L-MT-06-086, Response to Request for ECCS Surveillance Documentation to Confirm the Functionality of the LPCI Loop Select Time Delay Relays During Past Surveillance Testing

Response to Request for ECCS Surveillance Documentation to Confirm the Functionality of the LPCI Loop Select Time Delay Relays During Past Surveillance Testing

ML063630253
Person / Time
Site:	Monticello
Issue date:	12/28/2006
From:	Sawatzke B Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
10 CFR 50.90, L-MT-06-086
Download: ML063630253 (30)

Text

Monticello Nuclear Generatinq Plant N

Committed to Nucl Operated by Nuclear Management Company. LLC December 28,2006 L-MT-06-086 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Response to Request for ECCS Surveillance Documentation to Confirm the Functionalitv of the LPCI Loop Select Time Delay Relays During Past S~~rveillance Testing

Reference:

1) NMC letter to U.S. NRC, "License Amendment Request: One-Time Low Pressure Coolant Injection Loop Select Logic Time Delay Relay Surveillamce Interval Extension," (L-MT-06-071), dated November 14, 2006.

On November 14,2006, ,the Nuclear Management Company, LLC (NMC) submitted a license amendment request for the Monticello Nuclear Generating Plant (Reference 1) to request a one-time extension to the quarterly surveillance interval specified in the Technical Specifications (TS) for 'the following low pressure coolant injection (LPCI) loop select logic functions in Table 3.3.5.1-1 of Specification 3.3.5.1, "Emergency Core Cooling System (ECCS) Instrumentation:"

2.k. Reactor Steam Dome Pressure - Time Delay Relay (Break Detection) 2.1. Recirculation Pump Differential Pressure - Time Delay Relay (Break Detection) 2.m. Recirculation Riser Differential Pressure - Time Delay Relay (Break Detection)

On December 8, 2006, a teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and RIMC. The NRC requested Emergency Core Cooling System (ECCS) surveillance documentation to confirm the functionality of the time delay relays during testing. Enclosure 1 provides the NMC response to this request. Enclosure 2 provides copies of the surveillance documentation supporting the request. Enclosure 3 provides residual heat removal system schematics that support the response in Enclosure 1 and the surveillance documenta,l:ion in Enclosure 2.

2807 West County Road 75 Monticello, Minnesota 55362-9637 Telephone: 763.295.5151 Fax: 763.295.1454

USNRC Page 2 This letter makes no new commitments or changes to any existing commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on December 28,2006.

Bradley J. Sawatzke Acting Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC

Enclosures:

(3) cc: Administrator, Regilon Ill, USNRC Project Manager, hflonticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce

ENCLOSURE I ECCS SURVEILLANCE DOCUMENTATION Introduction On November 14,2006, the Nuclear Management Company, LLC (NMC) submitted a license amendment request for the Monticello Nuclear Generating Plant (Reference 1) to request a one-time extension to the quarterly surveillance interval specified in the Technical Specifications (TS) for the Low Pressure Coolant Injection (LPCI) loop select logic functions in Table 3.3.5.1-1 of Specification 3.3.5.1, "Emergency Core Cooling System (ECCS) Instrumentation:"

On December 8, 2006, a t~eleconferencewas held between the U.S. Nuclear Regulatory Commission (NRC) and NMC. The NRC requested Emergency Core Cooling System (ECCS) surveillance documentation to confirm the functionality of the time delay relays during testing. The NRC request is shown in bold and the NMC response is provided immediately thereafter in standard type.

NRC Request for Additional Information (I) Provide relevant documentation from three recent ECCS surveillances showing that the LF'CI loop select time delay relays have been functional.

Please note that the staff found the data referenced in the USAR and no longer needs time ~~equencing information as discussed during the conference call; onlly the ECCS surveillance documentation confirming the functionality of the time delay relay logic is necessary.

