ML20115H689

Forwards Info Clarifying Js Kemper 850325 Submittal Re Redundant Remote Shutdown Capability,Per 850328 Telcon Request

ML20115H689
Person / Time
Site:	Limerick
Issue date:	04/18/1985
From:	Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Schwencer A Office of Nuclear Reactor Regulation
References
CON-#285-663 GOVT-1-1, OL, NUDOCS 8504230229
Download: ML20115H689 (48)

Text

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Al PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 JOHN S. KEMPER VIC E#R ES!D E NT guesmaa nsmo Ano nest AnCM Mr. A. Schwencer, Chief Docket Nos.: 50-352 Licensing Branch No. 2 50-353 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 FOL No.: NPF-27

SUBJECT:

Limerick Generating Station, Units 1 and 2 Request for Additional Information:

Redundant Remote Shutdown Capability

REFERENCE:

1) Letter, J. S. Kemper to A. Schwencer

" Request for Additional Information -

Redundant Remote Shutdown Capability" March 25, 1985

2) Teleconference between R. E. Martin and R. Stevens of the NRC and W. W. Bowers, D. F. Ciarlone, R. T. George, H. D. Honan, and E. F. Sproat of PECo dated March 28, 1985 of the same subject.

FILE: GOVT l-1 (NRC)

Dear Mr. Schwencer:

The reference 2 teleconference transmitted a series of requests for clarification concerning the infornation provided in the reference 1 submittal. Attachments 1 through 6 to this letter provide the requested information to satisfy those requests for clarification.

Sincerely, Copy to (See Attached Service List) 8504230229 DR 850418 ADOCK 05 2 gO>)

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cc: Judge Helen F. Moyt (w/ enclosure)

Judge derry Harbour (w/ enclosure) dudge Richard F. Cole (w/ enclosure)

Troy B. Conner, Jr. , Esq. (w/ enclosure) i Ann P. Hodgdon, Esq. (w/ enclosure)

Mr. Frank R. Romano (w/ enclosure) ~

Mr. Robert L. Anthony (w/ enclosure)

Ms. Phyllis Zitzer (w/ enclosure)

Charles W. Elliot, Esq. (w/ enclosure)

Zori G. Ferkin, Esq. (w/ enclosure)

Mr. Thomas Gerusky (w/ enclosure)

Director, Penna. Emergency (w/ enclosure)

Management Agency Angus R. Love, Esq. (w/ enclosure)

David Wersan, Esq. (w/ enclosure)

Robert J. Sugannan, Esq. (w/ enclosure)

Martha W. Bush, Esq. (w/ enclosure)

Spence W. Perry, Esq. (w/ enclosure)

Jay M. Gutierrez, Esq. (w/ enclosure)

Atomic Safety & Licensing (w/ enclosure)

Appeal Board Atomic Safety & Licensing (w/ enclosure)

Board Panel Docket & Service Section (w/ enclosure)

Mr. James Wiggins (w/ enclosure)

Mr. Timothy R. S. Cangbell (w/ enclosure) a g-t I

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Attachment 1 Supplemental Information in Response to RAI - Remote Shutdown (License Condition A14)

RAI:I(a)

Information should be provided to give a one-to-one comparison of the final (after modifications) redundant safety-related train of equipment with that of the already existing safety-related remote shutdown train of equipment which was reviewed and accepted by the staff prior to licensing.

Response

Attachment 5 provides a comparison of the existing single train of remote shutdown equipment as described in FSAR Table 7.4-3 and the interim redundant remote shutdown t'r ai n of equipment. Each existing component has been evaluated for it's wor st case f ailure and each component's associated system design function has been verified to have been included in the interim redundant remote shutdown procedure.

Mul tipl e components associated with a system design function are grouped together.

The interim redundant remote shutdown procedure will be modified to incorporate the addition of a transfer switch to the B RHRSW, B RHR, and B ESW pump motor circuit breaker cubicles. The addition of these switches is scheduled to be implemented during the first refuel outage.

The added transfer switches will allow operation of the respective pump motors via their circuit breaker test switch without the need to install temporary jumpers. The only impact the added transfer switches will have on the interim redundant remote shutdown procedure will be:

a.) eliminate the steps required to install the temporary jumpers needed to establish control of the pump motors from their respective circuit breaker test switch b.) replace these steps with similar steps referencing the operation of the transfer switches to establish contal of the pump motors from their respective circuit breaker test switch.

Consequently, the interim redundant remote shutdown procedure and the final redundant remote shutdown procedure will be functionally equivalent. The compari son provided in Attachment 5 is equally applicable, without any changes, to the final redundant remote shutdown procedure.

r i Attechment la Paga 2 RAI: I (b)

That portion of the operational procedures to be implemented for the final (after modifications) tedundant safety-related remote shutdown system (both trains) should be provided.

Response

The final redundant remote shutdown procedure will not be issued until the identified design changes are finalized and implemented. However, as stated in the response to item I(a) above, the interim and final redundant remote shutd7wn procedures will be functionally equivalent. The interi.'.

redundant remote shutdown procedure will be modified to incorporate the addition of a transfer switch to the B RHRSW, B RHR, and B ESW pump motor circuit breaker cubicles. The addition of these switches is scheduled to be implemented during the first refuel outage. The added transfer switches will allow operation of the respective pump motors via their circuit breaker test switch without the need to install temporary jumpers. The only impact the added transfer switches will have on the interim redundant remote shutdown procedure will bet a.) eliminate the steps required to install the temporary jumpers needed to establish control of the pump motors from their respective circuit breaker test switch b.) replace these steps with similar steps referencing the operation of the transfer switches to establish contal of the pump motors from their respective circuit breaker test switch.

Attechment 1: Pcga 3 RAI:I(c)

Elementary drawings and electrical schematics should be provided to show the details of each hardware change necessary for full implementation of the redundant safety-related remote shutdown system train (drawings should reflect the addition of transfer swithes in relation to the function of the pump motor circuit breaker test switches, etc.).

Response

The redundant remote shutdown system train has been fully implemented via the interim redundant remote shutdown procedure. The interim redundant remote shutdown procedure requires the use of temporary jumpers to establish control of the B RHRSW, B RHR, and B ESW pumps at their respective circuit breaker cubicles. Design changes have been initiated to allow operation of the B RHRSW, B RHR, and B ESW pumps from their respective pump motor circuit breaker cubicles without the need to install temporary jumpers. A sketch illustrating the scope of the changes required in the B RHRSW pump motor control circuit is provided in Attachment 4. As shown in the sketch provided in Attachment 4, a keylocked, two position, maintained contacts transfer switch will be installed on the pump motor circuit breaker cubicle. When the transfer switch is in NORM, the associated pump can be operated from the control room only. When the transfer switch is placed in EMER, the pump can only be operated by the circuit breaker test switch and a control room annunciator will be activated identif ying the associated equipment as out-of-service. The sketch is typical of the changes required in the B RHR and B ESW pump motor control circuits. The pump motor control circuit changes are scheduled for implementation during the first refuel outage.

The detail ed design changes have not yet been finalized.

Ther ef ore, the final drawings required to implement the changes have not been isuued. However, these changes wi11 be engineered and implemented in accordance with safety-related design and qualification requirements, including seismic qualification. The equipment qualification requirements will envelope the service conditions expected to occur during shutdown conditions.

The remote shutdown scenario does not include any accidents or transients that would expose the equipment, including i ndi cator s, required to obtain the redundant safety grade r emote shutdown capabili ty to a harsh environment. The design and qual i f i cati on r equir ements will be applied in conformance with 10CFR50.49 and the guidance provided in NUREG-OBOO, section 7.4 and ICSB_Gy2 dance _Egt_lbe lutetntgigtigu_gi_Geogtgi_Desigu_Ctitutig_12_Cggcetuigg Beguitementp_Egt_ Remote _Sbytdowu_Stetigos.

e Attachmant 1: Page 4 RAI : I (d )

Secti on 7. 4.2.3 of the Limerick SER (NUREG-0991) states that the design does not include cedundgnt controls and display instrumentation. The February 15, 1985 letter shows that hardware changes are necessary for the addition of control (transfer switches) only. Information is necessary to clarify this i sstee as i t relates to additional redundant display instrumentation required to obtain the necessary redundancy.

Response

As shown in Attachment 3, the interim redundant remote shutdown procedure identifies the necessary redundant display instrumentation. The final redundant remote shutdown procedure will also identify the necessary redundant display instrumentation.

RAI I(e)

Information should be provided to verif y that the equipment, including indicators, used to obtain the tedundgut safety-related remote shutdown capability is to be safety-related including seismic qualification and the maintainability of functional operability under all service conditions postulated to occur.

