ML20129E188

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Temporary Mod Request T-9072 to Rev 11 to Sys Procedure Sp 1105.16, Steam & Feedwater Rupture Control Sys Operating Procedure
ML20129E188
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/03/1985
From: Lee D, Quennoz S
TOLEDO EDISON CO.
To:
References
SP-1105.16-01, SP-1105.16-1, NUDOCS 8507300287
Download: ML20129E188 (38)


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- COPf ES TO BE MODiplED POR IMMEDIATE IMPLEMENTATION DAVIS-BESSE NUCLEAR POWER STATION UNIT 1 T* C. 64 f'1 '

f"T TEMPORARY MOOlFICATION REQUEST 45

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3 SP 1105.16.11 A , deenergize to actuate their associated equipment, they also turn out a light on the front of the cabinet when in the tripped state.

Each input to SFRCS cabinet has a test switch & light so that a trip of that input can be initiated for testing purposes.

The outputs from the SFRCS are contacta from the output relays. These contacts are in the control circuits for the SFRCS actuated equipment (see Enclosure

, 2 for listing of actuated equipment). Most components require two SFRCS channels to trip to actuate.

Components 1-1 OTSG side require both channels 1 and 3; components on 1-2 OTSG side require channels 2 and

4. (See Enclosure 2) Certain Solenoid Valves (ata.

11l vents, MSIV bypasses, Steam Generator Blowdown, and MS warmup drains)are 1/2 channels to shut.

There is a block feature associated with the low steam 11l pressure and Hi S/G Lvl trip: to prevent the system from actuating on cooldown, each channel has a " block" pushbutton on C5721 and on SFRCS cabinet. When steam pressure reaches 650 psig (2/2 switches per channel) a block permissive light is received on C5721 along with annunciator and computer alarms. When the block button is pushed, the channel will not trip (on low steam pressure or Hi S/G Lvl) and a MS LP trip block lite is actuated on C5721 as well as annunciator and computer alarms. On a hestup the block signal is automatically removed when either of the 650 psig 11l pressure switches resets.

There is another block which is utilized on cool-down; this is in the form of contacts from the decay heat system suction valves from the RCS (DH11 and

12) which will block the open circuit on the main steam to aux. feed pump valves (MS 106 and 107).

This prevents the SFRCS from opening these valves when all reactor coolant pumps are secured on shut-down. This " block" is automatically removed when the decay heat system is secured on startup.

I 11 "' 100A e-o a 1075 "ill cle: eg; vu ;;;1dv=u wuca l all A n t'D ' : :: :ncured. Since

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.S 107A vyoulus .m d L; defsete N racking-out theie  !

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1.2.3 System Logic (Refer to Enclosure 2 for y.ogic in O .

6 SP 1105.16.1?

open. The action provided by these valves (f~'/

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defeats AFPT 1-1 from being controlled by LT-SP9B3 (46" H2 O) and aligns LT-SP9A4 to control at the higher level (50" H O).2 Aux feed pump 1-2 will control on LT-SP9A3 and AFPT 1-2 governor vill be run to low speed stop.

. In this configuration S/G 1-2 level will be controlled at 50" H O 2 by AFPT 1-1.

4. The SFRCS will automatically reset once the trip condition on the input is removed. None of the valves, however, will return to their original position until operated individually from the control room. The Main Feedwater Control Valves SP 6B/6A, must be reset at their local Reset buttons. Startup Feedwater Valves SP7A and SP7B may be blocked and reset from the back of the Control Room.
5. As shown on Enclosure 2, most of the valves on the 1-1 side are actuated by Channels 1 and 3; 11l most of the valves on the 1-2 side are actuated by Channels 2 and 4. The following are excep-tions:
a. MS 100 and MS 101 - each of these valves will shut when Channels 1 and 3 OR 2 and 4

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trip. There are 5 actuation solenoids on each MSIV. On MS 101 for example, 2 solenoids are actuated by Channels 1 and 3, and the remaining 3 are actuated by Channels 2 and

4. MS 101 will not shut as long as one solenoid from each set is energized.
b. SP 6B and SP 6A - Main feed control valves.

The valve in the 1-1 feed line - SP 6B -

shuts when Channel 2 and 4 trip; SP 6A shuts when channel 1 and 3 shut.

c. Startup Feedwater Valves SP7A and SP7B may be reset and/or blocked from the Control Room at local control stations NRS60AB, NRS60BB, NRS60CB and NRS60DB.

11 d. MC 105A ;;d MC 107A will cpcn in ;;} unction--

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6. As shown on Enclosure 2, the following valves are 1/2 to trip, i.e., Channel 1 o,,r_ 3; Channel 2 or_ 4:

Channels 1/3 Channels 2/4 i MS 101-1 MS 100-1 MSIV Bypass i MS 394 MS 375 MS Drain ICS 11B ICS 11A Ata. Vent 11 MS 611 MS 603 S/G Blowdown 1

7. Besides being actuated' automatically, the SFRCS

} may be manually actuated in two ways:

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a. Each input device (PS, PDS, LSLL, etc.) has
a test button on the input buffer card in the SFRCS cabinets (see Enclosure 1).

, Pushing one of these buttons will have the l( same effect as the input device reaching its l "j setpoint. Keep in mind that tripping one

! input device will trip its associated

channel in the appropriate trip function.

! For example: if S8 in channel #1 (refer to Enclosure #1) is pushed, channel #1 will j trip on the high >177 psid SG pressure to W pressure AP function. Using Enclosure #2

" Steam and Feedwater Rupture Control Actuation" note that no valves, except for those which  !

! are 1 out of 2 logic will trip. Note that  ;

these test pushbuttons are mainly for l

" Testing" purposes only.

l i

1 b. There are ten manual actuation switches on the panel C-5721 in the control roca. Each l switch is an HIS type with a red " TRIPPED" ,

light and " Trip /Off" pushbuttons. The r

! " TRIP" pushbutton is of the maintained i contact type so that when it is pushed, it I

will stay in the " tripped" position until

. the "0FF" button is pushed. The switch arrangement on panel C-5721 is as follows:

CAUTION: The low steam line pressure inputs O are not in the same configuration

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,. i 29 SP 1105.16.11

' ACTION TAKEN RESTORED C0ffPONENT OUTPUT RELAY ACTION TO DISABI.E (IF ANY) VERIFIED PHASE II PHASE III VER. IND. VER.