The LPCI loop select time delay relays associated with the TS Table 3.3.5.1-1 functions and their contacts are functionally tested in surveillance procedure 0036-02, "ECCS Automatic Initiation Test, Including Loss of Auxiliary Power." This is a comprehensive procedure performed once a cycle during refueling outages (RFO).

Enclosure 2 provides the applicable portions of .the 0036-02 surveillance procedure for the last .three performances. The performances of 0036-02, in reverse order, were on:

Refueling 0036-02 Date Outage Revision April 9, 2005 2005 27 May 20,2003 2003 22 December 8. 2001 2001 21 The LPCl loop select time delay relays were not identified as surveillance requirements in the previous custom TS, and therefore, are not explicitly identified within surveillance procedure 0036-02. A description is provided below of the other relays included in surveillance procedure 0036-02, that require the applicable Page ? of 5

ENCLOSURE I ECCS SURVEILLANCE DOCUMENTATION LPCl loop select time delay relay to be energized, indirectly verifying that the particular LPCl loop select relays functioned during surveillance perforn~ance. provides copies of the following three schematics, to enable the logic to be better understood during review of the surveillance tests in conjunction with the guidance below for verifying functionality for each LPCl loop select time delay relay below.

NX-7905-46-2, Elementary Diagram Residual Heat Removal System, Rev. V NX-7905-46-5, Residual Heat Removal System Schematic Diagram, Rev. U, (Relay Logic Circuit A) e NX-7905-46-9, Residual Heat Removal System Schematic Diagram, Rev. P, (Relay Logic Circuit 8)

A. Reactor Steam Dome Pressure - Time Delay Relay (Break Detection)

(Function 2.k) --- Relays IOA-K34A and 10A-K34B In the surveillance procedure 0036-02 steps referenced below, it is verified that the following relays are in CONDITION B (energized) using Table 1 in the surveillance procedure; 10A-K39A (see schematic NX-7905-46-5) 10A-K39B (see schematic NX-7905-46-9) 0036-02 Revision 27 STEP 82 0036-02 Revision 22 STEP 81 0036-02 Revision 21 STEP 81 Upstream of relay coils 10A-K39A and 10A-K39B are IOA-K37A contacts 1-2 and 10A-K37B contacts 1-2, respectively. These contacts must be made up for IOA-K39A a~nd10A-K39B to energize. Upstream of relay coils 10A-K37A and 10A-K37B are 10A-K34A contacts T I -MI and 10A-K34B contacts T I -MI, respectively. These contacts must be made up for 10A-K37A and 10A-K37B to energize. This is verification that 10A-K34A and 10A-K34B were energized during performance of the surveillance procedure 0036-02 and indicates the functioning of the Reactor Steam Dome Pressure -Time Delay Relays (Function 2.k).

Therefore, surveillance procedure 0036-02 functionally verifies all the used contacts of relays 10A-K34A and 10A-K34B.

In Enclosure 2 each procedure step will be annotated with the letter "A" in the left margin and each relay or set of contacts on the schematics of Enclosure 3 will be boxed with the letter " A next to the box.

Page 2 of 5

ENCLOSURE I ECC13SURVEILLANCE DOCUMENTATION B. Recirculation Pump Differential Pressure - Time Delay Relay (Break Detection) (Function 2.1) --- Relays 10A-K28A and 10A-K28B In the surveillance procedure 0036-02 steps referenced below, it is verified that the following relays are energized; IOA-K30A (see schematic NX-7905-46-5) 10A-K30B (see .schematic NX-7905-46-9) 0036-02 Revision 27 STEP 52.a.3) STEP 52.a.7) 0036-02 Revision 22 STEP 52.a.3) STEP 52.a.7) 0036-02 Revision 21 STEP 52.a.3) STEP 52.a.7) 10A-K88A (see schematic NX-7905-46-5) 10A-K88B (see schematic NX-7905-46-9) 10A-K88A 10A-K88B 0036-02 Revision 27 STEP 52.a.4) STEP 52.a.8) 0036-02 Revision 22 STEP 52.a.4) STEP 52.a.8) 0036-02 Revision 21 STEP 52.a.4) STEP 52.a.8)

Upstream of relay coils 10A-K30A and 10A-K30B are 10A-K28A contacts 2-6 and 10A-K28B contacts 2-6, respectively. These contacts must be made up for I OA-K30A and 10A-K30B to energize.