Response

The equipment, including indicators, required to obtain the redundant remote shutdown capability meets or exceeds the same design and qualification requirements, including seismic qualification, that apply to the corresponding control room equipment, including indicators. The equipment qualification envelopes the service conditions expected to occur during shutdown conditions. The remote shutdown scenario does not include any accidents or transients that would expose the equipment, including indicators, required to obtain the redundant remote shutdown capability to a harsh environment. The design and qualification requirements have been applied in conformance with 10CFR50.49 and with the guidance provided in NUREG-0800, section 7.4 and ICES _Guideugg_Egt_Ibe_lutetntetettgu_gi Deuetel_Desinu_ctitecie_12_concetutug_Benuttements_E9c Bemote_Sbutdewu_ Stations.

i

Attechment la Pege 5 A table listing the parameters for which indication is displayed on the remote shutdown panel .is provided in Attachment 6. Also listed are the existing remote shutdown panel indicators, the corresponding control room indicators, and the indicators utilized in both the interim and final redundant remote shutdown procedures used to display these parameters. Information describing whether the indicators are safety-related and seismically qualified is also provided.

As described in our March 25, 1985 response to this RAI, we stated that the design and qualification of the following indicators was not in conformance with the guidance provided in NUREG 0800, Section 7.4 and ISGB_Guidgncg_Egt_Thg lulEEpteigtigu_gi_Genetel_Desigu_C titetig_19_Ggutetuing Beuui tements_Egt_8pmotg_ Shutdown _ Stations:

1. RCIC flow indicator FI-49-1ROOl-1

2. Reactor vessel pressure indicator PI-42-lRoll

3. Reactor vessel level indicator L1-42-1RO10

4. RHR loop A flow indicator FI-51-lROO5 These indicators are located on the remote shutdown panel.

We therefore replaced these indicators with similar General Electric type 180 vertical meters for which the required quali ty assurance and seismic quali fication documentation exists. As shown in Attachment 6, all portions of these indicating loops are safety-related and seismically qualified.

RA1:I(f)

The February 15, 1985 letter states that keylock transfer switches will be installed on various pump motor circuit breaker cubicles. Information should be provided to verify that manual transfer of control to the remote location (s) will not change the operating status of the associated equipment and that operation of the transfer switches will be alarmed in the control room.

Response

As whown in the sketch provided in Attachment 4, a keylocked, two position, maintained contacts transfer switch will be installed on each of the circui t breaker cubicles. The key will be r emovable f rom the NORM position. When the transfer switch is in NORM, the associated pump can be operated from the contr al room only. When the transfer switch is placed in EMER, the pump can only be operated by the circuit breaker test switch and a contr al r com annunciator will be attivaled identifying the associated equipment as out-of-service. The control room annunciator will not be able to be clear ed unless the transfer swi tch is placed back in NORM. Operation of the transfer switch will not cause a change in the oper ating status of the associated equipment.

1 I I Attachment 1: Page 6 i RAI: l (g )

Information should be provided to describe the administrative controls associated with key operated transfer switches and to verify that access to the keys will not be precluded by the event causing evacuation of the control room.

Response

The transfer switch keys will be located in a seismically mounted box located in the remote shutdown room to enable ready access. The remote shutdown room is locked closed and access to the room is limited in accordance with the plant's ex i s t i ng administrative procedures.

RAl:II(a)

Information should be provided to enable a one-to-one comparison of the tedundant interim system train of equipment (controls and display instrumentation presently installed and proposed jumpers) with the existing single train of safety-related remote shutdown equipment which was reviewed and accepted by the staff prior to licensing. FSAR Table 7.4-3 should be discussed as part of this comparison.

Responses Attachment 5 provides a comparison of the existing single tr ain of remote shutdown equipment as described in FSAR Table 7.4-3 and the interim redundant remote shutdown train of equipment. Each existing component has been evaluated for i ts worst case f ailure and each component's associated system design function has been verified to have been included in the interim redundant remote shutdown procedure.

Mul tiple components associated wi th a system design function are grouped together.

RAI: (iib)

Elementary draw:ngs and electrical schematics should be provided to show the implementation of the jumpering scheme for each piece of ceduudaut equipment affected during the interim period of operation whereby jumpers would have to be used in the event of control room evacuation.

Responses Attachment 2 is a copy of a portion of the B RHRSW pump motor control circuit, marked-up to show the temporary jumpers required to opurate the B RHRSW pump as directed by the interim redundant remnte shutdown procedure.

Similar temporary jumpers are required to operate the B ESW and B RHR pumps as directed by the interim redundant remote shutdown procedure.

e i Attachment 1: Pcge 7 RAI (IIc)

-The details of the steps involved to accomplish the jumpering should be described if not included in the procedures.

Response

The steps required *7 install the temporary jumpers of item II(b) are included the interim redundant remote shutdown procedure. This procedure is discussed in the response to item II(d).

RAI: (IId)

The remote shutdown operational procedures to be implemented prior to operation above 5% power should be provided for staff review and should be highlighted and/or annotated as necessary (i) to identify the specific use of jumpers for the tedundant equipment, (ii) to describe the manual val ve alignments required to support system operations, (iii) to identify the tedundant display instrumentation required for the assessment of equipment and plant status, and (iv) to demonstrate how the above interim measures in conjunction with the existing single safety-related remote shutdown train provide the required redundant shutdown capability.

Response

Attachment 3 's a discussion of the procedure to be used to provide interim redundant remote shutdown capability. The installation of jumpers, manual valve alignments, and the redundant display instrumentation are identified. The response to item II(a) demonstrates that the interim redundant remote shutdown procedure and associated train of equipment, in conjunction with the existing single remote shutdown train, provides the required redundant shutdown capability. The interim redundant remote shutdown procedure has been approved by the plant staff.

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l N ac k ent 3 Po.ge. 1 i

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l ALTERNATE REMOTE SHUTDOWN p PURPOSE This procedure describes. actions necessary'for hot shutdown and subsequent cooldown in the event of partial or total failure of the controls'on_the remote shutdown panel (or the RSP is not accessible).

CAUTION SYSTEM INTERLOCKS ARE NOT FUNCTIONAL WHILE TAKING THE ACTIONS DESCRIBED IN THIS PROCEDURE. AUTOMATIC FUNCTIONS MAY NOT INITIATE DUE TO THE EQUIPMENT MANIPULATIONS AND ACTIONS TAKEN BY THIS PROCEDURE.

SYMPTOMS Main control room becomes uninhabitable

'AND -

Controls on the remote shutdown panel are partially'or totally inoperable or are not accessible.

IMMEDIATE OPERATOR ACTIONS Scram'the reactor-Trip the main turbine -

Close the main steam line isolation ~ valves (MSIV)  !

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+ = =~;

ame m ae.-- = +=== .ev eo . . ,,&., ++ .m. . -

MadntertY 3 F y e 2_

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. FOLLOW-UP ACTIONS

'In the event that manual scram and MSIV closure was not performed prior to. leaving the control room, scram and

.. isolate Group 1 from the Auxiliary Equipment Room.

a. Open Breaker -for circuit 13, at panel LAY 160, RPS Trip System "A" vertical board. ,

AND

b. Open Breaker for circuit 13, at panel 1BY160, RPS

' Trip System "B" vertical board.

/ verify- Static Inverter at remote shutdown panel 10C201 is energized by red indicator being illuminated.

. IPlace all Transfer Switches to Emergency position at the remote shutdown panel. -

CAUTION WITH THE TRANSFER SWITCHES IN EMERGENCY, THE RCIC TURBINE WILL NOT TRIP ON REACTOR.HIGH LEVEL.

RCIC MINIMUM FLOW-BYPASS VALVE HV-49-lF019 WILL NOT FUNCTION AUTOMATICALLY FROM THE REMOTE SHUTDOWN PANEL.

THE VALVE SHOULD BE POSITIONED MANUALLY USING THE HAND SWITCH ON THE RSP.

RCIC WILL NOT AUTOMATICALLY INITIATE.

RCIC WILL NOT AUTOMATICALLY ISOLATE.

RCIC' TURBINE STEAM INLET IS NOT INTERLOCKED Td PREVENT OPENING WITH TURBINE EXHAUST VALVE CLOSED.

9

~~

lIn the event that controls on the remote become inoperable, or are not accessible, follow tae.

shutdown ' panel alternate plans below:

NOTE CONSIDER IMPLEMENTING EMERGENCY PLANS j If_RCIC is not available or fails to operate

,7 . _ _

l A ff a.c k ne eni' 3 Pase a i Alternate: Utilize HPCI

a. Auto Operation: HPCI auto starts from reactor level 2, trips at level 8 and restarts at level 2, maintai'ning reactor level.

b. Verify HPCI Initiation: By reactor level at the remote shutdown panel..

If the remote shutdown panel is not

. operable establish communications with an operator stationed in the

' auxiliary equipment room and verify HPCI flow via FIS55-lN651, Reactor Level.via LIS-42-lN691B on 10C618

'.or.if the auxiliary equipment room is not ace,essible, establish communications with the TSC and l verify HPCI and Reactor Level via ERFDS.

} If Reactor Pressure Control via "A", "C", and "N" Main Steam Relief Valves is not possible.

