ ~

f. PS 3687C Steam Line 1 Channel 2 5"5 O PS 3687D Steam Line 1 Channel 2 gh 2 M s", 5 ~

g. PS 3687E Steam Line 2 Channel 2 Zr m C PS 3687F Steam Line 2 Channel 2

h. PS 3687G Steam Line 1 Channel 2 kC PS 368711 Steam Line 1 Channel 2 9

% ::- u> e p E R.n 2 o

w R C U ll? -

gn Pdy[

TABLE _3.3-11 (Continued)_ , *jgy

-mw STEAM AND FEEtWATER RUPTURE CONTROL SYSTEM INSTRUE NTATION O$i i G MIN!mM N TOTAL. NO. CHANNELS CHANNELS l'

FUNCTIONAL UNIT- t OF CHANNELS TO TRIP OPERABLE ACTION g ,

.4 2. Feedwater/ Steam Generator :

i

- Differential Pressure - High

Instrument Channels 2 1 2 13#

a. PDS 2685A -Feedwater/ Steam Generator 2 Channel 2 -

PDS 26858 Feedwater/ Steam Generator 2 Channel 2~

b. PDS 2635C Feedwater/ Steam Generator 2 Channel 1 l PDS 26850 Feedwater/ Steam Generator 2 Channel 1 .g R*

c. PDS 2686A Feedwater/ Steam Generator 1 Channel 1 i

, w PDS 26868 Feedwater/ Steam Generator 1 Channel 1 c. - .

C/lllr b d. PDS 2686C Feedwater/ Steam Generator 1 Channel 2 g

POS 26860 Feedwater/ Steam Generator 1 Channel 2 gp

3. Steam Generator "-

. Level - Low Instrument Channels 2 1 2

a. LSLL SP988 Steam Generator 1 Channel 1 LSLL SP989 Steam Generator 1 Channel 1 b@M I

gC D g .

) 3 b. LSLL SP9A6 Steam Generator 2 Channel 1 O ! =

l g LSLL SP9A7 Steam Generator 2 Channel 1 g 3 ,

i s E P P1 J " c. -8.SLL SP9AS Steam Generator 2 Channel 2 Qg 3 o g

} ,

LSti. SP9A9 Steam Generator 2 Channel 2 i i j &

O j % , ' ~/

_ . _ . =_. - -- . - . .. - -

- Y '

WWCC8:

ECZE>

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E *

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~tzs TABLE 3.3-11 (Continued) . $ q 6i k;; STEAM AMD FEEDWATER RUPTURE CONTROL SYSTEM INSTRUMENTATION MINIftM O TOTALi:0. CHANNELS CHANNELS M

'- 0F CHANNELS TO TRIP OPERABLE ACTION FUNCTIONAL UNIT.

g

~~.

-- 3. Steam Generator

- Level - Iow Instrument Channels (continued)

d. LSLL SP986 Steam Generator 1 Channel 2 LSLL SP937 Steam Generator 1 Channel 2

4. Loss cf RCP Channels 2 1 2 138 i

5. Manual Initiation (Push buttoas)

Steam Pressure - Low 4 2 4 14 a.

Y b. Level Steam Generator - Low 2 1 2 14 Feedwater a P - High 2 2 14 2 c. 1 2 1 2 14 ,g

d. Loss of RCP's O2 w

w- M i E

, EF , sE E

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Docket No. 50-346 Licente'No. NPF-3 Serial No.!1461 AD0lil0NAL CHANGES PREVIOUSLY Attachment 3

PROPOSED BY LETTER Page 5 , S0fial No. ,_]d Date_II/2/97 o 3 TABLE 3.3-11 (Continued) ,

TABLENOTAT!g 7oo

May be bypassed when steam pressure is below 650 psig. Bypass shall be automatically removed when the steam pressure exr.eeds fr50 psig.

750 i The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 13 With the nunber of OPERABLE Channels one less than the Total flunber of Channels, startup and/or power operation ,

may proceed until perfomance of the next required CHANNEL FUNCTI0fiAL TEST provided the incperable sec-tion of the channel is placed in the tripped condition '

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . .

l l

4 DAVIS-BESSE. UNIT 1 3/4 3-27 Amendment No. 31 l l

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- " ;* xE o TABLE 3.3-12 Cy$

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we g STEAM AND FEEDWATER RUPTURE 00kTa0L SYSTEM

,1, th5TidHENTATT5FTATF 5Eip01NTs Q

v.

s.