Upstream of relay coils IOA-K88A and 1OA-K88B are 10A-K28A contacts 1-5 and 10A-K28B contacts 1-5, respectively. These contacfs must be made up for 10A-K88A and 10A-K88B to energize.

This is verification that 10A-K28A and 10A-K28B were energized during performance of the surveillance procedure 0036-02 and indicates the functioning of the Recirculation Pump Differential Pressure -Time Delay Relays (Function 2.1).

Therefore, surveillance procedure 0036-02 functionally verifies all used contacts of relays 10A-K28A and 10A-K28B.

In Enclosure 2 each procedure step will be annotated with the letter "B" in the left margin and each relay or set of contacts on the schematics of Enclosure 3 will be boxed with the letter "B" next to the box.

Page 3 of 5

ENCLOSURE 1 ECCS SURVEILLANCE DOCUMENTATION C. Recirculation Rliser Differential Pressure - Time Delay Relay (Break Detection) (Function 2.m) --- Relays 10A-K4OA and 1OA-K40B In the surveillance procedure 0036-02 steps referenced below, it is verified that the following relays are in CONDITION A (energized) using Table 1 in the surveillance procedure; 10A-K43A (see schematic NX-7905-46-5) 10A-K43B (see schematic NX-7905-46-9) 0036-02 Revision 27 STEP 49 0036-02 Revision 22 STEP 49 0036-02 Revision 21 STEP 49 Upstream of relay coils 10A-K43A and 10A-K43B are 10A-K40A contacts T I - M I and 10A-K40B contacts T I - M I , respectively. These contacts must be made up for 10A-K43A and 10A-K43B to energize. This is verification that 1OA-K40A and 'I OA-K40B were energized during performance of the surveillance procedure 0036-02 and indicates the functioning of the Recirculation Riser Differential Pressure - Time Delay Relays (Function 2.m).

Therefore, surveillance procedure 0036-02 functionally verifies the contacts of relays 1OA-K40A and 10A-K40B. Note, that the Recirculation Riser Differential Pressure - Time Delay Relays also have normally closed contacts to ensure that once a LPCl loop is selected it remains selected.

In Enclosure 2 each procedure step will be annotated with the letter "C" in the left margin and each relay or set of contacts on the schematics of Enclosure 3 will be boxed with the letter "C" next to the box.

Page 4 of 5

ENCLOSURE l ECCS SURVEILLANCE DOCUMENTATION REFERENCE

1. NMC letter to U.S. NRC, "License Amendment Request: One-Time Low Pressure Coolant Injection Loop Select Logic Time Delay Relay Surveillance Interval Extension," (L-MT-06-071), dated November 14, 2006.

Page 5 of 5

ENCLOSURE 2 COPIES OF SURVEILLANCE DOCUMENTATION FOR THE LAST THREE PERFORMANCES OF SURVEILLANCE PROCEDURE 0036-02 ECCS AUTOMATIC lNlTlATlON TEST, INCLUDING LOSS OF AUXILIARY POWER (18 Pages Follow)

0038-02 ESCS !JNDE3VGLTAGZ FUhCTIGNAL-EST J

0039-02 ECCS LOSS OF .AUXILIARY ?WE??S~JNC'IGNAL -?ST J' .