] ^] Alternate: Use ADS - E, H, K, M and S

~ Relief Valves

a. Auto. Operation: ADS auto open signals open E, H, K, M and S relief valves dumping steam to the suppression pool.

b. Auxiliary Equipment Room:, The ADS Panel 10CbJ1 includes manual switches for the relief valves (via

, the Division'III solenoids).

Establish communications with an operator stationed in the auxiliary equipment room and maintain reactor pressure at nominal pressure at .

1000 psig via the.se relief valves.

Verify Reactor Pressure via PIS IN690B on 10C618. Drywell Pressure can be monitored via PIS-42-lN694B on 10C618.

c. Verify operation of relief valves via reactor pressure instrumentation at the Remote Shutdown Panel.

- - - . - -: = --- -- -

~

r -

l Mfo.e. l. m e n t 3 8 age y i I QR If the remote shutdown panel is not accessible, establish communications with TSC and verify reactor' pressure and ADS initiation via ERFDS. -

/If Safeguard Bus 11 does not have power

• AND Local start of the associated diesel generator does not start diesel (local start.is by

. switching t'o local / remote switch to " local")

AND The engine shutdown reset has been manually operated at the diesel generator local control panel, and still no Dll bus power, then:

.l Alternate: Use Appendix A to this procedure to ensure hot shutdown and subsequent cooldown with equipment powered by bus 12.

') Recovery of Remote Shutdown Panel Capability or when the Main Control Room can be re-entered.

p'anel'or're-entry.of the main control

, , room is possible, assessment of the damage shall be made by shift Supervision.

1. If recovery of remote shutdown panel control is possible, system operation should be returned to the .

RSP by:.

a. Establishing RSP control of valves by closure of the Mov breakers which were opened.

l A Mack med .3 Pase s~

b. Establishing RSP control of pumps by removal of jumpers which were installed and by use of SE-1 Remote Shutdown Procedure.

2. If, control room re-entry is possible, place.those pumps and "

valves which were being operated manually (or by jumpers) in a

, condition so-that they can lun i operated from the control room. Do this by removal of the jumpers and closure of the breakers which were previously open. .

1

^ ~

. 3. If RCIC is' operating, place the I

RCIC flow controllers on 10C648 in manual and run the setpoint to minimum, so that when transfer from RSP to main control room is made, the RCIC turbine speed will ,

-decrease.  ;

4. Return the remote shutdown panel.to normal by performing S88.1.A.

e o e 4

9 8

ea meow -

AMo.c. k m en .3 Pase 6 APPENDIX A - D12 BUS A. USE EQUIPMENT POWERED BY BUS D12

'l. Start "D" ESW Pump locally by placing jumpers per Appendix A, Table 1. .

NOTE '

"B" ESW PUMP MAY ALSO BE STARTED BY LOCALLY STARTING THE "B" DIESEL GENERATOR ON PANEL 1BC514.

2. Lineup ESW, RHRSW return.to the spray pond by positioning valves indicated in Appendix A, Table 2.

. NOTE IF AVAILABLE, DISPATCH SOMEONE TO OBSERVE SPRAY POND EQUIPMENT, LEVEL AND AREA PARAMETERS. VERIFY HV-ll-015A IN PIPE TUNNEL EL. 201', HV-12-005 IN SPRAY POND PUMP HOUSE AND HV-12-017A IN MANHOLE BEHIND CIRC. WATER PUMP HOUSE, ARE CLOSED. MANUALLY CLOSE THESE VALVES IF NECESSARY.

3. Lineup RHR "B" in the suppression pool cooling mode by positioning valves indicated in Appendix A, Table 3.

4. Lineup the "B"-RHRSW System to the "B" RHR Heat Exchanger per Appendix A, Table 3.

5. Start the RHRSW Pump "B" locally by placing jumpers per Appendix A, Table 4.

6. Establish communications with the TSC so that flow can be determined via ERFDS for~FI-IR602B or if unavailable use local pump-Discharge Pressure Indicator PI-12-002B located in the Spray Pond Pump House or local RHR Heat Exchange Discharge Pre'ssure Indicator PIT-51-105B located in the "B" RHR Room. -

7. Start RHR "B" Pump locally by placing jumpers per Appendix A, Table 5.

8. Open valve HV-51-lF007B (minimum flow valve) per Appendix A, Table 6.

AOn e k m e,d 3 Pa 3 e- 7

9. Open valve HV-51-F024B and then close HV-51-F007B.

possible close HV-51-F007B as flow thru HV-51-F024B (If exceeds 1500 gpm as indicated on FISL-51-lN652B located on Auxiliary Equipment Room Panel. Open valves per Appendix A, Table 6.

10. Remain.in the suppression pool cooling mode, while operating the main steam relief valves, as necessary to bring the reactor pressure below the limit for RHR ,

shutdown cooling (96 psig) . Verify Suppression Pool Level'via LIS-55-lN662B located on Auxiliary Equipment Room Panel 10C618. Suppression Pool Temperature can be monitored by requesting IEC to attach a thermocouple test

~

box to Suppression P.ool Temperature Element (RHR "B" Pump Suction Line Temperature) . TE51-104B is located in the "B" RHR_ Pump Room. Connect test box to point A and B on the temperature element and read the thermocouple voltage. Use Appendix A, Table 9 to obtain corresponding temperature.

i CAUTION SHUTDOWN COOLING SHOULD RESULT IN A COOLDOWN OF LESS THAN 100 DEGREES-F IN ANY ONE HOUR.

11. Once below 96 psig, place the RHR System in the shutdown cooling mode'by alignment of valves per Appendix A, Table 7.

4 CAUTION

-...RHR VALVE INTERLOCKS MAY NOT BE FUNCTIONAL.IN THIS U PROCEDURE.

12. If it is not possible to close the associated recirc pump Suction Valve HV-43-lF023A (or B), or open the shutdown cooling suction inboard isolation valve HV-51-lF009 then go to Appendix A, Table 8 to modify.

the shutdown cooling mode so as to. inject into the c- vessel via the LPCI line with the RHR suction lined f up to the suppression pool.

A Mac.krnenY 3 Page. 8 APPENDIX A TABLE 1

~

LOCAL START OF "B" ESW PUMP OBP548

1. Go to 4KV Breaker 152-11608 and open the control door / cover. .

2. Remove both control fuses, #FU 16.

3. Jumper the breaker cell switch as indicated below (with #10 wire minimum):

A. Jumper. terminals 3 to 4 on the breaker cell switch.

B. Jumper terminals 7 to 8 on the breaker cell switch.

4. Ensure that the. test switch 152-11608/ CST is in the

" Pull-to-Lock" position.

5. Replace both control fuses, #FU 16.

6. To start the Pump, place the test switch 152-ll608/ CST to the "CLOSE" position..

7.- Pl' ace the test switch to'the " TRIP" position to stop the pump.

NOTE

' ONCE CONTROL IS ESTABLISHED AT THE RSP OR AT THE MAIN i

CONTROL ROOM, REMOVE THE JUMPERS INSTALLED IN 3A & B ABOVE.

i l

l I

l l

l l

k _ _ _

. ~~

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

I A Mo,c. b m e nY 3 Pa.3e 7

. APPENDIX A TABLE 2

~

ESW, RHRSW RETURN TO SPRAY POND FOR ESW "B" LOOP

1. Verify ESW pump "B" is Operating *.

2. Position the valves listed below to the positions indicated (if necessary open the valve (s) associated breaker and manually position the valve) .

(HV) Required Valve (MOV) Description Valve Position Breaker i of Valve COL.

12-032B OPEN (D124-S-L-02) Spraypond 52-52002 Nozzle Inlet 12-017A CLOSED (Dll4-S-L-13) Cooling Twr 52-51913 Rtn Crosstie 1

l 12-034B CLOSED (D124-S-L-05) Spraypond l 52-52005 Crosstie l

! 12-032D ^

CLOSED (D244-S-L-02) Spraypond 52-52202 Nozzle Inlet

• Note: "B" ESW pump may be verified ~as operating via communications with the TSC via ERFDS or if unavailable use Local Pump Discharge Pressure Indicator PI-ll-002A located in.the Spray Pond Pump House.

CAUTION IF MANPOWER IS AVAILABLE, DISPATCH MANPOWER WITH COMMUNICATIONS CAPABILITY TO THE SPRAY POND TO OBSERVE SPRAY POND LEVEL AND OTHER AREA PARAMETERS.

l

l A b el,n en + 3

[ ctg e /O APPENDIX A TABLE 3 (Page 1 of 2)-

VALVE LINE UP FOR RHR PUMP B

• TO SUPPRESSION POOL COOLING MODE

1. Position the'. valves listed below to the positions indicated (if necessary open the valve (s) associated breaker and

., . manually position the valve):

(HV) Required Valve (MOV) Description Valve Position Breaker i of Valve COL 51-lF003B OPEN .D124-R-G-01 RHR Ex.

(52-21201) Shell. Outlet 51-lF004B OPEN '

.D124-R-G-27 RHR PP (52-21227) Suction valve 51-lF015B CLOSED D124-R-G-33 R'HR S/D. Clg.

