Text

Forwards Response to NRC Concerns Re Util 860516 10CFR50.48 & App R Exemption requests.W/12 Oversize Drawings
	ML20213G684
Person / Time
Site:	Hatch
Issue date:	09/23/1986
From:	Gucwa L, Gucwz L; GEORGIA POWER CO.
To:	Muller D; Office of Nuclear Reactor Regulation
Shared Package
ML20213G681	List: ML20213G680; ML20213G684; ML20265A774; ML20265A780; ML20265A791; ML20265A796; ML20265A801; ML20265A806; ML20265A810; ML20265A816; ML20265A821; ML20265A826; ML20265A832; ML20265A837;
References
	0749C, 749C, SL-1283, TAC-61626, TAC-61627, NUDOCS 8611180264
	Download: ML20213G684 (50)
	v • d • e

r Georgia Fbwer Company 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526-6526 Mailing Address:

Post O' hee Box 4545 Atlanta. Georgia 30302 Georgia Power f/vi wattim eW Inc cycem L. T. G ucwa Mar.ager Nuclear Safety and ucensing SL-1283 0749C September 23, 1986 Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1 AND 2 ADDITIONAL INFORMATION RELATED TO APPENDIX R EXEMPTIONS Gentlemen:

The enclosed information is submitted in response to your informal requests for additional information relative to Georgia Power Company's Appendix R Exemption Request, dated May 16, 1986.

If you have additional questions in this regard, please contact this office at any time.

Sincerely, cyd'7"egt m L. T. Gucwa JDH/ac c: Georgia Power Company U.S. Nuclear Regulatory Commission Mr. J. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr. Mr. P. Holmes-Ray, Senior Resident Mr. H. C. Nix, Jr. Inspector-Hatch G0-NORMS 004 k g i*

8611180264 861114 1 (g DR ADOCK 0500 (o

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ENCLOSURE TO GPC LETTER SL-1283 RESPONSE TO NRC CONCERNS RELATIVE TO GEORGIA POWER COMPANY SUBMITTAL RELATED TO EDWIN I. HATCH NUCLEAR PLANT UNITS 1 AND 2 10 CFR 50.48 AND APPENDIX R EXEMPTION REQUESTS DATED MAY 16, 1986 Ouestion 1:

Section 1.1 (1) In accordance with Generic Letter 86-10 the 1.1.2.1 - 1.1.2.6 requested relief from the 3-hour barrier requirement is not an exemption. However, the licensee must perform an evaluation on all fire boundaries in its plant and retain these evaluations for NRC audit.

Response 1:

Evaluations and justifications will be available for audit.

_0ues_t_i_on 2:

Section 1.2 (2) Will the reroute or 1-hour barrier protection of the pathway 2 circuits be accomplished by the end of this outage?

Response 2:

All work needed to protect or reroute the required circuits, with one exception, is scheduled to be complete prior to the Appendix R completion date of November 30, 1986.

The circuit identified as needing protection is associated with the control power transfer switch which is scheduled for installation in Diesel Building Switchgear Room 1F after November 30, 1986. (Refer to Section 2.2 of the May 16, 1986, exemption request letter.) This circuit will not be rerouted or wrapped. The control power transfer switch will provide the protection needed.

Question 3:

Section 1.2 (3) What is the arrangement of the combustible cable insulation in relation to the pathway 2 I

circuits?

i 0745C E-1 09/10/86

I ENCLOSURE TO GPC LETTER SL-1283 (Continued)

APPENDIX R EXEMPTION REQUEST Response 3:

The raceways located in Fire Areas 1408 and 1412, which are required to be wrapped, are highlighted on the enclosed preliminary drawings:

H-40144, Rev.1 H-40152, Rev.1 H-40145, Rev.1 H-40154, Rev.1 As shown in the drawings, the following circuits:

PUED41002-B RTED09C01-B R22-S006-ESB-C09-B PUED41C05-B RTED09C03-B R22-S006-ESB-Cll-B RTED01C07-8 RTED16C02-B R22-S006-ES7-C05-2 RTED01E01-B RTED16C04-B R22-S027-ESB-C53A-B RTED05C01-B R22-S006-ESB-C08-B R22-S027-ESB-C53B-B in raceways:

2ESB168-B PB1 7 TB1-673-8 ESA-6-B 2ESB167-B ESS-II-249-B TB1-629-8 ESA-108-B ESS-I-62-B ESS-II-380-B PB1-18 TLA7-13-B ESB-156-B generally _ run in a north-south direction through a congested area, across and beside numerous other circuits. Although many of the circuits in close proximity to the required circuits are contained in metal enclosures (conduit, walker duct, etc.), exposed cables may also be located near the required cables.

J 4 These two exemption requests are similar to the exemption already granted in Section 10.0 of the April 18, 1984, Safety Evaluation Report.

,0uestion 4:

l Section 1.3 (4) How are the outside security lights powered?

Can the security lights be readily switched on to the emergency diesel generators?