OC93 CORE SFCiXf SYSTEM SiMCUTEZ AU7rJMfiT,?IC 4CTLAiI 5-03 LFCl SYSTEM SlMULnTEG AGCMA7iT:C ACTLlr1T:2N 2111-31 HPCl SvSTEM SLMLJLJ~TED AUTJMATIC ACTUATION.^

15171-02 hFCI S'fSTElrl AUTC RESTART AFTER +IGb 'WATER 01: 3-01 435 SYSTEM SIML'L4TEC AUTOMATIC ACTUATION 0:17-01 RClC SYSTEM SlklULATED AUTOMATIC ACTUATION 01!7-C2 FClC SYSTEM ACT3 qESTAFiT AFTER HIGH WATER LEVEL TRIP 518s-93 STANDBY DIESEL GENERATO3 SiMULATED AUTOMATIC ACTgATiGN .AN@ [.CADIN r

(LOADING TEST CNLW 0452 ADS INHIBIT SWITCH TEST J' REVIEW AND APPROVALS OC Review Req'd: YES OC Results Review Req'd: NO Date: -1 1108j78

~ ~ ~ ; o By:

v e d &- 3 . A-

,Date: 1 1- 3 0-94 7'

/ REVIEW AND A P P ~ V A OF L ACTIVITIES 1 DATE 1 1 Completion 1 Shiff S u ~ v : _/I I OC R ~ s u l t sReviewed at Meeting Number: &A COMMENTS 3 W o r k G p t a j - Op;r, EVI? - aI -C =.

Infrequent Tsst or Evolu~ionsee 4 AWI-04.05.07 (PROCEDURE IMPLEMENTATION}.

&&d 5 ~ 706,

~ 7/0 5 &, $38& f-2 P 5

- 8 x/ 0 5 0.50- CQ$&S~S~L f/$5 G m o Choqqe fa h p p ~ ~ d , 5~4' ~l ~17-29 5 & / neLj H PC I RCfc t o q i ~ l i a q 3 y-6-0j WO(S) ISSUED YES- NO - NUMBER(S)

'3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: -- ,wY - 74 a41 Resc Supv: EB1 c EBI

/ ~ s r oRsf: I - b ~Y :

ARMS: C036-02 ) Doc Type: 4020 1 Admin In~tials: \'$1

STEP 4.8 Verify the following:

a. MO-2013, LPCl INJECTION OUTBOARD, is OPEN.

b. MO-2015, LPCl lNJECTlON INBOARD, is OPEN and remains open when associated handswitch is placed in CLOSE.

c. MO-2012, LPCl INJECTION-OUTBOARD, is CLOSED.

d. MO-2014, LPCl INJECTION-INBOARD, is CLOSED.

& STEP 49 Verify relay status in Table 1, CONDITION A.

STEP 50 Place control switches for the following Drywell fans to the OFF position (Panel C-25):

a. V-RF-1, OW COOLING RECIRC FAN I

b. V-RF-2,DW COOLING RECIRC FAN 2 C. V-RF-3,OW COOLING REClRC FAN 3

d. V-RF-4, DW COOLING RECIRC FAN 4 STEP 51 Perform the following:

a. Verify the following relays are de-energized (Panel C-32):

(b.) At PLC-2-184-180, Slot 7 move input switch A1 to the left to restore the feedwater flow interlock with 12 Recirc MG (Panel C-18). Ttf (c.) Apply 520 psig to PS-2-3-52A (instrument rack C-56). /Id /

(d.) Raise STABLE CURRENT ADJUST potentiometer to LIS-2-3-672A and LIS-2-3-672C (Panel C-303A, Cable Spread) until LLWL trip is RESET on each instrument (center knobs to remain engaged). kJ /

PART A

LPCl LOOPSelect Logic STEP 52 Perform the following:

a. Verify the following relays are energized:

1) 23A-K23 (Panel C-39)

2) 1OA-K33A (Panel C-32) 5 4) 1OA-K88A (Panel (3-32)

5) 1OA-K9OA (Panel C-32)

6) 1O A - ~ 3 3 (Panel 5 C-33)

E5 7) 1OA-K30B (Panel C-33) l3 8) 1OA-K88B (Panel C-33)

9) 1OA-KSOB (Panel C-33)

b. Verify the following status lights are off:

1) RHR DlVlSlON I - CONTAINMENT SPRAY PERM ISSlVE INTLK "RESET" (Panel C-03).