(52-21233) Rtn.Isol. Valve 51-lF016B

~ - ' '

CLOSED

-~

D124-R-C-02 'RRR Cntmt.

(52-21402) Spray Iso.

I Valve 51-lF017B' '

' CLOSED-'

D124-R-C RHR LPCI'. .

(52-21405) Inject. Valve 51-lF022 CLOSED Dll4-R-G-25 RHR Hd. ~

(52-21125)- Spray Iso.V1v 51-lF026B CLOSED D124-R-G-28 ~IUH1 Ex.

(52-21228) Outlet. to RCIC Iso.

51-lF047B OPEN D124-R-G-14 RHR HX.

(52-21214) Shell. Side.

Inlet

I AMo.c km en E 3 Po, qt. 1I APPENDIX A TABLE 3 (Page.2 of 2)

VALVE LINE UP FOR RHR PUMP B -

TO SUPPRESSION POOL COOLING MODE (HV) Required l Valve Valve (MOV) Description Position Breaker i of Valve COL Sl-lF048B CLOSED D124-R-G-15 RHR Ex.

(52-21215) Shell. Bypass 51-lF052B CLOSED D124-R-G-34 HPCI Stm.

(52-21234) to RHR Ex.

51-125B OPEN D124-R-G-12 RHR Loops (52-21212) B&D Full Flow Test Sl-153B CLOSED D124-R-G-42 HPCI to RHR (52-21242) Ex. Shutoff Bypass 2.. .

Position valve (s) below as indicated:

Sl-1F068B OPEN 1

Dl44-R-H-19 RHRSW Outlet (52-21819) to B RHR Ex.

l l

OCIcucktwe 3 Pk g e i nt_

APPENDIX A TABLE 4 LOCAL START OF RHRSW "B" PUMP OBP506 ~-

1. Go to 4KV Breaker 152-11603 and open the control door / cover.

2. Remove both control fuses, #FU 19.

3. Jumper the breaker cell switch as indicated below (with #10 wire' minimum) : -

A. Jumper terminals 3 t'o 4 on the breaker cell switch.

B. Jumper terminals 7 to 8 on the breaker cell switch.

4. Ensure that the test switch 152-ll603/ CST is in the

" Pull-to-Lock" position.

5. Replace both control fuses, #FU 19.

6. To start the Pump, place the test switch l'52-ll60$/ CST to the "CLOSE" position.

l 7. Place the test switch to the " TRIP" position to stop the pump.

NOTE ONCE CONTROL IS ESTABLISHED AT THE RSP OR AT THE MAIN CONTROL ROOM,. REMOVE THE JUMPERS INSTALLED IN 3A & B ABOVE.

l

- . . . . . . . . . . . . . . ._ l l

A Hae.Lm ent 3 BAge 13 APPENDIX A TABLE 5

~

LOCAL START OF RHR "B" PUMP 1BP202 l

1. Go to 4KV Breaker 152-11604 and open the control door / cover.

2. Remove both control fuses, fFU 18.

3. Jumper the breaker cell switch as indicated below.(with #10 '

wire minimum):

A. Jumper terminals 3 to 4 on the breaker cell switch.

~

B. ' Jumper terminals 7 to 8 on the breaker cell switch. I

4. Ensure that the test switch 152-ll604/ CST is in the '

" Pull-to-Lock" position.

5. Replace both control fuses, IFU 18.

6. To start'the Pump,. place.the test switch 152-11604/ CST'to the "CLOSE" position.

7. . Place the test switch to the " TRIP" position to stop the pump.

NOTE

ONCE CONiROL'IS ESTABLISHED AT THE RSP OR~AT THE MAIN CONTROL ROOM, REMOVE THE JUMPERS INSTALLED IN 3A & B ABOVE.

- ~

. . . . - . . . . . . . . . :- . 1 :. . .. ._.. . . ._ ..

I k$$o.c.Nru en$ 3 Page 11

, APPFNDIX A TABLE 6 ESTABLISH' MINIMUM FLOW ON RHR 1.

Open the minimum flow valve HV-51-F007B to obtain minimum 1500 gpm. using FISL-51-lN652B on 10C618.

NOTE IN ORDER TO OPEN THE MINIMUM FLOW VALVE IT MAY BE NECESSARY TO OPEN BREAKER D124-R-Gl-ll (52-21611) AND MANUALLY OPEN THE VALVE. .

2. Open valve HV-51-F024B then close valve HV-51-F007B.

NOTE IN ORDER TO OPEN THE FULL FLOW TEST RETURN VALVE HV-51-F024B IT MAY BE NECESSARY TO OPEN BREAKER D124-R-G-35 (52-21235) .

AND MANUALLY OPEN THE VALVE.

NOTE'

~

HV-51-F007B MAY BE CLOSED ONCE THE FLOW RATE THRU HV-51-F024B EXCEEDS 1500 GPM.

i -

l i

A f da c.k m ed .3 Pa g e. Is~

APPENDIX A TABLE 7

_(Page.1 of 4) i PLACING RHR IN SHUTDOWN COOLING

1. Shutdown RHR "B" Pump 1BP202

a. By use of HS-51-102B-1 in the main control room..

9.R

, b. 'By use of the " Test Switch" at 4KV Breaker 152-11604 -

(place " Test Switch" to " TRIP") - if jumpers were

.previously placed at the breaker' cell switch.

2. Place the valves listed below to the positions indicated: I NOTE THE VALVES MAY BE MANIPULATED "OPEN/ CLOSED" BY OPENING THE VALVE (S) ASSOCIATED BREAKER AND OPERATING THE VALVE WITH THE MANUAL OVERRIDE.

~

A 10 FOOT LADDER IS REQUIRED FOR VALVE HV-51-lF006B.

._ (HV) . Required Valve'(MOV) Description l Valve Position Breaker i of Valve . COL 51-F003B OPEN D124-R-G-01 RHR'Hx.

52-21201 Shell Side Outlet Sl-lF004B CLOSED D124-R-G-27 RHR PP 52-21227 Suction Valve

51-lF006B OPEN D124-R-G-31 RHR PP S/D

, 52-21231 Clg. Suction 51-lF008 OPEN D124-R-Gl-05 RHR S/D 52-21605 Cooling Suct.

Out. Iso.

. , , --.--,....we.

. :.- ~ . . - . - . . . .

I A tt cL uen t 3 Page llo APPENDIX A TABLE 7 (Page 2 of 4)

PLACING RHR IN SHUTDOWN COOLING .

(HV) Required Valve (MOV) Description Valve Position ' Breaker i of Valve COL 51-F009 OPEN Dll4-R-G-24 RHR S/D 52-21124 Cooling Suct. -

In. Iso.

Sl-lF0llB CLOSED D124-R-G-17 RHR Hx.

52-21217 Flush to Supp. Pool Sl-lF015B OPEN D124-R-G-33 RHR S/D 52-21233 Clg.'Rtn.

Out. Iso.

51-lF016B' -CLOSED D124-R-C-02 RHR Cntmt.

52-21402 Spray Out.

t Iso.

51-lF017B CLOSED D124-R-C-05 RHR LPCI .

52-21405 Inject Valve

~

~

i Sl-F022 CLOSED Dll4-R-G-25 RHR'Hd.

52-21125. _ Spray Inbd.

Iso.-

! 51-lF024B CLOSED D124-R-G-35 RHR Full 52-21235 Flow Test Return 51-lF026B CLOSED D124-R-G-28 RHR Hx.

52-21228 Out. to RCIC Iso.

l

//80o.ckme,d 3 Fa ge n

. APPENDIX A TABLE 7 (Page 3 of 4)

PLACING RHR IN SHUTDOWN COOLING (HV) Required Valve.(MOV) Description Valve Position Breaker # of Valve COL 51-lF0'27B CLOSED D124-R-G-29 RHR Supp.

52-21229 Pool Spray Hdr. Iso.

.Sl-lF047B OPEN D124-R-G-14 RHR HX.

52-21214 Shell Side Inlet 51-lF048B CLOSED D124-R-G-15 RHR HX.

52-21215 Shell Side Bypass Sl-lF052B' CLOSED D124-R-G-34 HPCI Steam 52-21234 to RHR Hx.

'51-125B OPEN D124-R-G-12: RHR'B&D' 52-21212 Full Flow Test 51-153B CLOSED D124-R-G-42 'HPCI Stm.

- 52-21242 ~to RHR Ex.

Bypass 51-lF007B CLOSED D124--R-Gl-ll RHR Min.

52-21611 Flow Sl-lF068B OPEN D144-R-H-19 RHRSW 52-21819 Outlet valve l

l

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

e e I

j9tfo.ckmenY 3 18F

/)a 3e APPENDIX A TABLE 7 (Page 4 of 4)

' PLACING RHR IN SHUTDOWN COOLING

3. Start the'RHRSW Pump OBP506 (If not already operating)-by Appendix B, Table 4. -

4.- Open HV-51-lF014B -

(HV) Required Valve (MOV) Description Valve Position Breaker i of Valve COL 51-lF014B .OPEN D124-R-G-32 RHRSW Hx.