Response 4:

As discussed in our August 27th telephone conversation, portable lighting, other than flashlights, is available, if necessary, to allow the operators

to traverse between buildings and to perform any necessary manual actions

in the yard area. Additional details related to this security safeguards lighting can be provided, if required. It is GPC's position that only i minimal lighting is necessary to traverse between buildings and to close the valve in the plant service water valve pits. Therefore, any additional lighting, other than that normally available during a LOSP, probably will not be needed.

I 0745C E-2 09/10/86 L >

r '

ENCLOSURE TO GPC LETTER SL-1283 (Continued)

APPENDIX R EXEMPTION REQUEST Ouestion 5:

Section 1.4 (5) State that all of the equipment located within the water curtain zone will not be damaged by continuous exposure to the water spray.

Response 5:

For those components required to remain operable in the water spray, spray protection is provided where needed, and exposure to the water spray will not render the equipment inoperable.

_0_ue_stion 6:

Section 1.4.1.1.1 (6) Are any combustibles located within 20 feet of the RHR valves Ell-F015A and E11-F017A?

Response 6:

Valves Ell-F015A and Ell-F0017A are located within the piping penetration room. Combustibles consisting of cable insulation are located within 20 ft of the subject valves. A conservative estimate of the fire loading located within 20 ft of these valves is approximately 69,000 BTU /ft 2, which is equivalent to a 0.83-hour fire. Valves E11-F015A and E11-F017A are located totally within the water curtain zone and an area-wide fire detection system.

Because of the low fire loading, the protected circuits should not be damaged, and the suppression system should contain and suppress any fire that would develop in the area of the subject valves.

_0_ues_ tion 7:

Section 1.4.1.1.7 (7) The last paragraph of this exemption request is unclear. Please describe in more detail the location of the shutdown panel relative to the water curtain and the significance of extending the curtain 5 feet north of the panel.

Response 7:

As explained in our July 1,1982 submittal, " Response to 10 CFR 50.48 and Appendix R," page 4-17, and in Section 4.2.1 of the April 18, 1984, Safety Evaluation Report, GPC comitted to install an automatic sprinkler system to protect against the spread of fire from one hal f of the Reactor Building to the other where there was no physical barrier. We proposed 0745C E-1 09/10/86

F ENCLOSURE TO GPC LETTER SL-1283 (Continued)

APPENDIX R EXEMPTION REQUEST that the sprinkler system extend from the east-west centerline of the Reactor Building into each fire area a minimum distance of 10 ft, or to a distance of 20 ft beyond the last redundant opposite train component, whichever is greater.

Panel 2H21-P173 contains a control cable for a pathway 2 component and is located on the side of the Reactor Building where pathway 2 is used for shutdown. Therefore, to meet the proposed separation criteria by locating a sprinkler system within this area, the system should extend 20 ft beyond panel 2H21 -Pl 73, or 5 to 10 ft beyond its present_ actual location.

However, the steam chase, shown as Zone 2205H-on the Fire Hazards Analysis drawings, provides a substantial, but unrated, physical barrier between the Reactor Building halves in this area. Therefore, the sprinkler system is not necessary to separate the Reactor Building halves.

The primary purpose of this particular sprinkler zone is to protect the remote shutdown panels. This sprinkler zone would not be required to meet the water curtain criteria because of the physical separation provided by the steam chase.

There are no required active components contained in panel 2H21-Pl73, and the loss of the control cable can be compensated for by a manual operator action. Therefore, extending the sprinkler system north to a distance of 20 ft beyond the panel would not materially enhance fire protection safety in this area.

In order to adequately document these statements, the following exception to a GPC commitment is also requested.

Requested Exception:

An exception to the water curtain separation criteria stated in Section

4. 2.1 of the April 18, 1984, Safety Evaluation Report is requested.

Specifically, GPC requests that the water curtain criteria be revised to extend only beyond remote shutdown panel 2H21-P173.

Justification:

Physical separation of the Reactor Building halves is provided in this l zone by the steam chase (designated as Fire Zone 2205H). The substantial ,

l but unrated, reinforced concrete walls of the steam chase should provide adequate separation of the Reactor Building for a fire occurring on the i

west side. The circuit located in panel 2H21-Pl73 should be adequately protected by the existing suppression system located between column lines R15 and R18 and the area-wide fire detection system.

The detection and suppression provided inside remote shutdown panel 2C82-P001, and the physical protection provided by the panels themselves should prevent a fire occurring in either panel (2C82-P001 or 2H21-Pl73) 0745C E-4 09/10/86

ENCLOSURE TO GPC LETTER SL-1283 (Continued)

APPENDIX R EXEMPTION REQUEST from damaging the other panel. The sprinkler system located at ceiling level should prevent a fire occurring outside the vicinity of these panels from damaging either of the remote shutdown panels.

Therefore, it is GPC's position that extending the existing sprinkler system north to a distance of 20 ft beyond panel 2H21-P173 would not materially enhance fire protection safety in this area.

Question 8:

Section 1.4.1.1.15 (8) The exemption request is not clear.