2) RHR DIVISION I - LPCl LOOP SELECT LOGIC "RESET" (Panel C-03).

3) RHR DIVISION If - CONTAINMENT SPRAY PERM ISSIVE INTLK "RESET" (Panel (2-03).

4) RHR DIVISION II - LPCl LOOP SELECT LOGIC "RESET" Panel C-03).

5) HPCI - INITIATION RESET (Panel C-03).

STEP 53 Perform the following:

a. Monientarily depress the following for the RHR and HPCI systems (Panel C-03),

AND verifjr the associated status lights are on:

1) HPCI - INITIATION RESET

2) RHR DIVISION f - CONTAINMENT SPRAY PERM ISSlVE INTLK RESET

-PART

- A

MONTICEFFONUCLEAIR GENERATJNGPUNT- I

.- TITLE: I ECCS AUTOMATlC lNUIAT10N TEST, I Revisio

.@ 2 LOSS OF AUXlLlARY POWER -1 STEP T7 Verify the following:

a. Relay 14A-K13A is de-energized (Panel C-32).

b. Refay 10A-K44A is de-energized (Panel C-32).

c. Relay 14A-K138 is de-energized (Pane/ C-33).

d. Relay I OA-K44B is de-eneroized (Panel C-3.3).

'STEPf 8 Verify MO-4085A, RHR DISCHARGE EQUALIZING VALVE, is CLOSEO.

STEP 79 Verify MO-40856,RHR DISCHARGE EQUALIZING VALVE, is CLOSEO.

(STEP $0) Simulate low reactor pressure by releasing pressure on PS-2-3-52A below trip point, ~ 4 7 psi 0 (Panel C-56).

STEP 81 Verify the following:

a. MO-2012, LPCl INJECTION-OUTBOARD. is OPEN.

b. ifAO-2014, LPCl INJECTION-INBOARD, is OPEN and remains open when its associated bandswitch is placed in C:LOSE.

c. MO-2013,LPCl tNJECTlON OUTBOARD, is CLOSED.

d. MO-2015, LPCl INJECTION INBOARD, is CLOSED.

c?.. ,411 RI-I\? C o c a 5 p r ~ yPk.-?? G-GZ , P T L .

i Verify relay status in Table 1, CONDITION B.

(STEP83) Apply 2 9 2 0 psig to PS-2-3-52A {instrument rack C-56).

Perform the fol!owing:

(a.) Raise STABLE CURRENT ADJUST potentiometer to L3S-2-3-6728and LIS-2-3-6720, (Panel C-3038,EFT 3rd Floor) until LLWL is RESET (center knobs to remain engaged).

(b.) Reduce pressure on DPIS-2-1298 and DPIS-2-129Dto reset.

c. Verify relays 10A-K358 and 10A-K36B are de-energized (Panel C-33).

Table 1 Page 1 of 2

Table 1 (Cont'd)

Page 2 of 2

~003&02ECCS UNDERVOLTAGEFUNCllONMTESF

/003402 ECCS LOSS OFAUXltlARY PONER NNCTIONAL TEST CORE SPRAY SYSTEM SIMWTEU AUTOMATIC ACTUATION 3 0 3 LPCf SYSTEM SIMUIATEDAWOMAnCACNAtlON Joitrai HPCISYSTEM SIUWTEU ALTOMATIC ACTUAT~ON