Inlet

5. Open HV-51-F048B (HV) Required Valve (MOV) Description Valve Position. Breaker # of Valve COL 51-F048B. OPEN* D124-R-G-15 RHR Hx.

- Bvpass

• Throttle as necessary to maintain a reactor cooldown rate of

'less than 100 degrees F in any one hour.

6. Continue in shutdown cooling mode of operation to lower the reactor vessel water temperature to approximately 125 degrees F. Maintain this temperature by adjusting RHR pump flow via the RHR heat exchanger Bypass Valve 51-1F048B.

-- -- ~' -

.:.--......_.._.A_.._._..._

_ _ . .~ ._

I p .g f a e j , ,,,-t 3

/ hag e 19

.- APPENDIX A TABLE 8 (Page 1 of 3)

ALTERNATE SHUTDOWN COOLING VIA LPCI .

1. ]:f[ the Shutdown Cooling Suction Inboard Isolation Valve HV-lF009 cannot be opened or the Recirculation Pump Suction-Valve HV-43-lF023A (or B) cannot be Closed, modify the RHR Shutdown Cooling Mode to'take RHR Suction from the Suppression Pool and inject via LPCI injection valve, maintaining ~ reacto'r level by spilling to the Suppression Pool via the Relief, Valves.

. :2. Place the valves listed below to the positions indicated:

NOTE

~

THE VALVES MAY BE MANIPULATED "OPEN/ CLOSED":BY OPENING THE ASSOCIATED BREAKER FOR THE VALVE (S) AND THEN OPERATING THE VALVE WITH THE MANUAL OVERRIDE. -

RHR INJECTION VIA LPCI t

. -(HV) , Required . Valve .!(MOV) Description Valve Position Breaker i of Valve COL 51-F003B OPEN D124'-R-G-01 RHR'Hx. .

, 52-21201 Shell Side

• Outlet 51-lF004B OPEN D124-R-G-27 RHR PP 52-21227 suction valve 51-lF006B CLOSED D124-R-G-31 RHR PP S/D 52-21231 Clg. Suction 51-lF008 OPEN D124-R-Gl-05 RHR S/D 52-21605 Cooling Suct.

Out. Iso.

..-:... - .. . - . . . . . .. . ..~ - -...- - .. .. :

1 At-6ac. lum.ent 3 Page 20 APPENDIX A TABLE 8

- (Page 2 of 3)

RHR - INJECTION VIA LPCI ,

(HV) Required . Valve . (MOV) Description Valve Position Breaker i of Valve COL Sl-F009 'OPEN Dll4-R-G-24 RHR S/D 52-21124 Cooling Suct.

In. Iso.

Sl-lF0llB CLOSE- D124-R-G-17 RHR Ex.

52-21217 Flush to Supp. Pool Sl-lF015B CLOSED .D124-R-G-33 .RHR S/D 52-21233 Clg. Rtn.

Out. Iso.

Sl-lF016B CLOSED D124-R-C-02 RHR Cntmt.

52-21402 ' Spray Out.

'i Iso.

~

51-lF017B OPEN D124-R-C-05 ~

RHR L'PCI

~52-21405 ' Inject Valve

/' . 51-F022 CLOSED Dll4-R-G-25 RHR'Hd.

52-21125 Spray Inbd.

Iso.

51-lF024B CLOSED D124-R-G-35 RHR Full 52-21235 Flow Test

. Return 51-lF026B CLOSED D124-R-G-28 RHR Hx.

52-21228 Out. to Rcic. Iso.

,m~,. - _

-m. _

.___. - - w - m . _ _. ___ .o 4 #x4 m e .,

• 3

% 3e 2I APPENDIX A TABLE 8 (Page 3 of 3)

- . . -. . . :.w - . . . . . . .. . .. ..

RHR' INJECTION VIA LPCI' --

. (HV) Required Valve (MOV) Description Valve . Position Br'eaker i 'of Valve COL 51-lF027B ~

CLOSED D124-R-G-29 RHR Supp.

52-21229 Pool-Spray Hdr. Iso.

51-lF047B. OPEN .D124-R-G-14 .RHR'HX..

52-21214 Shell' Side-Inlet

, 51-lF048B ' CLOSED; .,D124-R-G .15  ;RHR HX.,

52-21215

~_.

'Shell-Side

' Bypass

=' .. .

.l. .

51-lF052B CLOSED ~ D124-R-G-34. ~

HPCI Steam 52--21234~

.to RHR Ex. .

.. . ~ .-~

~

T,51.-125B't.f r. '[ ..OPEN ; . .f'.-.D12'4-R-G-12 ~

l g ,

.RHR.B&D. _.

.+

' . ' 52--21212'-

1 . , . , ,, .

Full' Flow s.

, . .:. yg g g .

. ..: sy -

s .

-512153Bl%,

. CLOSED- .; D124-R-G-4 2 : .HPCI-Stm..

!52-21242

. , ,. 3 '

to RHR Ex.-

. 1- *_-  ;, . - -' Bypass

,  ; Y 'i .. . .' . . :,

i ' 51-lF0 07B '- . CLOSED' D124-R-Gl'-ll , RHR Min.

i

,. l ' ;;;" 7W .

.~52 f 21611'~ ' Flow 51-lF068B OPEN D144-R-H-19 RHRSW 52-21819 Outlet Valve i

I

.I i

BA. Led 3

. Q., Poaw e 2.2_

' APPENDIX A l

TABLE 9 i

i (Page 1 of 1)

• a i _ -

r

,. TYPE 7 THERMOCOUPLES ,

EEFEAEN G JUNC720N A7 33'F TEMPERATUAE6 IN DEGREE 8 F83 PTS IM8b , _

DEG F 0 1 . 3 $ 4 p. *e _7 3 9 13 c tw.monecuse va74se a waurs nn.uva75

-0 909 -0 446 =0.447

• 0 a0.674 -0 654 *0 633 =0 613 -SeS92 * -0.671 4 0.550 * -0 539 -0 299 -0.277 =0.IM

-0 428 -0 404 -0 363' =0.341 40 320

.30 =0.447 -0 446 *0 383

-0.0 M +0 043 20 -0.256 =0 215 -0.214 *0 193 -0 171 -0 158 -c.129 -0 107 -00 086 130 0,151 0 173

.

• 30 +0.043 -0.022 . 0 000 0 033 0 043 0.063 0.986

• 00 103 32s 0 347 0.369 0 391 40 0.173 0 195 Dette entss, 0 260 0.tst 0. sos 0.438' 0 479 a.801 0.533 0 545 0 567 0 546 0 611

. 5.0 ; 0.39I* 9 413 O.457.

0.748 0 747 0 789 0.s13 0.sM 60 0.611 . 0,6M 066 0 473 c.700 0 723 1 034

• 1,037 2.068 79

• 8.s34 0.s5" 9 8@79Setet 0 924 0.947 0.969 0.992 3.151 1.175 11%6 1 219 1 243 1.265 1 268 a0 1.060 1 083 1.105 letts

'1 499 3.H4 1 403 1.424 1 449 1 472 90 , 1,2as '1 311 1 334 . 1 357 1 380

2. m . 2. m :1. = 2.m 1.m 1.m m 1.n's i.M2. 1. m 1. m 2. m .

1.964 .1.988 als

• 1.752 1.778 1.799 1 333 3 8u 1.s49 1.s93 - 1 917 - 1 940 2.202 2.226

'1.988 3 011 2 059 ,8 059 2 083 3 107 - 3.131 23 395 154 2 178 120 3 447

{ .

150 m

2.226 2.y?

3 250

2. m 2 274 2.298 te323 ' 2 347 , 2.371

,m. 2 M0 3.uS .m . Sem 2.,

m 2 419 2.Mt 2 44S 2.,a7 2.m 2 760 2 7s5 ' t,009 . 2.884' 2.ast 2.sas 2 90s 2.935-* 3.954 150 2.7H - 2 786 3 088 3.107 3.151 3 156 3.181 3.206 160 2.958 3 007 3 032 3 057 3e432

• 3 454 3 281 'S.307 3 332 3.387 3.332 Se407 178 3.206

• 32231 982 3 256 S. 3 5A . 3.699 , 3 635' 3.MO *3.646 3 7H 280 3.458 3 483 3 505 3 533 3.M1 3.M7 3 762s 3,748

• 3,5pt 3.s39. 3.864 3.590 3 914 313 290,3.711 3 737 , .+.

4. m 4.199 ~.4. m 200 3,u? 3.= 4 019 4 04. ... 4.m 4.m 4.Ms 44M 4.M0 4.486 4.303 4 339 4.355 4.3s1 4.408 210 4.225 . 4 251 4.277 4 591. 4,&J 4.643 4 670 4 496 4.722 4 749

'230

• 4.4s4 4.512 - 4.S$8 4 565 S.0M 288 4.749 4.775 4.501 4.82 4.854 4.553 4.907 4 9M ' 4 960*.4.987 S.2s1 -

S.134 5 147 5.174 S.,300 5 327 S.284 240 5 014 S.040.s 5 067 S.093 .. .

s.469 . 5 4M -5'523 .S.558 250 s.Est 3 ,507 . se s p 3.361 sessa 3.413 s.442 .