MS 101 101A (2/2 x 2) 103A 1. Shut Viv OR 602C 2. Jumper

  • 602F 604C 604F MS 100 102A (2/2 x 2) 104A 1. Shut V1v, OR 601C 2. Jumper
  • 601F 603C 603F MS 106 201A (2/2) _ _20,3A ', Open Breaker 301C D135 (DINA) 303Cg ,,

MS 107 202A Open Breaker 3

(2/2) _ _2044 _ _ BF 1124 (Fila) 302C 304C D **

- MS 106A 9cM99tf-(2/2) Pg3Mh"I ,

Open Breaker

, BE 1271 (E12B)

MS 107A Gb2A302R (2/2) Sq304[I"", Open Breaker Open (I }

AF 3870 201B (2/2) _ _203B3"I ,

Open Breaker 301D D107 (DIPA) 303D AF 3872 2023 3 "*

(2/2) _ _20_4B ,

Open Breaker 302D ,, BF 1262 (F12B) 304D AF 3869 301F (2/2) __303[_hu open Breaker 401B BE 1146 (EllE) 403B D**

AF 3871 302F (2/2) __30,4phu I Open Breaker 402B j BF 1201 (F12A) 404B D ** '

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Attachment 1 Page 2 of 5 m_ ____ _ -_ . _ _ - , - , _ _ . _ .- , , _ , . .- p _- _ _ _

SP 1105.16

, . Davis-Besse Nuclear Power Staticm thit No. 1 Syst m Procedure SP 1105.16 Stearn and Feedwater Rupture Control Systm Operating Procedure h a g g iBi > I D ancord of Approval and aanges Prepared By T. Iehman, T. Porerski, D. Ricci 5/5/76 D:te Subcitted By Terry D. Mzrrav 5/12/76 secticn send Date W By Jack Evans 9/14/76 Sse _ ,_, D.te OA.M: proved NA Quality Assurance Dirw h Date Approved By Jack Evans 9/14/76 Plant Manager Date Revisicn SRB 0A Plant Manager No. Reccanmendaticn Date - Approved Date Apprcyral Date 11 #_' -

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1 SP 1105.16.11

1. PURPOSE j 1.1 To detail tha procedures necessary to per' form the following

? operations associated with the Steam and Feedwater Rupture Control System (SFRCS).

Section >

. SFRCS Energization and Initialization for 4
Plant Startup ,

l Deenergization of an SFRCS Channel (During 5

! Power Operations) '

l SFRCS Operations during plant shutdown 6 l Abnormal Operations 7 1'  ;

1.2 Discussion i

1.2.1 General The steam and feedwater rupture control system (SFRCS) is an automatic system designed to protect against the  ;

! following accidents:

i I

1. Main-steam rupture, either upstream or downstream of main steam isolation valve (MSIV). This

,- accident, if. allowed to proceed, could rapidly .

3' blow down both steam generators, resulting in a i rapid RCS cooldown and therefore a' rapid reactivity insertion under certain core conditions. To

, prevent this, SFRCS senses low main steam pressure

and automatically initiates auxiliary feedwater.

4

! 2. Main feed rupture. If on the steam generator

side of the feed check valve, this is approx-
imately the same accident as the steam rupture; a l on the feedwater side of the feed check valve this results in a total loss of feedwater (see c).

i j 3. Loss of all main feedwater. This (as well as the .  ;

i above accident) could resultin boiling both steam generators dry. If this happened, there would be l no steam available for running auxiliary feed ,

pumps to remove decay heat. To prevent this, SFRCS senses the loss of feedwater and automatically j initiates auxiliary feedwater.

The SFRCS, upon indication of any of the above accidents, will isolate main steam and feedwater to the steam generators and start the auxiliary feed system. This rapidly isolates the affected steam generator (s) by j 11 stopping main feed to it and isolating steam from O[

I l..

_ . - _. . . _ . _ _ - . . .._. _ _ .. _.s. ... . _ . _ . _ . _ . _ . . . . ._

3 SP 1105.16.11

) deenergize to actuate their associated equipment, they V also turn out a light on the front of the cabi;st when in the tripped state.

Each input to SFRCS cabinet has a test switch & light so that a trip of that input can be initiated for testing purposes.

The outputs from the SFRCS are ccatacts from the output relays. These contacts are in the control circuits for the SFRCS actuated equipment (see Enclosure 2 for listing of actuated equipment). Most components require two SFRCS channels to trip to actuate.

Components 1-1 OTSG side require both channels 1 and 3; components on 1-2 OTSG side require channels 2 and

4. (See Enclosure 2) Certain Solenoid Valves (atm.

11l vents, MSIV bypasses, Steam Generator Blowdown, and MS warmup drains)are 1/2 channels to shut.

There is a block feature associated with the low steam 11l pressure and Hi S/G Lvl trip: to prevent the system from actuating on cooldown, each channel has a " block" pushbutton on C5721 and on SFRCS cabinet. When steam pressure reaches 650 psig (2/2 switches per channel) a block permissive light is received on C5721 along with annunciator and computer alarms. When the block button is pushed, the channel will not trip (on low 1\ **- rre::ae w Hi S/G Lvl) and a MS LP trip block lite is actuated on C5721 as well as annunciator and computer alarms. On a heatup the block signal is automatically removed when either of the 650 psig 11l pressure switches resets.

There is another block which is utilized on cool-down; this is in the form of contacts from the decay heat system suction valves from the RCS (DH11 and

12) which will block the open circuit on the main steam to aux. feed pump valves (MS 106 and 107).

This prevents the SFRCS from opening these valves when all reactor coolant pumps are secured on shut-down. This " block" is automatically removed when the decay heat system is secured on startup.

11 MS 106A and MS 107A will also open on cooldown when all 4 RCP's are secured. Since the decay heat interlock (block) function does not prevent this, MS 106A and MS 107A opening must be defeated by racking out their supply breakers.

1.2.3 System Logic (Refer to Enclosure 2 for logic in

,m xs

- .. i ra .

i 1 SP 1105.16.11  :

1 1. PURPOSE ,

i 1.1 To detail the procedures necessary to per' form the following

operations associated with the Steam and Feedwater Rupture  ;

Control System (SFRCS).  !

I l Section J SFRCS Energization and Initialization for 4 l Plant Startup  ;

Deenergization of an SFRCS Channel (During 5 i

Power Operations)

SFRCS Operations during plant shutdown 6 j Abnormal Operations 7 1.2 Discussion i 1.2.1 General I

The steaa ru.i feedwater rupture control system (SFRCS) is an autcmet.'.c system designed to protect against the following ac-idents:  !

l 1. Main steam rupture, either upstream or downstresa l

[ of main steam isolation valve (MSIV). This  ;

t f'- accident, if allowed to proceed, could rapidly j i blow down both steam generators, resulting in a j rapid RCS cooldown and therefore a rapid reactivity '.

1 insertion under certain core conditions. To prevent this, SFRCS senses low main steam pressure l and automatically initiates auxiliary feedwater.

] 2. Main feed rupture. If on the steam generator '

side of the feed check valve, this is approx-

{ imately the same accident as the steam rupture; 1 on the feedwater side of the feed check valve 1 l this results in a total loss of feedwater (see c).

} 3. Loss of all main feedwater. This (as well as the .

, above accident) could resultin boiling both steam generators dry. If this happened, there would be ,

! no steam available for running auxiliary feed pumps to remove decay heat. To prevent this, j SFRCS senses the loss of feedwater and automatically

initiates auxiliary feedwater.

i The SFRCS, upon indication of any of the above accidents, l

! will isolate mein steam and feedwater to the steam  !

[ generators and start the auxiliary feed system. This j rapidly isolates the affected steam generator (s) by 1[ stopping main feed to it and isolating steam from i l I

,- - - . . - _ . . _ . _ , . . - _ _ _ ~ _ _ _ - _ _--~ , . . . . ~ , - - - , , , _ - _ _ _ _ . . , _ - - ~ _ _ [

2 SP 1105.16.11 it. Auxiliary feed is initiated to keep :t.eam available for cooldown. Once this is accomplished, the operator will have time to complete the shutdown and begin a cooldown in an orderly manner.