/0111-02 HPCl SYSTEM AUTO RESTART Amft HlGH WATER LEVEL TRIP

/Of1341 ADS SYSTEM SIMULATED AUTCMATIC ACTUATION

/aii7ul R ~ SYSTEM C SIM~TEO wwnc ACTUATION 4 011742 RClC SYSTEMM O RESrAQIT A F E R HlGH WATER L W L TRIP

/018443 STANDBY DIESEL GENERATOR SI ED AUTOMATIC ACrUATlON AND LOADING (LOADING TEST ONLY)

/6051! AOSIWBFFSWrrCHTEST

-CUMMEWS

--InfrequentTest or Evolution see 4 AN-04.05.07 (PROCEDURE IMPLEMENTATION).

STEP 48 Verify the following:

A

a. MO-2013, LPG! lNJECTlON OUTBOARD, is OPEN. 6

b. MO-2015, LPCl INJECTlON INBOARD. is OPEN and remains open when associated handswitch is placed in CLOSE.

n C.

d.

MO-2012, LPC1 INJECTION-OWBOARD, is CLOSED.

MO-2014, LPCl INJECTION-INBOARD, is CLOSED.

A&=-

!EL

/^r

.- STEP 49 Verify relay sfatus in Table I, CONDITION A.

STEP 50 Place control witches for the following Drywell fans to the OFF position (Panel C25):

a. V-RF-I, DW COOLING RECIRC FAN 1

b. V-RF-2, DW COOLING RECIRC FAN 2 C. V-RF-3, DW COOLING REClRG FAN 3

d. V-RF-4, DW COOLING RECf RC FAN 4 &

STEP 51 Perform the following:

a. Verify the following relays are de-energized (Panel C-32):

(5.)' At PLC-2-184-180, Slot 7 move input switch A1 to the left to restore the feedwater flow interlock with 12 Recirc MG (Panel C-18).

(c) Apply 520 p i g lo PS-2-3-52A (instrument rack C-56). (

(d.) Raise STABLE CURRENT ADJUST potentiometer to LIS-2-3-672A and US-2-3-672C (Panel C-303A, Cable Spread) until LLWL trip is RESET on each instrument (center knobs to remain engaged).

WD Select Lwic STEP 52 Perform the following:

a Verify the following relays are energized:

1) 23A-K23 (Panel C-39)

2) 10A-K33A (Panel (3-32)

Y-?

b 3) 1OA-W0A (Panel C32) 3 4) 10A-KBBA (Panel C-32)

5) 10A-K9OA (Panel C-32)

6) 1OA-K338 (Panel C-33)

R 7) 10A-K308 (Panel C-33)

J? 8) 1OA-KBBB (Panel 12-33]

9) 10A-Kg08 (Panel C-33)

b. Verii the following status lights are off:

1) -

RHR DIVlSlON 1 CONTAINMENT SPRAY PERMISSIVE I M I K "RESET" (Panel (2-03).

2)

"RESET (Panel C-03).

RHR DlVlSION I LPCl LOOP SELECT LOGIC L-

3) RHR DIVISION II -CONTAINMENT SPFi4Y PERMISSIVE INTLK'RESR" (Panel C-03).

RH8 DIVISION I1 - LPCi LOOP SELECT LOGIC 4)

"RESET P a e l C-03). d HPCI - IP!ITIATlON RESET (Panel C-03). 9

!a STEP 53 5)

Perform the following:

a. Momentarily depress the following for the RHR and HPCl systems (Panel C-03).

M v e r i i f y the associated status lights are on:

1) -

HPCl INlTlATlON RESET -3

2) RHR DIVISION I - CONTAINMENT SPRAY PERMlSSlVE INflK RESET -

STEP 80 Verify the fdlowing:

a. MO-2018. LPCl INJECTION-OUTBOARD, is OPEN, fl

+

b. MO-2014. LPCl INJECTlON-INBOARD.i a sOPEN and remains &en when its associated handswitch is placed in CLOSE.

c. MO-2013, LPCl INJECTION OUTBOARD, Is CLOSED.

d, MO-2015. LPCf INJECTION INBOARD, is CLOSED.