. 260 .3 550 , 5 577 9.6M S.631 S.655 5.6sp S.?!R 5.739 S.767 5.7M 5.s21 5.985 6.012 6 039 s.067 6.cM.

370 5.821 5 848 5,875 5,903 5 958 36957 6.M2 6.369

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Attachment 5 Comparison of the Existing Remote Shutdown Equipment and the Interim Redundant Remote Shutdown Capability Items 1-5, 29, 35-41, 49, 73, 74, 86-88, and 102-104 are the remote shutdown panel system transfer switches that are provided to transfer control of the Standby AC Power Supply, RCIC, A RHR, A RHRSW, A ESW, Nuclear Boiler, and Containment and Suppression Pool Monitoring systems to the remote shutdown panel. The failure of any one of these switches would require implementation of the interim redundant remote shutdown procedure to provide the necessary remote shutdown functions.

Items 6-24, and 26-28 are provided to control RCIC from the remote shutdown panel to provide high pressure reactor coolant make-up. The redundant method of high preusure reactor coolant make-up is to allow automatic operation of HPCI per the interim redundant remote shutdown procedure.

HPCI will automatically cycle between reactor vessel water level 2 and level 8. HPCI operation can be monitored via flow indicator FIS-55-1N651 located on auxiliary equipment room panel 10C618. Condensate storage tank level can be monitored via level indicator LIS-55-1N661B located on auniliary equipment panel 10C618.

Item 25 provides indication of RCIC turbine speed. RCIC turbine speed indication is supplemental information not required to bring the reactor to a hot shutdown or cold shutdown condition. RCIC operation is monitored via the RCIC flow indicator. Loss of this indication will have no impact on shutdown from the remote shutdown panel or during use of the interim redundant remote shutdown procedure.

Hence, redundant indication of RCIC speed is not provided.

Item 30 is provided to monitor reactor vessel pressure. A redundant reactor vessel pressure indicator PIS-42-1N690B is located on auxiliary equipment room panel 10C618.

Item 31 is provided to monitor reactor vessel level. A redundant reactor vessel level indicator LIS-42-1N691B is located on auxiliary equipment room panel 10C618.

Attcchment 5: Page 2 Items 32-34 are the Main Steam Line (MSL) relief valves provided to limit and reduce reactor vessel pressure. The redundant method to limit and reduce reactor vessel pressure is to use the division III MSL relief valves per the interim redundant remote shutdown procedure. Manual switches to operate the division III valves are located on auxiliary equipment room panel 10C631.

Items 42-48, 50-67 are provided to operate the the A loop of RHR in the suppression pool cooling or shutdown cooling modes. The redundant method of suppression pool cooling is to manually align the B loop of RHR per the interim redundant remote shutdown procedure. The redundant method of shutdown cooling is to manually align the B loop of RHR per the interim redundant remote shutdown procedure.

Operation of the B loop of RHR in either the suppression pool cooling or shutdown cooling modes can be monitored via the flow indicator FISL-51-1N652B located on auxiliary equipment room panel 10C618.

Item 68 provides position indication of the A RHR heat exchanger bypass valve. Position indication of the A RHR heat exchanger bypass valve is supplemental information not required to bring the reactor to a hot shutdown or cold shutdown condition. The A RHR heat exchanger bypass valve is throttled to regulate RHR loop A flow to maintain a reactor cooldown rate of 100 F. per hour. There is no established correspondence between bypass valve position and reactor cooldown rate. The reactor cooldown rate is determined by observing reactor pressure. Loss of bypass valve position indication will have no impact on shutdown from the remote shutdown panel or during use of the interim redundant remote shutdown procedure. Hence, redundant position indication of the A RHR heat exchanger bypass valve is not provided.

Items 69-72 and 75-79 are provided to align and operate the A loop of RHRSW. The redundant method to provide RHRSW is to manually align the B loop of RHRSW per the interim redundant remote shutdown procedure. Operation of the B loop of RHRSW can be monitored via the local pump discharge pressure indicator PI-12-OO28.

Items 80-82 are RHRSW and ESW valves. In order to place RHRSW and ESW in a configuration such that they can be readily placed in service from the remote shutdown panel, these valves automatically close when the remote shutdown panel system transfer switches are placed in EMER. These valves are not required to change position once they have closed and remain closed as long as the transfer switches are in EMER. The redundant method to position these valves is to manually close them per the interim redundant remote shutdown procedur e.

Attachment 5: Paga 3

' Items 83-85 are provided to operate the A loop of ESW.

The redundant method to provide ESW is to manually align the B loop of_ESW per the interim redundant remote shutdown procedure. Operation of the_ B loop of ESW can be monitored via the local pump discharge pressure indicator PI-11-OO2B.

Item 89 is provided to monitor drywell pressure. A redundant drywell pressure indicator PIS-42-1N694B is located on auxiliary equipment room panel 10C618.

Item 90 provides drywell airspace temperature indication.

Redundant indication is not necessary for the following reasons:

1.- Drywell pressure indication (indicative of drywell temperature) is also provided on the remote shutdown panel. Redundant drywell pressure indication is available as described for item 89 above.

2. There are no postulated accidents or transients in the remote shutdown scenario that would cause a significant increase in drywell temperature and require mitigating or protective actions. No equipment is provided on the remote shutdown panel to protect against or mitigate a significant increase in drywell temperature. Loss of this indication will have no impact on shutdown from the remote shutdown panel or during use of the interim redundant remote shutdown procedure.

Item 91 is provided to monitor suppression pool level. A redundant suppression pool l evel indicator LIS-55-1N662B is located on auxiliary equipment room panel 10C618.

Item 92 provides suppression pool temperature indication via the A RHR pump suction line temperature element.

Redundant indication will be available on ERFDS when the SPDS is placed in service. Until the SPDS is placed in service, redundant suppression pool temperature indication will be availble via the B RHR pump suction line temperature element per the interim redundant remote shutdown procedure.

F '

Attachment 5: Pcge 4 Items 93-98 provide manual control of the application of offsite power to the division I, II, and III safeguard busses. The design basis for the remote shutdown system includes a loss of offsite power. The diesel generators will automatically start and supply power to the division I, II, and III safeguard busses. Therefore, these items are not required to operate to support shutdown from the remote shutdown panel or during use of the interim redundant remote shutdown procedure. Hence, redundant controls, to supply offsite power to the division I, and III safeguard busses, ar e not required. Redundant control of the division II safeguard bus feeder breaker is provided on the breaker cubicl e f or compliance with safe shutdown requirements for an exposure fire in the remote shutdown room.

Items99-101 provide manual control of the application of power to the safeguard 440 Volt load centers. These breakers automatically close on availability of safeguard bus voltage. The failure of one of these breakers would require implementation of the interim redundant remote shutdown procedure to provide the necessary remote shutdown functions. Hence, redundant controls to operate the division I and III safeguard load center transformer breakers are not required. Redundant control of the division II safeguard load center transformer breaker is provided on the breaker cubicle for compliance with safe shutdown requirements for an exposure fire in the remote shutdown room.

m

LGS FSAR

• TABLE 7.4-3 (Page 1 of 9)

REMOTE SHUTDOWN PANEL INSTRUMENTATION i Hot Cold Unit 1 Unit 2 Shutdown ___ Shutdown ____pesgription BCIC System l* HSS-49-191 HSS-49-291 X X Control-RCIC Remote' Shutdown Transfer Div. II 2e HSS-49-192 HSS-49-292 X X Control-RCIC R'e te Shutdown Transfer Div. I J. HSS-49-193 HSS-49-293 X X Control-RCIC Remote Shutdown Transfer T, HSS-49-195 HSS-49-295 X X Control-RCIC Remote Shutdown Transfer JO HSS-49-196 HSS-49-296 i i X X Control-RCIC.Re ote Shutdown Transfer

8. HV-49-1F076 HV-4 9-2 F076 X Control-RCIC Ste'am Line warmup valve

~7 HV-49-1F060 HV-49-2F060 X 1

X Control-RCIC tur exhaust 8.HV-50-112 HV-50-212 -

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X X control-RCIC.tu trip throttle valve 9.HV 1 F04 5 HV-50-2F005 X X Control-PCIC st m supply valve C.HV-49-1F008 HV-49-2F008 "

X X Control-RCIC st a line outboard isolation valve l1.HV-49-1F007 *W-49-2 F007 ~X X Control-RCIC st a line inboard isolation valve J2.HV-49-1F031 HV-49-2F031 X X Control-RCIC suppression pool water supply valve