4. Loss of 4 reactor coolant pumps. This results in loss of primary flow and therefore anxiliary feed is needed to establish natural circulation flow.

The SFRCS will sense loss of 4 RC Pumps and automatically initiate auxiliary feedwater.

1.2.2 Functional Description (refer to Enclosures 1 and 2)

The SFRCS is divided for redundancy, diversity, and testability into four channels. Channels 1 and 3 (basically OTSG 1-1) are located in a Cabinet in the Control Room, Channels 2 and 4 (basically 01SG 1-2) are in another. In one cabinet, one channel has an AC power supply, the other a DC supply.

Channel Cabinet Power Supply Breaker 1 C5762A Y1 21 2 C5792 Y2 21 3 C5762A DIP 11 4 C5792 D2P 11 Each channel receives the following inputs (See Enclosure 1 for list of input devices).

1. Six pressure switches - 2 from each steam line set at 612 1 20 psig decreasing and 2 on ene steam line (1-1 for ch. 1/3; 1-2 for ch. 2/4) set at 650 110 psig increasing.

11l 2. Two feed-steam AP switches, one from each loop (See Enclosure 1 for sensing points) set at 177 120 psid steam higher than feedwater.

11 3. Four Hi & Lo level bistables, two from each steam generator set at 280" for Hi Lvl Trip and 26.5" for Low Lvl Trip indicated on the startup range.

4. A contact from RCP pump power sensing circuit; contact opens on loss of all four RCP. (See E52B, sheet 49)

The SFRCS cabinets consist basically of an AC and a DC power supply, input buffer, logic modules, and 11l output relays. The output relays (in most instances)

3 SP 1105.16.11 r

O deenergize to actuate their associated equipment, they also turn out a light on the front of the cabinet when in the tripped state.

Each input to SFRCS cabinet has a test switch & light so that a trip of that input can be initiated for testing purposes.

The outputs from the SSCS are contacts from the output relays. These contacts are in the control circuits for the SFRCS actuated equipment (see Enclosure 2 for listing of actuated equipment). Most components require two SR CS channels to trip to actuate.

Components 1-1 OTSG side require both channels 1 and 3; components on 1-2 OTSG side require channels 2 and

4. (See Enclosure 2) Certain Solenoid Valves (ats.

11l vents, MSIV bypasses, Steam Generator Bloudown, and MS warsup drains)are 1/2 channels to shut.

l There is a block feature associated with the low steam I

! - 11l pressure and Ri S/G Lvl trip: to prevent the system l from actuating on cooldown, each channel has a " block" l pushbutton on C5721 and on SFRCS cabinet. h a steam pressure reaches 650 psig (2/2 switches per channel) a block permissive light is received on C5721 along with annunciator and computer alarms, h a the block button is pushed, the channel will not trip (on low 1l steam pressure or Hi S/G Lv1) and a MS LP trip block lite is actuated on C5721 as well as annunciator and computer alares. On a heatup the block signal is automatically removed when either of the 650 psig 11l pressure switches resets.

There is.another block which is utilized on cool-down; this is in the form of contacts from the decay heat systes suction valves from the RCS (DR11 and

12) which will block the open circuit on the main steam to aux. feed pump valves (MS 106 and 107).

This prevents the SMCS from opening these valves when all reactor coolant pumps are secured on shut-down. This " block" is autoestically removed when the decay heat system is secured on startup.

11 MS 106A and MS 107A will also open on cooldown when all 4 RCP's are secured. Since the decay heat interlock (block) function does not prevent this, MS 106A and MS 107A opening must be defeated by racking out their supply breakers.

1.2.3 System Logic (Refer to Enclosure 2 for logic in O

i 4 SP 1105.16.11 tabular form. M-050 & M-051 and E-18 are the Bechtel i Logic Diagrams.)

1. The following will trip one channel of the SFRCS:
a. 1/2 Steam Pressure Switches <612 psig; two switches are on 1-1 steam line; two are on 1-2 steam line. (See Enclosure 1.)
b. 1/2 Steam-feed differential pressure switches

>177 psid steam greater than feedwater.

One PDS is on 1-1 feed-steam line; one is on 1-2 feed-steam line (See Enclosure 1).

11l c. 1/2 OTSG low level switches (26.5" indicated S/U range. One switch is on 1-1 OTSG: One is on 1-2. (See Enclosure 1) 11 d. 1/2 OTSG Hi Lvl Trip >280" H2 O as indicated on S/U range. One Hi Trip bistable for each OTSG. SFRCS monitored level S/U range is 0 to 385" H20.

e. Loss of 4 RC Pumps.
2. The response of the actuated components depends on the type of trip: (Refer to Enclosure 2) /
a. On low steam pressure on one steam line, steam feedwater are isolated to and from each steam generator. In addition, both auxiliary feed pumps are aligned to take steam from and to feed the steam generator which is above 612 psig.

If botn steam generators go below 612 psig, steam and feedwater is isolated to and from each steam generator and no_ auxiliary feed-water is initiated.

If any other trip (such as low steam gen-erator level) accompanies a low steam pres-sure trip, the valves will align per low steam pressure trip logic.

11l b. On high feed-steam dp or Hi/ low OTSG level on one steam generator, feed and steam are isolated to and from both OTSG's and each auxiliary feed pump is aligned to feed its own steam generator.

O s

5 SP 1105.16.11 (w)

( c. On loss of all four RC pumps, neither feed nor steam is isolated; each auxiliary feed pump is aligned te its respective steam generator.

11 d. On all of the above events, the turbine and ARTS is tripped by the SFRCS. This results in a Rx trip.

~

3. The auxiliary feed pump governor control switch in the control room has 2 positions:

Auto-essential (SFRCS)

Manual NOTE: The Mode Gelector Switch still has an ICS position which is not to be used.

4 In the auto-essential position, a SFRCS trip will position the governor to control OTSG levels 11l at 46" inches on S/U range. If an SFAS Incident Level 2 exists, then the governor will control at 11 124" on the S/U range.

This can be blocked after the SFAS O NOTE:

Incident Level 2 trip has occurred to allow control at the Low Level, however, administratively this is NOT permitted.

In manual the auxiliary feed pump is controlled by the operator with the Raise-Lower switch on C5709. This " Auto-Essential" speed control circuit receives a signal from the S/U range level for the appropriate steam generator. When each steam generator is being fed from its respective auxiliary feed pump,1-1 S/U level controls speed on 1-1 auxiliary feed pump,1-2 S/U level controls speed on 1-2 auxiliary feed

pump. If both feed pumps are feeding one steam generator, they will be controlled by the S/U i

level on the steam generator being fed.

11 If there is an SEAS and a SFRCS trip, the S/G level will be controlled at 128" H 20.

The level selection is determined by which aux feedwater supply valve is opened.

l For example if S/G 1-1 has a low pressure trip

AF-3870 will remain closed and AF-3869 will 1

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- l I

6 SP 1105.16.11 11 open. The action provided by these valves defeats AFPT 1-1 from being controlled by LT-SP9B3 (46" H2 O) and aligns LT-SP9A4 to control at the higher level (50" H 20). Aux feed pump 1-2 will control on LT-SP9A3 and AFPT 1-2 governor will be run to low speed stop.