-A STEP 81 Verify relay status in Table I,CONDITION 8. 7 (STEP82)

STEP 83 Apply 2520 p i g to PS2-3-5% (instrument rack (2-56).

Petform the follawing:

d '6 (a.) Raise STABLE CURRENT ADJUST ptentiorneter to US-2-36726 and US-2-3-672D, (Panel C-3038,EFT 3rd Floor) until LLWL is RESET (center knobs tg remain engagM1.

(b.) Reduce pressure on DPtS-2-1298 and DPIS-2-1290 to reset.

c. Veniy relays 1OA-K35B and 1OASK36Bare deenergized (Panel C-33).

STEP 84 Perform the following:

a. Verify the following relays are energized (Panel C-32):

b. Boot Contact 10A-K37A, 1-2 (Panel C-32) \

Boot No. 33 Installed By:

Independently Verified By:

Table 1 Page Iof 2

Table 1 (Gont'd)

Page 2 of 2

'0036.02 ECCS UNDERVOLTAGE FUNCTIONAL TEST f ~ 3 9 . 0 2ECCS LOSS OF AUXILIARY POWER FUNCTIONAL TEST 40093 CORE SPRAY SYSTEM SIMULATED AUTOMATIC ACTUAT!ON 0103 LPCl SYSTEM SIMULATE0 AUTOMATIC ACTUATION

/0111-01 HPCl SYSTEM SIMULATED AUTOlAATIC ACTUATION J0111-02 HPCI SYSTEM A?ITO RESTART AFTER HIGH WATER LEVEL TRIP

.bfAsTE ri

/Of 13.01 ADS SYSTEM SIMULATED AUTOMATIC ACTUATION

' 0117-01 RClC SYSTEM SIMULATED AUTOMATIC ACTUATION 10117-02 RClC SYSTEM AUTO RESTART AFTER HIGH WATER iEVEL TRIP J 0189.03 STANDBY DIESEL GENERATOR SIMULATED AUTOMATlCACNATlONAND LOADING (LQAOINGTEST ONCI]

A J 0452 ADS INHIBIT SWITCH TEST COMMENT'S 72, Infrequent Test or Evolution see 4 AW1-04.05.07 (PROCEDURE IMPLEMENTATION).

@& WA* P AtWa n 3 3 ~3 1 3 r m

' 3d.5 iGF/2-5&'

C-1 C-0 I

rib. fEO +, Ir i n =+(\wtad- .I Y. i b. Y j h

• W/

.J/&

WO(S) ISSUED YES- NO NUMBER(S)

STEP 43 Attempt !o close MO-1752, GS INJECTION OUTBOARD, Ab2J verify valve remains open.

STEP 44 Perform the following:

a. Place 74A-Si6B, MO-1752, CS INJECTION BYPASS keyswitch to BYPASS (Panel C-03).

b. Verify annunciator 3-6-33 (CORE SPRAY ISOL ViV 1752 BYPASS) alarms.

STEP 45 CLOSE MO-1752, CS INJECTION OUTBOARD.

STEP 46 Attempt to open MO-1752, CS INJECTIONOUTBOARD, ANL)verify it does not operate.

STEP 47 PIace MO-1752, CS INJECTION BYPASS keyswitch i14A-St681 to AUTO (Panel C-03). ,.

&Dverlfy'M0-1752 I$ OPEN.

STEP 418 Verify the following:

a. MO-2013, LPCl INJECTION OUTBOARD, is OPEN.

b. MO-2M5, LPCI INJECTlON INBOARD, is OPEN and remains open when associated handswitch is placed in CLOSE.

c. MO-2012,LPCi INJECTION-OUTBOARD,is CLOSED.

d. MO-2014, LPCI INJECTION-INBOARD, is CLOSED.