FUNCTIONAL UNITS TRIP $tTPOINTS ALLOWASLE VALUES E

y 1. Steam Line Pressure - Low > 591.5 psig > 591.6 psig*

-, se 1586.6 psig**

2. Steam Generator Level - Low III > 26" H 2O > 20*.H20*

a > is.ar n zo.*

3. Steam Generator Feedwater E5 ~

DifforentialPressure-High(2) < 197.5 psid 3y; i 97.51 psid*

2gg 2 i 199.5 psid**

< 1384.6 emps I I

4. Reactor Coolant Pumps - Loss of High 1 1384.6 amps b

{ Low 1 106.5 anos E' = { 10s.5 amps 8 Y

D*$

Si 5 m --4 '

'g G mg W##

IIIMeasured above the lower steam generator tubesheet, q (2)Where differentisi pressure is steam generator minait fe* Muster pressure. Q 3D ;

Allowable Value for CHANNEL FUNCTIONAL TEST NE 5

Allowable Value for CliANNEL eJLLISRATI0li M- m Allowable Value for CHANNEL FUNCTIONAL TEST and CHANNEL CAllthAT!0ft N

f, CD

=

gag C CD CD ~g~~

_Q JE m QC t

Dockst No. 50-346 L'ic:nna No. NPF-3 a 4

Ssiini No. 1461 TABLE 3.3-13 1 i

STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIMES ACTUATED EQUIPMENT RESPONSE TIME IN SECONDS

1. Auxiliary Feed Pump 10 4

2. Main Steam Isolation Valves 16 l

3. Main Feedwater Valves

a. Main Control <8

b. Startup Control 7 13 :

c. Stop Valve 7, 16

4. Turbine Stop Valves <6 nDDlil0NAL CHANGES PREVIOUSLY PROPOSED BY LETTER SerialNo. l36.7_ 03teJ[JS[$1 ADDlil0NAL CHANGES PREVl00 Sty '

PROPOSED Serial No__ I 35y

__ g,te3 BY , LETTER,,

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i DAVIS-BESSE. UNIT 1 3/4 3-29 i

Docket No. 50-366

' Lic'ense No. NPF-3 Gerial*No. 1461 5. s HUyayby h h Attach:nent 3 -

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Docket Uo'.~50-346 ,

Licpnse No. NPF-3 THEi a r !

Serial No. 1461 gg g g' ;

'Attachent 3 Page 9 3/4,7 [ N ST RU. MENT AT ICN_

i BASES I

l 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND bi@ hl I 515ILM INSTRUMENTATION l

y e The OPERABILITY of the RPS, SFAS and SFRCS instrumentation systams !

d M ensure that 1) the associated action and/or trip will be initiated when :

8 4 the parameter :nonitored by each channel or combination thereof exceeds 5 5 ", its setpoint, 2) the specified coincidence logic is maintained 3) i EEw sufficient redundancy is maintained to permit a channel to be out of I m" service for testing or maintenance. and 4) sufficient system functional '

yE

<o capability is available for RPS, SFAS and SFRC3 purposes from diverse parameters.

5Mr

The OPERA 8!LITY of these systems is required to provide the overall 5g$I reliability, redundance and diversity assumed available in the facility E e design for the protection and mitigation of accident and transient con-8 v, di t.i o ns . The integrated operation of each of these systems is consistent i A with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable t S to the original design standards. The periodic surveillance tests '

N h performed at the minimum frequencies are sufficient to demonstrate this I 9 mi capability. !

a a-W*hdE The measurement of response time at the specified frequencies l

@ >. provides assurance that the RPS, SFAS, and SFRCS action function associated i E* with each channel is completed within the time limit assumed in the

@$3 safety analyses. No credit was taken in the analyses for those channels m2 with response times indicated as not applicable.

< o ~g ,

55 g Reconse time may be deonstrated by any series of sequential.

E E overlapping or total channel test measurements provided that such test 2 2 demonstrate the total channel response time as defined. Sensor response a time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sehsors with certified response times.

3 6 An SFRCS channel consists of 1) the sensing device (s). 2) associated i g $ logic and output relays including Isolation of Main Feedwater Non Essential ;

e Valves and Turbine Trip)(, and 3) power sources. I Bm$ w 4 1 E$3 Safety-grade anticipatory reactor trip is initiated by a turbine trip (above 25 percent of RATED THERMANL POWER) or trip of both main feedwater g= pump turbines. This anticipatory tr.ip will operate in advance of the 1 58_ reactor coolant system high pressure reactor trip to reduce the peak' C3 8 a reactor coolant system pressure and thus reduce challenges to the power y Si 0 operated relief valve. This anticipatory reactor trip system was eE, installed to satisfy Ites !!.K.2.10 of NUREG-0737.

5 5 l 2 a l A

DAVIS-8 ESSE Unit 1 8 3/4 3-1 Amendment No. 73

ML20196G218

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