In this configuration S/G 1-2 level will be controlled at 50" H O2 by AFPT 1-1.

4. The SFRCS will automatically reset once the trip condition on the input is removed. None of the valves, however, will return to their original position until operated individually from the control room. The Main Feedwater Control Valves SP 6B/6A, must be reset at their local Reset buttons. Startup Feedwater Valves SP7A and SP7B may be blocked and reset from the back of the Control Room.
5. As shown on Enclosure 2, most of the valves on the 1-1 side are actuated by Channels 1 and 3; 11l most of the valves on the 1-2 side are actuated by Channels 2 and 4. The following are excep-tions:
a. MS 100 and MS 101 - each of these valves will shut when Channels 1 and 3 OR 2 and 4 trip. There are 5 actuation solenoids on each MSIV. On MS 101 for example, 2 solenoids are actuated by Channels 1 and 3, and the remaining 3 are actuated by Channels 2 and
4. MS 101 will not shut as long as one solenoid from each set is energized.
b. SP 6B and SP 6A - Main feed control valves.

The valve in the 1-1 feed line - SP 6B -

shuts when Channel 2 and 4 trip; SP 6A shuts when Channel 1 and 3 shut.

c. Startup Feedwater Valves SP7A and SP7B may be reset and/or blocked from the Control Room at local control stations NRS60AB, NRS60BB, NRS60CB and NRS60DB.

11 d. MS 106A and MS 107A will open in conjunction with MS 106 and MS 107 when the SFRCS trips on the following signals:

Hi/Lo level S/G 1-1 or 1-2

7 SP 1105.16.11

)1 Hi AP S/G 1-1 or 1-2  ;

Loss of all 4 RCP's  !

l

, If the situation arises in that we have low steam pressure in both MS 106A and MS 107A l will not reclose automatically, but may be closed manually. }

I

6. As shown on Enclosure 2, the following valves are 1/2 to trip, i.e., Channel 1 or 3; Channel 2 l or 4:

Channels 1/3 Channels 2/4 MS 101-1 MS 100-1 MSIV Bypass MS 394 MS 375 MS Drain ICS 11B ICS 11A Atm. Vent 11 MS 611 MS 603 S/G Blowdown i

7. Besides being actuated automatically, the SFRCS may be manually actuated in two ways:
a. Each input device (PS, PDS, LSLL, etc.) has a test button on the input buffer card in the SFRCS cabinets (see Enclosure 1).

Pushing one of these buttons will have the i

same effect as the input device reaching its setpoint. Keep in mind that tripping one input device will trip its associated I

channel in the appropriate trip function.

For example
if S8 in channel #1 (refer to l Enclosure #1) is pushed, channel #1 will j trip on the high >177 psid SG pressure to FW ,

4 pressure AP function. Using Enclosure #2

" Steam and Feedwater Rupture Control Actuation" note that no valves, except for those which

& Nr 1 out of 2 logic will trip. Note that these test pushbuttons are mainly for

" Testing" purposes only,

b. There are ten manual actuation switches on the panel C-5721 in the control room. Each switch is an HIS type with a red " TRIPPED" light and " Trip /Off" pushbuttons. The

" TRIP" pushbutton is of the maintained contact type so that when it is pushed, it will stay in the " tripped" position until the "0FF" button is pushed. The switch arrangement on panel C-5721 is as follows:

CAUTION: The low steam line pressure inputs are not in the same configuration

.O

. - , . . ,, . , - - . - , . -,.,-.,...,-..----.-,w,

. ,m- - ,, ,en- - - - - - , .,--.-

8 SP 1105.16.11 in Channels 1 & 3 as Channel 2 &

4. This is indicated in the manual trip switch alignment shown below.

For example if we wish to initiate a manual trip for " Low Steam Pressure 1-1" in both SFRCS actuation channels, we must depress HIS 4869A for SFRCS CH I and HIS 4870B for SFRCS CH 2.

Trip switches are diagonal from one another as indicated below.

Channels 1&3 Channels 2&4 SG 1-1 Low HIS 4869A Tripped Tripped HIS 4870A SG 1-2 Low Stm Press Trip i Off Trip i off Stm Press SG I-2 Low HIS 4869B Tripped Tripped HIS 4870B SG 1-1 Low Stm Press Trip l Off Trip i off Stm Press SG 1-1 FW AP HIS 48C9C Tripped Tripped HIS 4870C SG 1-2 FW A P Trip i Off Trip i Off SG 1-1 HIS 4869D Tripped Tripped HIS 4870D SG 1-2 11l Hi/ Low Level Trip I off Trip l Off Hi/ Low Level Loss of RCPS H'.S 4869E I Tripped Tripped HIS 4870E Loss of RCPS l Trio l Of f Trip i Off The HIS-4869 switch series is for channels 1 and

3. The HIS 4870 series is for channels 2 and 4.

Pushing any " Trip" button will trip its assoc-iated channels for the designated trip function.

Forexample: HIS 4869C is pushed, channels 1 and 3 will trip in the "High FW-STM A P" function.

Refering to Enclosure #2 provides a list of valves which will actuate and the position they assume.

Unlike the Reactor Protective System and the Safety Features Actuation System, these manual trip buttons for the SFRCS are in series with the system input signal coming from the detector.

This switch placement causes the channels to react as though an actual trip conditioned as sensed by the detector exists.

8. On C5721 are four " BLOCK" switches:

/

_. 9 SP 1105.16.11 y CH. 1 G. 3 G. 2 CH. 4 IBLoGl lBLocrl lBroCri lBLoil lRAl lRAl lRAl lRAl HIS 101B HIS 101C HIS 100B HIS 100C When 2/2 650 psis pressure switches (decreasing) actuate, the red " BLOCK PERNISSIVE" alarm will light. The operator will push the "BLOCr" button 11I which will block the low, steam pressure and Hi S/G Lvl trip and light the amber "BLOCrED" light.

9. The following alarms are actuated by the SFRCS:

ALARM ID NO. COMPUTER ANNUN. SOURCE MS Iso Valve Q681, 688 Yes No Na accus 1200 Trouble pois, or one solenoid in trip position.

11 " SG 1 (2) Lo Q693, 692 Yes Yes One or more Press /Hi Lvl channels blocked.

Trip B1kd MS LP Trip P681, 680 Yes Yes LP Trip on one Channel.

11 SG 1 (2) Lo P685, 684 Yes Yes Two Channels Press /Hi Lvl 650f.

Trip Blk Prat W-SG dP trip P671, 672 Yes Yes W-SG Trip on one channel.

111 OTSG High/ Low L886, 896 Yes Yes OTSG High/ Low Level Trip Level trip on one channel.

RCP Matt Trip Q774 Yes Yes Loss of all four RCP's.

SFRCS Full Q963 Yes Yes Full trip from Trip Channels 1/3 or 2/4.

1.2.4 Srstem Operation In order to understand the operation of the SFRCS System, perhaps it is best to follow the various rystem actions under several accident conditions.