/J.HV-49-1F029 HV-49-2F029  ! X X Control-RCIC' suppression pool water supply valve jif,HV-49-1F010 HV-49-2F010 X X Control-RCIC cond storage to pump suction valve I S HV-49-1F019 NV-49-2F019 X X Control-RCIC puml discharge min.flow valve f6.HV-49-1F022 HV-49-2F022 X Control-RCIC Test Loop Isolation valve k l7,HV-50-1F046 HV-50-2F046 X l S X' Control-RCIC Cooling Water Supply. Isolation

[

'b P 9>

- G3 pm j

9 m

(

- .i o

S i

1 a

IGS FSAR f

• TABLE 7.4-3 (Cont'd) (Page 2 of 9)

Unit 1 Hot Cold Unit 2 Shutdown Shutdown Description i

/O.'HV-49-1F012 HV-49-2F012 X X Control-RCIC pump o oard disch valve II.HV-49-1F013 HV-49-2F013 K K Control-RCIC pump i ard disch valve 10 10P220 20P220 K K Control-RCIC barometric condenser condensate pump 31-10P219 '20P219 I K i

Control-RCIC barometric condenser vacuum pump

11. BV-4 9-1F002 HV-49-2F002 X K. Control-RCIC barome ic condenser vacuum pump discharge valve, 3.3.HV-49-1F080 HV-49-2F080 '

E K Control-RCIC turb exh outboard vacuum relief l isolation valve 1 2 T. HV-49-1F084 HV-49-2F084 'I I control-RCIC turb eich inboard vacuum " relief l isolation valve  !

'Af", SI-50-1R003 SI-50-2R003 K K Indication - RCIC turb speed 2(. . FC-4 9-1R001 FC-49-2R001 1 Controller-RCICpul:pdischargeflow X

1") FI-49-1R001-1 FI-49-2R0'01-1 E I 'I' ndicator ' RCIC pump discharge flow 17.LI-55-112-2 LI-55-212-2 K' K ' Indicator - Condensate Storage tank level Indicating lights are provided for all of the above listed valves as well as t;he followingi turbine tripped, turbine bearing tesserature oil pressure low, turbine governor bearing oil temperature highi . turbine coupling bearing oil high. ~

k f

O DF 3

" 4D

. h k

Rev. 40, 01/85

{

}

. LGS FSAR .

i TABLE 7.4-3 (Cont'd) - --

(Page 3 of 9)

Hot Cold Unit 1 Unit 2 Shutdown " Shutdown Description

~

Nuclear Boiler System 2 9. HSS-41-191 HSS-41-291 . I X Control - Nuclea - boiler Remote Shutdown Transfer I

I 30. PI-42-1R011 PI-42-2RO11 i, I X' Indication -_ rea: tor vessel pressure

31. LI-42-1RO10 LI-42-2R010 X X' Indication ~rea : tor vessel level

32. PSv-41-1F013A PSV-41-2F013A X '

X Control - Main S:eam line relief valve i 33. PSV-41-1F013C PSV-41-2F013C X ~X Control - Main s eam line relief valve 3'f. PSv-41-Ir013N

~

PSV-41-2F013N I I Control - Main s'eam line relief valve j RHR System N I ' '

35. HSS-51-192

• HSS-51-292 I X Control-RHR Remo';e Shutdown Transfer

{ 3 6. RSS-51-193 HSS-51-293 'a K-

,X- Control'RHR.Remo'e' Shutdown Transfer

' ' -(. . . .

3"), HSS-51-194 HSS-5.1-294 X' -

X _ . Control-RHR Remo';e Shutdown Transfer l

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,,- r b s

g D

r p &

L.D b

, -i -

~ : (D 9

-J Rev. 38, 11/84

- - - - - , o _ _ _

LGS FSAR .

TABLE 7.4-3 (Cont' d) (Page 4 of 9)

H3t ~'

Cold-Unit 1 Unit 2 Shutdown Shutdown- Description PHR System (Cont'd) t

. 38. BSS-51-195 HSS-51-295 I Y Control-RHR Remote Shutdown Transfer 3 9. HSS-51-196 . HSS-51-296 X X -Control-RHR Remo e Shutdown Transfer Ago, BSS-51-197 HSS-51-297 1 X' Control-RHR Remo e Shutdown Transfer

~

8//. HSS-51-198 HSS-51-29 8 I X Coritrol-RHR Remote Shutdown Transfer

~

'f 2. HV-51-1F009 HV-51-2F009 X- ' control-RHR pump shutdown cooling suction valve 8/3. HV-51-1F008 HV-51-2F008 X Control-RHR' pump ' shutdown cooling suction valve

'f af. HV-51-1F006A HV-51-2F006A K I control-RHR' pump stintdown cooling suction valve 8/S.HV-51-1F006B - HV-51-2F006B X X Control-RHR pump shutdown cooling suction valve

'8/6. BV-51-1F004A HV-51-2F004A lt .K I < Control-RHR pump s' action isolation valve 8/ ').1AP202 2AP202 K I Control-RHR pump

-97.HV-43-1F023A HV-43-2F023A- X Control-Recircula .lon. pump suction valve l

8/y, HSS-43-191' 'HSS-43-291 X' ,

Control-Remote s tSown transfer

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i

.. e T L :.- '. + I ",

l .__..

~_ * : 3 -

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h

~

m' *

' .l '

F

'D p

p p

, ID 3

0) * .

4 ,

Pev. 40, 01/85

_ . . . . . . . . . . . _ = __

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I i

• l

-TABLE 7.4-3 (Cont'd)

I (Page 5 of 9)

I- Hot Cold - '

, Unit 1 Unit 2 Shutdog__ shutdown DescE12 tion i 80, HV-51-1F007A HV-51-2F007A X I - X Control-RHR min $ Low bypass valve I

S/. HV-51-1F048A HV-51-2F048A X X Control-RHR.heatlexchanger bypass valve fl. HV-51-1F015A HV-51-2F015A X 'X' Control.- Shutdo d Cooling Injection i

) . S3. HV-51-1F022 .HV-51-2F022' X. Control-BHR rea'ct r' vessel head spray valve I '

fy. HV-51-1F023 HV-51-2F023 .X- Control-BHR react r vessel head spray valve ff. HV-51-1FC16 A HV-51-2F016A X i Control - BHR drywell spray valve f

Sf.HV-51-1F011A HV-51-2F011A 'X X~ Control 2BHR Loop l:est line valve

87. HV-51-1F017A HV-51-2F017 A X X' Control-RHR ' LPCI :.njection valve

~

68. HV-51-1F024 A HV-51-2F024A X' X ' Control.-RHR. full ;ilow bypass valve 8T. HV-51-1F027 A HV-51-2F027A X' X

^

Control 2RHR suppritssion pool spray valve

.., A.

40, HV-51-1F047A HV-51-2F047A i X X

• Control-HHR'HX-in:.et' valve -

s .

\ $

.=

' . M $

n, . * ,,

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p, -

.+, g

. . :. - . - .] a 2 ' , ' --f-j "

'j ('

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. ' <- 2'n .

9

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LGS FSAR TABLE.7.4-3 (Conted)_ (Page 6 of 9)

Hot Cold Unit _1

_ __ _ tinit_2 . Shutdg_wg___ _ Shutdown [Desggigtion BHR Systs (Cont'd) fo l- HV-51-1F003 A HV-51-2F003A X X - Control-RHR heat exchanger outlet valve S2.HV-51-1F026A -

HV-51-2F026A X X Control-RHR HX to RCIC valve i

b3.IN-51-1F049 HV-51-2F049 X Control-RHR disch to radwaste valve I

bV.HV-51-125A HV-51-225A X X- Control-RHR full low bypass valve ES.HV-51-1F052A HV-51-2F052A X X Control-HPCI Steam line valve

64. HV-51-153A HV-51-253A X control-HPCI Stean line warmup valve 6 7- FI-51-1R005 FI-51-2R005 x X- Indication-RHR system flow 6 7,ZI-51-148-2 ZI-51-248-2 X X Heat exchanger bypass valve position

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t t t

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L3S FSAR TABLE 7.4-3 (Cont'd) (Page 7 of 9)

- ~~' --- - Hot Cold. . ._. '.

l Unit, 2 RhutSown Shutdown Description f Unit 1 i l- l'

! RHR Service Water System

49.HSS-12-015A-2 X X , Control'-' Spray pond / cooling tower select h 70. HSS-12-015C-2 , 'X X control - Spray poud/ cooling tower select X X Control f- spray /by pass select

.- 7/. HSS-12-016A-2 ,

X X Control - spray /by pass select

~)2. HSS- 12-016C- 2

~73.HSS-12-094 iX X. Control - Remote s.tutdown transfer

.X . X - Control - Pemote s tutdown transfer

. *)Y.HSS-12-093

~1S. HV 1F014 A HV- 51-2F014 A 'X -X . Control - PHRSW HTC. inlet valve.

~14,OAP506 OCP506 .K X Control- RHRSW'punp

~71. HV-51-1F068A HV-51-2F068A .X X Cor. trol - RHRSW HTC outlet valva

., s_.