& STEP 49 Verify rehy status in Tabfe 1, CONDITION A.

STEP 50 Place control switches for the following Drywellfans to the OFF position (Panel C-25):

a. V-RF-I , DW COOLING RECIRC FAN 1

b. V-RF-2, DW COOLING RECIRC FAN 2 C. V-RF-3, DW COOLING REClRC FAN 3

d. V-RF-4, DW COOLING RECIRC FAN 4 STEP 51 Perform the following:

a. VerifL the following relays are de-energized (Panel C-32):

PART A 3\

k. Boot the following contacts in Panel C-30:

1) -

13A-K1,3-4 prevents auto opening oi MO-2096 during Mure low low level signals.

Boot No. 3 Independently Verified By:

2) -

13A-KI, 9-10 prevents auto opening of MO-2078 during future low low level signah.

Boot No. 1 s

Independently Verified By:

LPCl LOODSelect Lo&

STEP 52 Perform the following:

a. Veriv the following relays are energized:

1) 23A-K23 (Panel C-39)

2) 10A-K33A (Panel C-32) f?>- 3) 10A-K3DA (Panel C-32) 6 4) 10A-K88A (Panel '2-32)

5) 1OA-K9OA (Panel (2-32)

6) IOA-K33B (Panel C-33) A&-

-% 7) 10A-K3OB (Panel (2-33) 2%

R% 8) 1OA-K88B (Panel (2-33)

9) 10A-K90B (Panel (2-33)

b. Verify the following status lights are off:

1) RHR DlVlSlON I - CONTAINMENT SPRAY PERMISSIVE INTLK 'RESET (Pane! C-03).

2) RHR DIVIS1ON i LPG1 LOOP SELECT LOGIC "RESET" (Panel C-03). &

PART A 55

i STEP 76 Verify the fdiowing:

a. Relay 14A-K13A is de-energized (Panel C-32). /r,

b. Relay .IOA-K44A is de-energized (Panel C-32). /c

c. Relay 14A-K13B is de-energized (Panel (3-33). L'

d. Relay 11 OA-K14B is de-energi~ed(Panel C-33). 4.-

STEP 77 Verrfy MO-4085A, RHR DISCHARGE EQUALIZING VALVE, is CLOSED. /L STEP 78 Verify M0-40858,RHR DISCHARGE EQUAtlZiNG VALVE, is CLOSED. 4 (STEP 79) Simulate IOWP reactor pressuro by releasing pressure on PS-2-3-52A below trip point, s K 0 psi (Panel C-56).

STEP 80 Verify the following:

a. MO-2012,LPG1 INJECTION-OUTBOARD, is OPEN. 7' .-

b. MO-2014, LPCl INJECTION-INBOARD, is OPEN and remains open when its associated handswitch is placed in CLOSE.

4-

c. MO-2013, PC1 INJECTION OUTBOARD, is CMSED. 4 p

I STEP 131 (STEP82)

d. MO-2015, LPCl INJECTION INBOARD, is CLOSED.

Verify relay status in Table 1, CONDITION 6.

Apply 2520 psig to PS-2-3-529 (inslrurnsnt rack C-56).

k STEP 83 Perform fhe following:

(a.) Raise STABLE CURRENTADJUST potentiometer to 1-1 8-2-3-6728 and US-2-3-672D, (Panel C303%,EFT 3rd Floor) until LLWL is RESET (center knobs to remain engagedl).

(b.) Reduce pressure on DPIS-2-1298 and DPIS-2-1290 to reset-

c. Verify relays I OA-K35B and 10A-K36B are de-energized (Panel C-33). .

Ificc PART A Sa

Table 1 Page 1 of2

Table 1 (Cont'd)

Page 2 of 2

ENCLOSURE 3 COPIES OF RESIDUAL HEAT REMOVAL SYSTEM SCHEMATICS (3 Pages Follow)

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