9he following cases will be considered:

10 SP 1105.16.11

1. Steam rupture
2. Feed rupture
3. Loss of feed pumps
4. Loss of 4 RCP Enclosures 1 and 2 should be used as an aid to under-standing the description. All discussions assume 100%

FP operation at start. Some non-SFRCS actions are considered to aid in understanding the transient.

1. Steam rupture - Assume 1'-1 steam line shears downstream of MSIV. Steaci pressure will rapidly drop. hien either side reaches 612 psig, all four channels will trip, isolating steam and feed for both steam generators. (See Enclosure 2 for specific valves.) The MSIV takes five seconds to shut, the MF isolation valve 15 seconds. Both steam lines will probably drop below 612 psig, therefore auxiliary feed will not start until one steam generator recovers to above 612 psig it will align as described in Section 3 to feed the high pressure steam gen-erator with both auxiliary feed pumps. The SFRCS 11 will trip the turbine and the ARTS. The reactor -

will trip due to ARTS trip.

2. Feed rupture - Assume 1-1 feedwater line shears upstream of the feed check valve. Feed pressure will rapidly drop (since our feed headers are cross-connected, both will drop). hten either feed header drops to 177 psig less than OTSG pressure, the SFRCS will trip, the steam and feedwater valves ca both sides and align the auxiliary feed pumps to their steam generator (1-1 to 1-1; 1-2 to 1-2). The STRCS will trip the ARTS. The ARTS will trip the teactor.

11l

3. Feed Pump Trip - Assume both main feed pumps trip. The SFRCS will trip on steam to feed AP >177 psig. The feed-steam AP trip on each steam generator will actuate due to loss of feed 11 header pressure. The CRDM Bkrs (A&B) and ARTS will trip the turbine and reactor. Loss of both MFPT's will trip the ARTS also.
4. Loss of 4 RCP - If all four RC Pumps trip, the ARTS and turbine will trip. The SFRCS will 11l initiate auxiliary feed as described in Section 3.

.e .

I 11 SP 1105.16.11

! 1l NOTE: The RCP monitoring system should be t viewed as an independent safety system whose output contacts provide trip

inputs to the EHC, RPS and SFRCS.
5. System Testina
a. Inputs: Each input device (pressure switch, 11 level switch, etc.) de-energizes a series of relays in the SFRCS cabinet which opens a contacts in the trip logic. Each of these 11 output relays can also be de-energized by a

! test button located on the input buffer

cards, this will turn out a lights in the r

^

cabinet. This, of course, will trip one

, channel in many cases; the SFRCS components will then be in a 1 out of 1 to trip mode;  ;

the 1/2 components will be tripped.

2 b. Outputs: Each output relay, except those l 11l for the alarms, has a status light which

will go out when the relay is de-energized.
Thus, when an input is tested and the j chma=*1 trips, the associated output relays
can be monitored for proper actuation.
2. LIMITATIONS AND PRECAUTIONS i

l 2.1 During plant cooldown, to prevent a SFRCS trip:

11l 1. Block the main steam line low pressure Hi OSTG Lvl trip

between 650 and 612 p'sig.

. 2. Place the Startup Feedwater Pump in operation prior to l removing the last Main Feedwater Pump from service.

i

3. Ensure both decay heat normal suction valves DH-11 and 2

DH-12 are fully open before the last RCP is tripped.

t

4. Maintain Steam Generator level above 35 indicated inches of [

{ 1evel in SUR. *

! 2.2 Should it ever be necessary to de-energize an SFRCS channel,

! prior to de-energizing, the Reactor Operators, Shift Supervisor ,

11 and Supervising Operator must visually verify that there is not

! a trip present in any other SFRCS channel then consult Enclosure

! 2 and Attachment 1, System Trip Logic and Trip Channel Identifica- ,

tion to determine which valves will open or close when that '

channel is de-energized and they must take the necessary steps to prevent inadvertant system actuation. De-energization of

channel trips everything on that channel. Only valves having a ,

s 3

(

12 SP 1105.16.11 11 1 out of I logic will trip. The associated ARTS channel must be placed in TTBP for the SFRCS parameter.

2.3 Whenever a channel is de-energized, the output relays in that channel are in the tripped condition. For this reason, testing or maintenance on the complementary channel (e.g. I and 3 or 2 and 4) cannot be performed as a trip would occur and system actuation would take place.

Note that among other things, the following will de-energize an SFRCS channel:

1. De-energizing DIP, D2P, Y1, or Y2.
2. Performing dead transfer on essential DC Distribution Panels.

(TS) 2.4 D-B Technical Specifications 3.3.2.2.

3. REFERENCES (TS) 3.1 Davis-Besse Unit 1 Technical Specification para. 3.3.2.2 11l 3.2 USAR 7.4.1.3 3.3 SFAS/SFRCS Instrumentation Manual TM-19 Consolidated Controls 3.4 AD 1803 Safety Tagging 3.5 SFRCS Logic Diagrams Bechtel F&ID Drawing M-050, M-051, E-18 3.6 Station Shutdown and Cooldown Procedure, PP 1102.10 3.7 Station Startup Procedure, PP 1102.02 11l 3.8 Automated Industries Inc. (ARTS)
4. SFRCS ENERGIZATION AND INITIALIZATION FOR PLANT STARTUP 4.1 Prerequisites 4.1.1 Essential instrument AC and DC distribution panels are energized for each channel.

SFRCS Channel Distribution Panel 1 Y-1 (AC) 2 Y-2 (AC) 3 D1P (DC) 4 D2P (DC)

.)

. . - .- _-_ _-. ~_ -- .-- . . . - - - . - ..- -. -. --

13 SP 1105.16.11

/~'

4.1.2 The Shift Supervisor has given permission to energize the SFRCS cabinets and/or the SGLI cabinets and has

issued SFRCS and/or SGLI cabinet door keys as appropriate.

I 4.2 Procedure

] 4.2.1 Verify that the AC and DC power supply input switches in the SFRCS and/or SGLI cabinets are "0FF" for each channel.

Channel 1 Channel 3 SFRCS Cabinet C5762A Channel 2 Channel 4 SFRCS Cabinet C5792 SGLI Channel 1 SGLI Cabinet C5736

! SGLI Channel 2 SGLI Cabinet C5737 j SGLI Channel 3 SGLI Cabinet C5738 SGLI Channel 4 SGLI Cabinet C5739 4.2.2 Clear tags from and "close" the appropriate

SFRCS and/or SGLI source breaker at its essential j distribution panel.

4

SFRCS Chan Distribution Panel Breaker

/ -1 Y1 Y1-21 l1 2 Y2 Y2-12 3 DIP DIP-11 4 D2P D2P-11 SGLI Chan Distribution Panel Breaker

! 1 Y1 Y1-15 2 Y2 Y2-15 3 DIP D1P-17 4 D2P D2P-17 ,

1 4.2.3 Turn the power input switch on each SFRCS power supply to the ON position. >

l i Verify that both 48V and 15V " Power on" lights are '

lit.

l

!i Cabinet 48V 15V 48V 15V C-5762A Ch-1 Ch 3 1

, C-5792 Ch 2 Ch 4 11 4.2.4 ' Prior to energizing any SGLIC cabinet remove all power supply fuses, turn power switch on, then replace fuses one at a time.