~)K.PI-12-001A-2 s - PI-12-00.1A-3 X~ ,X- Indicator - hMRSW Pump Discharge Pressure

{X outlet pressure X'.[

~

'. PI-51-20 5 A-2 X 77.PI-51-155A-2 .

} Indicator' - RHRSW RHR SW HTX sutlet high l

' Indicating lights are provided for all the above listed valves as well as,the, l radiation.. ,

l

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c. ; -..

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P

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Rev. 33, 06/84 i

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TABLE 7.4-3 (Cont'd) (Page 8 of 9) r -

' Ho t  :. Cold - -

ifnit 1 Unit 2 Shutdown Shutdown Description I The: following valves'of the ESW and R'HRSW systems; are actuated by signals from .the trans er t switches: {

.e 1 ,

.. n .: .

t 3 0. HV-12-00 5 ESW and RHRSW pumps'wetwell ,intertie gate ' '

l

? l' HV-12-017A ESH an'd RHRSW' cooling, tower return cross tief ,

[

T1. EV-11-015A . ESH loop A discharge to

• RHRSW loop' B '

l Pmeroency Service Wat'er System

. ' c '

T 3. CAP 548 X, .X -

. Control ,emerger cy service water pump .

'8h.~PI-11-003A-2 X- X. ,

Ind'icat' ion - emergency _ service water pressure

. y,g" HV-11-01 M -

CX. . '. X . . . a Control - ESW loop'A return to RHRSW 3 ~. .' . ;-  : J.- *

~

Tf,' HSS-11-091

'.: g ,c

,. :1

. ". 3 .. , . . - -

" . . -y,..

, f g., ',- , _ , ' ll,. X . , 7.

. ,, e '.". X ' ? - - 3 , Control-' -. Remote shutdown'. tr.ansfer

,g , , . . . , . . .. , . ,.

( XL,,y .E %.,g.p.c.-'

S*J. HSS-11-092  ?

"'i,. -

• . . . . . Xc.; , ..j : Control: - ' Remote shutdown.. transfer

. ~.

.... - ~  :, . .

..s. ,x.. . -. . . p. 3 . . - ..,,

F

- ? % HSS-11-093 N -'i'.,.." X .Wy..

r. .

. ., c,. ,1 Control - Remote shutdown transfer.

. . . ~ . .

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s .

- X . ., e-7 q., , , ,-

, . h' i .

, , , I; - ,' ( ', *

. .. ;.* .:; :af I- . .- '."; V., i ,.. , ,,

. .? , ,

... . 3 N..  : a b: . .T M b " .C.'c.d'. .'.. 9 ,,: ,;.(d ,;.. E' '

containment and Suppression ~ Pool Monitoring System

@ . :.l..

- G /' '.,

Flo- 2. Q.~) o . . .U.W.'f 7,N N. y)A .J. h- ( E i

'2 .

- .. ,y 3 9. PI-4 2- H&tt .

2. . PI-42-2fte tt . . . . "T.g.' .-' I ..  ;'".' .c X./ ;..@' O. Indication..,) .dryvell. pre...ssure. , .

- 2 '-- .a . . M.3 p-f-s.Q.t-.<?. . ' : . 4.'N .;d!f-5 . , - - C r'3 T p. E IM M .<!l S tr.,,.iiQ qry .c

. 90 i TI-57-122  ; Indication.; , .dryv4,5 ell e -6 ....ture-

.TI-57-222;-7 . . '12 X- , X : , r. tempera

. .. . - ;. _ p . . 3,  %

3/. LI-55-115-2 LI-55-215-2 ' 4 .

X. ~';X :: .

' c.. '. .Indication . ,, sup .. . ression pool level a:...._. ..

- - - ~

. ,....: . . . :3my , . .%. , . ,.

9 2,, TI-51-104A TI-51-204Ay .c . ;jA .. f r: , -

[X,j. ", 'c ~ 7,,Indicasion'J.-g,up s ression'bool' temperature 3

b c ' *. . , . : ,:e > :,-

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, Rev. 40, 01/85 i

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. TABLR ; 7. 4-3.. (Cont 5) 't,.. (Page 9 of 9) i Hot Cold k j ggit 1 UDit 2 Sbat_ggwn Shutdown Des _griptign_ _

S.tangby_gg_gower Supply

_ I

93. iS2-iiS09/CSR X. . X 101-Dii Safeguard SWGR feeaer breaker I

8 152-11509/CSE X X 101-D21 Safeguard SWGR feeder breaker

.\ . .

l 94.152-11609/CSR . I X. 101-D12 Safegtiard 'SWGB feeder breaker J .

t 152-11609/CSR  ! X X .101-D22 safeguard SWGR feeder breaker

96 152-11709/CSR X- .X 101-D13 Safeguard 'SWGR. feeder breaker ,

{ 152-11709/CSR 'I! X X' 101-D23 S$tfeguard SWGR feeder breaker 96,152-11502/CSE X X 201-D11 Safeguard SWGB feeder breaker 152-1'1502/CSR p X X 201-D21 Safeguard'SWGR_ feeder breaker 97.152-11602/CSR I' X X ' 201-D12 Safeguard SWGR. feeder breaker i  ;

. 152-11602/CSR- X -

X 201-D22 Safeguard SWGR feeder breaker TI.152-11702/CSR X X 201-D13 Safeguarq SWGN' feeder breaker

. l

.. 152-11702/CSR X X _ 201-D23, Safeguard SWGR feeder breaker 91.'152-11505/CSE ,,.X_ .

X. D'114 Safeguard LC XFMR. breaker

.t . f -

152'11505/CSR. -[X- ,

.X.' D214 Safeguard LC XFMR breaker p . ICO.152-11605/CSR b,II. X"'- D1 4 Sa'feg ['k LC XFM bFeaker.

~

'8

'E .~-

d _'A.-

SX , , ,

152-116d'5/ChR ~' X '

. X- D224 Safeguard LC XFMR breaker

-[.

~ '

/0f.152-11705/CSR J '

y- 'X #'

X. D.134iS afeguard LC IXFMR breaker s '", . . Q p

t

~

152-11705/CSR"- '

.. X X D234. Safeguard 'LC XFMR breaker p

,JO2 143-115/CS g

143-115/CS

.d.,0X ,

X'- Control transfer P g 103.143-116/CS  ; a

• iii3-116/CS : ,

X' ,-X- - Control: transfer' m latf.143-117/CS 143-117/CS' ~ X X Control transfer-

~

Indicating lights are provided for all the abdve listed breakers.

m

p e a ca.

Attachaent 6 FRAMETER Ells 11NG FEM 0iE SHUIDOWN COERESPONDING CONTROL INDICATOR USED FOR INTERIM L FANEL INDICATOR R00M INDICATOR FINAL REDUNIANT REMOTE SHuiDOWN FROEEDURES SAFEIV/ SEISMIC SAFEif/ SEISMIC SAFETY / SEISMIC RELATED QUAL FELATED QUAL RELATED QUAL FCIC speed SI-50-IR003 NO NO SI-50-101 NO NO N/A (NOTE 1)

FCIC flow F1-47-1R001-1 VES VES FI-49-1R600-1 YES VES FIS-55-lN651 VES YES CSI level LI-55-ll2-2 NO NO LI-55-112-1 NO NO LIS-55-1N661B YES VES Fe ctor pressure FI-42-!R011 VES YES JR-42-IR623A YES YES FIS-42-IN690B )ES VES Fe2ctor level LI-42-IR010 1ES 1ES (R-42-1R623A VES iES LIS-42-IN6918 1ES iES FHR loop fica F1-51-lR005 VES 1ES F1-51-!R603A iES YES FIS-51-1N652B iES VES FHR heat each byp 11-51-148-2 ND NO Zl-48-148-1 NO NO N/A (NOTE 1) valve position f;HR heat etch FHRSW FI-51-105A-2 NO NO FI-51-105A-1 NO NO FIS-51-165B NO N0 outlet pressure FhESd puep disch F1-12-001A-2 NO NO F1-12-001A-1 NO NO F1-12-002B NO N0 pressure ESW pump disch F1-il-003A-2 h0 NO F1-il-003A-1 NO NO FI-II-0028 NO N0 pressure Drytell pressure FI-42-170-2 )ES )ES FI-42-170-1 )ES iES FIS-42-1N6948 YES 1ES Drywell teeperature T1-57-122 iES rES TR-57-122 iES 1ES N/A (NOTE 1)

Suppression pool L1-55-115-2 NO NO L1-55-115-1 NO NO LIS-55-IN662B 1ES VES level Suppression pool Il-51-104A NO NO IFS-55-1F605 NO NO EFFDS(interia NO N0 temperaturelFHR .ia purp suction line IE-51-1048) lempetalutel N0!E 1: As described in Attachsent 5, stees 25, 68,and 90, these paraseters are not required to bring the plant to a hot thutdown or a cold shutdown cordition. Hence, redundant indication is not provided.

t_