O m

l -l l

14 SP 1105.16.11 4.2.5 To energize the SGLI cabinets, perform steps 4.2.5.1 through 4.2.5.4.

1. Open the FRONT Cabinet door to the respective SGLI Cabinet.
2. Turn the power switch "0N" located in the inside center of the SGLI Cabinet.

SGLI Channel Cabinet 1 C5736 2 C5737 3 C5738 4 C5739

3. Verify all four power supply indicators on the front panel indicate "0N" for the respective SGLI Cabinet.

Power Supply SGLI Channel Cabinet Status 1 C5736 "ALL ON" 2 C5737 "ALL ON" 3 C5738 "ALL ON" 4 C5739 "ALL ON"

4. Close and lock FRONT cabinet doors.
5. If Steam Generator Level is greater than the low 11l level and less than hi level trip bistable setpoint, verify that LIO and L11 input buffer lamps in the same SFRCS Channel are on.

11 l 4.2.6 If main steam pressure is less than 612 psi: Verify the low pressure trip logics and the 650 psi low steam pressure block permit logics are tripped.

(Lights out at SFRCS cab.)

Trip Permit Trip Permit Ch I Ch 3 Ch 2 Ch 4 NOTE: Verification is performed by visual inspection of the STRCS input lights L1 through L6 on the input buffer cards for each channel.

(Refer to Enclosure 1)

Verify the "MN STM LINE LOW PRESS TRIP" annunciator windows for Channel #1 and Channel #2 have alarmed.

15 SP 1105.16.11 4.2.7 To initialize the SFRCS (e.g. Remove the low steam pressure trip and block it) perform the following for each channel at the SFRCS cabinets.

1. Press and hold S-14 the " Initial Bypass" pushbutton, then,
2. Press S-7, the " Block" pushbutton.
3. Release both S-7 and S-14.

NOTE: Switches are located on the SFRC3 cabinets on input buffer cards.

Enclosure 1 shows switch labelin;, its function and the detector which it corresponds to.

Ch 1 Ch 3 Ch 2 Ch 4 4.2.8 Verify "MS LP/Hi Lvl Trip Blocked" amber lights on HIS 11l 101B, HIS 101C, HIS 100B and HIS 100C on C5721 are "on".

4.2.9 Verify that all input instrumentation (Enclosure 1) is b in service.

4.2.10 Verify that all disabled outputs have been restored per Attachment 1 (except for Auxiliary Feedwater  !

Valves marked

  • which are covered by PP 1102.02 -

Plant Startup).

Independently Verified Date 4.2.11 Verify that input test light status in SFRCS Cabinets agrees with plant conditions. Light status for cold shutdown, all RC Pumps OFF, Steam generators filled is as follows:

l INPUT TEST LIGHT (Enclosure 1) STATUS L1 0FF L2 0FF L3 0FF-L4 0FF L5 0FF L6 0FF L7 ON L8 ON

.O L9 ON

i 16 SP 1105.16.11 INPUI TEST LIGHT (Enclosure 1) STATUS L 10 ON L 11 ON L 12 0FF L 13 ON L 14 ON 11l L 15 0FF Spare 4.2.12 Verify output relay status as follows:

CH. 1 CH. 3 CH. 2 CH. 4 STATUS 101A 103A 102A 104A ON 201A 203A 202A 204A ON 201B 203B 202B 204B ON 201C 203C 202C 204C ON 301A 303A 302A 304A OUT 301B 303B 302B 304B OUT 301C 303C 302C 304C OUT 301D 303D 302D 304D OUT ll) 901A 903A 902A 904A ON 301F 303F 302F 304F OUT 11l 801A 803A 802A 804A OUT 401B 403B 402B 404B ON 11 601A 603A 602A 604A ON _

601G 603G 602G 604G ON 601H 603H 602H 604H ON 601J 603J 602J 604J ON 601B 603B 602B 604B ON 601C 603C 602C 604C ON 601D 603D 602D 604D ON 601E 603E 602E 604E ON 601F 603F 602F 604F ON 60AA 60CA 60BA 60DA ON 60AB 60CB 60BB 60DB ON 60AC 60CC 60BC 60DC ON 71AA 71CA 71BA 71DA ON 72AA 72CA 72BA 72DA ON 73AA 73CA 73BA 73DA ON 4.2.13 Place HAND / AUTO Station (s) for Main & S/U Feedwater Valves associated with the Channel (s) which have been tripped in HAND and adjust " POSITION" Signal to that corresponding to valve position. Reset Main Feedwater Valves by pushing RESET button by the valves. Shift valves to AUTO as desired. Reset Startup Feedwater Valves in accordance with Step 7.2 of this procedure.

.+ 4.2.14 Return the SFRCS door keys to the Shift Supervisor.

- - .-. . ~. . .. . -

t. .

f 17 SP 1105.16.11 i

i g 1 4.2.15 If the ARTS was placed in TTBP return to the position

as determined by the Shift Supervisor.

l 4 Section 4 completed by Date l S. DE-ENERGIZE AN SFRCS CHANNEL (DURING POWER OPERATIONS) <

i

- 5.1 Prerequisites 5.1.1 A situation exists requiring that an SFRCS Channel i

must be tripped or de-energized.

5.1.2 There are no existing trips on the remaining 3 channels.

Verified by all the output relay lights for the l remaining channels being lit.

4 l lij NOTE: There should be no RPS, SFAS or ARTS testing in progress during the time that any SFRCS Channels are being tested or de-energized.

5.1.3 The Shift Supervisor, Supervising Operator and Reactor Operator have determined from Attachment I which valves naving a 1 out of 2 logic will close when that

Channel trips.

N 11 5.1.4 Place the associated ARTS channel in TTBS for the

1 SFRCS channel.

i SFRCS CH 1 ARTS CH I

! 2 2 3 3 l 4 4

5.1.5 Prior to performing, this procedure must be read and  ;

l understood by the Shif t Supervisor, Supervising  :

Operator and Reactor Operators. l l 5.1.6 The Limits and Precautions have been reviewed.

?

! 5.2 Procedure l NOTE: When one Channel of SFRCS is tripped, the valves which are 1/2 trip will normally be shut at power.

i 4 5.2.1 Proceed with deenergizing the appropriate SFRCS 11 Channel. If the SFRCS channel is to be de-energized at the breaker, refer to Section 4 for b'reaker number I

and location.

NOTE: Deenergizing SFRCS Channel 1 and 2 by way

O of the ON/0FF switch or channel breaker .,

l

18 SP 1105.16.11 will deenergize all relay status lights in the appropriate cabinet. To verify complimentary channel operability observe the Input Buffer Lamps on the complimentary channel are illuminated.

11 5.2.2 Return to Section 4 for re-energization.

5.2.3 After testing is complete and the channel is re-energized ensure the channel is reset by observing appropriate relay status lamps are "0N" for plant conditions.

Section 5 completed by Date

6. SFRCS OPERATIONS DURING PLANT SHUTDOWN AND C00LDOWN 6.1 Prerequisites 6.1.1 The plant is being Shutdown and cooled down according to Plant Shutdown and Cooldown Procedure, SP 1102.10.

6.2 Procedure During Cooldown (These steps are covered in SP 1102.10) 11 6.2.1 Upon receipt of the " Main Steam Line Low Pressure /Hi Lvl Block Permit" alarms (one for each channel) depress the low steam pressure blocks switches HIS-101B, HIS-101C, HIS-100B and HIS-100C on Panel C5721. The 11l " Main Steam Line Low Pressure /Hi Lvl Trip Blocked" annunciator alarms should sound and light.

6.2.2 Place the SUFP in service prior to tripping the MFPT.

This acton prevents a FW-Steam dP trip.

6.2.3 Place the DH System in operation and, after Tav 280'F, disable motor operated valves in the auxiliary feed system per SP 1102.10. This action prevents a loss of all RCP trip upon securing the last RC Pump.

6.3 Action to be taken if SFRCS Channel (s) are to be tripped or deenergized during Shutdown.

6.3.1 SFRCS Channels may need to be tripped or deenergized for testing or maintenance during plant shutdown. In order to prevent or predict valve operation, the Shift Supervisor shall consult Enclosure 2 and Attachment I and complete Attachment 1 far any outputs which need to be disabled.

NOTE: The SFRCS must be in operation as defined by TS 3.3.2.2 with all outputs operable prior to exceeding 280*F Tav.

=

g .

19 SP 1105.16.11 6.3.2 Restore all outputs to operable status prior to startup by completing RESTORED column on Attachment 1.

11l Section 6 completed by Date

7. ABNORMAL OPERATION

' 7.1 Action to be taken after an SFRCS trip.

7.1.1 It is NOT possible to provide detailed steps to cover all possible trip situations (failure of instruments, actual casualty, etc.). The following general statements apply:

1. The SFRCS will remain tripped as long as the trip situation exists. For example, on loss of feedwater the system will remain tripped as long as feed header pressere is greater than 177 psid less than steam pressure.
2. It is NOT possible to operate any SFRCS valve l

remotely with the SFRCS in the tripped state, l -

with the exception of the Atmospheric Vent l Valves, the Feedwater Stop Valves, Startup

!- .11l Feedwater Valves and the S/G Blowdown Vivs. All

( other valves will require manual control.

3. Once the trip situation has been cleared, the SFRCS will automatically reset, and valves any then be operated at will.
4. In a trip situation, the first action to regain control should va to clear the trip situation (Restore feed header pressure, raise steam generator level, start a RC pump, etc.).
5. If the trip situation cannot be cleared (such as an actual steam rupture upstream of MSIV) it will normally be necessary to make a cooldown using auxiliary feedwater and controlling the atmospheric vents manually.
6. If so desired to feed utilizing the SUFP and maintaining atmospheric vent valve control during an SFRCS trip condition, the Startup Feedwater Valves, the S/G Blowdown Valves, the Main Feedwater Stop Valves, and Atmospheric Vent Valves can be

, blocked to override the SFRCS trip signal to these valves.

  • 7.2 Action to be taken to Reset Startup Feedwater valves SP7A and SP7B after an SFRCS trip.

20 SP 1105.16.9 NOTE: In order to gain control of the Startup Feedwater Valves, the SFRCS signal must be blocked (if pre-sent) and the reset button must be pushed per the following steps.

7.2.1 The SFRCS Channels provide trip and reset functions in cocjunction with the following local stations.

Channel 1 - NRS60AB Channel 2 - NRS60BB Channel 3 - NRS60CB Channel 4 - NRS60DB 7.2.2 If the SFRCS Channels are not reset and it is desired to open SP7A/7B, depress the " BLOCK" button at the respective local station NRS60AB, BB, CB, DB located on the back wall in the control room next to the cabinet C5736, then proceed to 7.2.3.

7.2.3 Once the SFRCS trips signals have cleared - or the local stations have been " BLOCKED", reset SP7A/7B by depressing the " RESET" button at the respective local control station NRS60AB, LB, CB, DB - determined by whichever reset light is "0FF".

NOTE: If the STARTUP FEEDWATER VALVE TRIP signals were blocked and the SFRCS trip signals have .

cleared, the BLOCK functions will automatically 9 clear, however should a subsequent SFRCS trip occur and it is still desired to maintain SP7A/7B "0 PEN" the above procedure will have to be repeated.

7.3 Actions to be taken to Operate Atmospheric Vent Valves ICS11A (ICS11B) during an SFRCS trip.

7.3.1 At HIS ICS11C (HIS ICS11D) depress BLOCK button.

Verify "SFRCS BLOCK". Light ILICS11 (ILICS11) is on.

NOTE: If an SFAS Incident Level 2 exists at the same time that the SFRCS is tripped, depress BLOCK button HIS ICS11C (HIS ICS11D) will block both the SFRCS signal and the SFAS signal.

7.3.2 Verify the demand for ICS-11B (ICS-11A) is zero and the Hand / Auto Station is in hand.

7.3.3 At HIS ICS11B (HIS ICS11A) depress the Auto Button.

ICS11B (ICS11A) may now be controlled as desired.

/

g .

21 SP 1105.16.11

+

NOTE: Atmospheric Vent Valves ICS11A and ICS11B should not be operated without steam to prevent damage to the valves.

i 7.4 Actions to be taken to Reset Main Feedwater Stop Valves FW 601 (FW 612) after an SFRCS trip.

7.4.1 At HIS 601 (HIS 612) depress BLOCK button HIS 601A (HIS 612A).

1

, NOTE: This will enable the Valves FW 601 (FW 612) to be operated as desired.

11 7.5 Action to be taken to reset S/G Blowdown Viva MS 603 (MS 611) after an SFRCS 1/2 trip (or full trip).

i 4

! 7.5.1 At HIS 603 (HIS 611) depress block button HIS 603B 1

} (HIS 611B) and verify the amber block light is lit. I

, This will enable the valves MS 603 (MS 611) to be operated as desired.

} Section 7 completed by Date 1

1 t i

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i 1

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<- O 1 - . - - - - . _ - _ - - - - -- -. _ - . -.- - - .- -,-. - . -

22 SP 1105.16.11 , ,

i

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s. s, in so witch is depressed o input device actuates) >

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s: Tim,li- """ I EITI e vliiv isa E l a:st,jtl'fgI 3 psp, I 1ls s stl 1 Enclosure 2 Page 1 of 2

24 SP 1105.16.11 - -

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Mn FW1 Press Turbine 2 RCS-72BA Trip 2/2 SG2 Press 177 PSID 11l Trip 4 RCS-72DA Trip >Mn IV2 Press Turbine 1 RCS-73AA Trip 2/2 Sta Gen 1 Low Level Trip 3 RCS-73CA Trip Turbine 2 RCS-73BA Trip 2/2 Sta Gen 2 Low Level Trip 4 RCS-73DA Trip i 11 ARTS Trip 1 RCS-601J Trip 1/1 1/5 Trip on all ARTS CH's ARTS Trip 2 RCS-602J Trip 1/1 1/5 Trip on all ARTS CH's 1/5 Trip on all ARTS CH's ARTS Trip 3 RCS-603J Trip 1/1 ARTS Trip 4 RCS-604J Trip 1/1 1/5 Trip on all ARTS CH's  ;

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. G Enclosure 3 l Page 3 of 3

28 SP 1105.16.11 DISABLING SFRCS OUTPUTS

1. De-energizing or tripping one channel in an SFRCS Cabinet will 11 trip only those valves listed as 1/2 logic and will place a 1/5 trip in all ARTS channels.
2. De-energizing or tripping both channels (either 1&3 or 2&4) in an SFRCS Cabinet will trip all valves actuated by the actuation Ch #1 or 2.
3. This w'1 trip the turb and ARTS will trip the reactor. Prior to de-energizing or tripping a SFRCS Channel, the Shift Supervisor will determine which steps are needed on this Attachment. The completed attachment will be retained for returning the system to service. Disable the components as required on this attachment and record in the appropriate block what has been done.

(TS) 4. Refer to Davis-Besse Technical Specifications 3.3.2.2 and 3.7.1.2 for requirements when a portion of SFRCS or Auxiliary Feedwater System is disabled. Refer to 3.6.3.1 for requirements when a containment isolation valve is out of service.

5. Refer to table in Step 4.2.10 for correlation of relay numbers to SFRCS Channel.
6. The valves marked
  • are disabled during cooldown per PP 1102.10

- Plant Shutdown & Cooldown and enabled on heatup per PP 1102.02 .

- Plant Startup.

O Attachment 1 Page 1 of 5

29 SP 1105.16.11 ACTION TAKEN RESTORED f, COMP 0 MENT OtJTPUT REI.AY ACTION TO DISABI.E (IT ANY) VERIFIED PHASE II PHASE III VER. IND. VER.

l

MS 101 101A '

i (2/2 x 2) 103A 1. Shut Viv OR l 602C 2. Jumper * (

602F i

) 604C l 604F  !

MS 100 102A l (2/2 x 2) 104A 1. Shut Viv, OR  ;

) 601C 2. Jumper *  !

! 601F

  • l 603C '

1 603F  !

! MS 106 201A '

l "

(2/2) 203A -~

Open Breaker i I ~ ~ 331C D135 (DINA) '

} 303C D" t

! MS 107 202A Open Breaker I (2/2) _ _204A "I BT 1124 (F11A) 3025

  • s

-l 304C i MS 106A  !

301E

! 3 "'  !

(2/2) 313E open Breaker

{ ~ ~451I ~ ~ BE 1271 (E128) '

403A Pen  !

l MS 107A 3021 Shut

! (2/2) 304E Open Breaker 4

~ ~452I0~ ~ BT 1188 (F118) 7 j 404A pen {

i AF 3870 2018 8h"E i (2/2) 2038 Open Breaker j

J

~~515~;

3 303D 9 ,, D107 (D1PA)

! AF 3872 2028  !

l' (2/2) _ _2048 "I Open Breaker 302D BT 1262 (F128) {

304D0pen i AF 3869 301F  !

"I

! (2/2) 303F -~

Open Breaker i - ~451B BE 1146 (EllE)

' 4038 i AF 3871 302F Shut  !

l (2/2) 304F Open Breaker .

~ ~4525 ~ ~ BT 1201 (F12A) '

I 4048

' i See NOTE on Pese 5 of 5 Attachment 1 Page 2 of 5  !

r

30 SP 1105.16.11 ACTION TAKEN RESTORED 9)

COMPONENT OUTPUT REI.AY ACTION TO DISABI.E (IF ANY) VERIFIED PHASE II PHASE III VER. IND. VER.

AF 608 201C Open Breaker 8h"*

(2/2) _ _203C BE 1160 (E11C) 301A 303A

- ~ 615 3 Vent 303BClose AF 599 202C Open Breaker 8

(2/2) __204CI"" BF 1118 (Fila) 302A 304A0pen

~ ~3 525 - -

304B SP 6A 60AA 1. Shut Viva, OR (2/2) 60CA 2. Place Vivs on hand Jacks SP eB 60BA 1. Shut Vivs, OR (2/2) 60DA 2. Place vivs on hand jacks SP 7A 60BB 1. Shut Vivs, OR (2/2) 60DB 2. Place V1vs on 60AB hand jacks k) 60CB ./

SP 7B 60AB 1. Shut vivs, OR (2/2) 60CB 2. Place viva on 60BB hand jacks 60DB IV 780 60AC Open Breaker (2/2) 60CC BE 3213 (E*i2A)

FW 779 60BC Open Breaker (2/2) 60DC BF 3261 (F32A)

MS 101A 601A 1. Shut Vlv, OR (1/2) 603A 2. Jumper contacts on TB 4 in C5762A, Term 9 to 13 MS 100A 602A 1. Shut V1v, OR (1/2) 604A 2. Jumper contacts on TB 4 in C5792 term 9 to 13 1CS 118 601B 1. Shut Viv (1/2) 603B ICS 11A 602D 1. Shut V1v (1/2) 604B O

Attachment 1 Page 3 of 5

D 31 SP 1105.16.11 ACTION TAKEN RESTORED l COMPONENT OLTPUT REI.AY ACTION TO DISABI.E (IF ANY) VERIFIED PHASE II PHASE III VER. IND. VER.

MS 394 601D 1. Shat Viv (1/2) 603D MS 375 602D 1. Shut Viv (1/2) 604D FW 612 601E 1. Shut Vlv, OR (2/2) 603E 2. Open Breaker BE 1155 (E11C)

FW 601 602E 1. Shut Vlv, OR (2/2) 604E 2. Open Breaker BF 1117 (E11D)

Turbine 71AA 1. Trip Turbine, Trip 71CA OR 71BA 2. Jumper contacts 71DA for Channel to to be tripped Turbine 72AA 1. Trip Turbine, Trip 72CA OR (2/2) 72BA 2. Jumper contacts

) 72DA for Channel to 73AA be tripped 73CA In C5762A TB13 73BA TERM 6 to TB 15 73DA TERM 7 In C5792 TB 13 TERM 6 to TB 15 TERM 7 KV 611 601G 1. Shut Valve (1/2) 603G KV 603 602G 1. Shut Valve (1/2) 604G ARTS Trip 601J CRP Breakers Trip-(2/4) 602J ped or place all 603J 4 ARTS Chann91s 604J in Test Trip By-pass for STRCS Disable MS 101, MS 100 trip by jumpering in C5762A TB 39 Term 3,4 Verified Independently Verified TB 39 Term 6,7 Verified Independently Verified TB 6, Term 6,7 Verified Independently Verified TB 8, Tera 9,10 Verified __ Independently Verified TB 6, Term 9,10 Verified Independently Verified TB 8, Term 12.13 Verified Independently Verified Attachment 1 Page 4 of 5

a r* '

32 SP 1105.16.11 C5792 TB 39, Term 3,4 Verified Independently Verified _

TB 39, Term 6,7 Verified Independently Verities, TB 6 Term 6,7 Verified Independently Verified '-'-- ,

TB 8, Term 9,10 Verified Independently Verified TB 6, Term 9,10 Verified Independently Verified TB 8. Term 12,13 Verified Independently Verified NOTE: The below listed relays are (spares):

601H 602H 603H 604H l

i l

l 1

O l

Attachment 1 END Page 5 of 5 l