Figure 25 of the FHA indicates that MCC 2R24-S018B is already within the water curtain.

Response 8:

Motor Control Center 2R24-S018B is already located within the water curtain, but because of the proposed water curtain separation of the Reactor Building, as explained in our response to Question 7, the water curtain criteria is not strictly met for this component. In this case, the extending of the sprinkler system a distance of 20 ft north of the subject MCC is not possible. This is because of the open hatchway located in the ceiling imediately north of the subject MCC, as shown on the enclosed sketch, 8-1. Because of this open hatchway, the fixed combustible loading in the location of the hatch is essentially zero, and transient combustibles are administrative 1y controlled.

The spray protection provided to MCC 2R24-S0188 consists of two spray nozzles located approximately 2 ft above the MCC. The location of these heads will ensure that a fire occurring in the MCC will not spread, and a fire occurring outside the MCC should not damage it. The specific suppression system arrangement for this panel is shown on enclosed sketches SM83-248-105 and SM83-248-106.

As in our response to Question 7, GPC would like to request an exception I

to the water curtain separation criteria.

Requested Exception:

An exception to the water curtain separation criteria stated in Section 4.2.1 of the April 18, 1984, Safety Evaluation Report is requested. This exception is requested to the extent that the water curtain criteria used to separate the Reactor Building halves must only extend beyond MCC 2R24-S018B, thus exempting the 20-ft criteria in this case.

0745C E-5 09/10/86 l ;

ENCLOSURE TO GPC LETTER SL-1283 (Continued)

APPENDIX R EXEMPTION REQUEST Justification:

Motor Control Center 2R24-S018B is located against the reinforced concrete wall on the north side of the piping penetration room. The north and south halves of the Reactor Building are separated by a suppression system which is approximately 55 ft wide at this point. However, the suppression system only extends approximately 6 ft north and 21/2 ft west beyond MCC 2R24-S0188. The MCC contains a pathway 2 motor starter and is located on the side of the Reactor Building where pathway 2 would be used for shutdown.

The suppression system cannot be extended t. distance of 20 ft north of MCC 2R24-S018B due to an open hatchway in the ceiling immediately north of the NCC. The MCC is protected by the water curtain system and the area-wide early warning fire detection system. The Reactor Building separation is provided by a suppression system which is approximately 55 ft wide.

Extension of the suppression system to a distance 20 ft beyond the MCC would not materially enhance the separation of the Reactor Building and is not practical because of the open hatchway. Protection of the cables and the motor starter contained within the MCC is provided by: (1) the suppression system located above the MCC, (2) the metal enclosure of the MCC itself, and (3) the area-wide fire detection system.

Question 9:

Section 2.1 (9) Provide a drawing clearly showing the location and height above floor level of the automatic fire suppression system and detection system (if any) in the intake structure. Describe any significant deviations from applicable NFPA codes.

I Response 9:

! Enclosed drawing H-11847, Rev. D shows the location of the smoke detectors l located within the Intake Structure. These detectors are located at l ceiling level.

Enclosed drawings H-ll321, Rev. 5; S-50509, Rev. 7; and S-50510, Rev. 4, l along with the enclosed sketch, show the location of the automatic fire I

suppression system. Each pump motor has two spray nozzles rated at 135'F, with 65* deflectors placed at 35* angles. This arrangement provides full sprinkler coverage of the fire hazard, which is the pump motor.

l The NFPA Code deviations, as described in Chapter 5 of our " Response to 10 CFR 50.48 and Appendix R" and in Appendix H of the FHA, all apply to ,

the Intake Structure. Within the Intake Structure, there are no significant deviations from the applicable NFPA codes.

I 0745C E-6 09/10/86

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7 ENCLOSURE TO GPC trTTER SL-1283 ~(Continued)

APPENDIXR;EJEMPTIONREQUEST Question 10: '

, ~

Section 2.2 (10) Provide a drawing clearly showirig the layout of automatic fire sppresion and detection systems in the Tu(bine Building and east

~ cableway Unit 2.

Response 10: ,

Enclosed drawings M-ll821, Rev. E; a SM-004-020-010, Rev. B; S-60012,

- Rev. 7, and S-60313,' Rey. 6. indici.te the layout of the automatic fire suppression and detection systems >in the Turbine Builcing and the East Cableway for Unit 2. m

~

Ouestion ll: -

Section 1.7 :(ll-) What are~ the estimated times requiredasto perform the Manual Operator .' Actions (M0As)?

- / - Also, how long after'the plant scram will it ,

be before these M0As must be perforced?

Response ll: " '

i Section 1.7 of our May 16, 1986, submittal dis' cusses the fol16 wing types .-f <

of MOAS which entail opening links and installing jumpers: '

- RHR pump room cooler T

- RCIC pump room cooler -

4

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l - Diesel-generator voltage regnistor (one for each die::el-generator) s

- Diesel-generator local ammeters (one for each dieschgenerator) ,

f The time required to perform the (101s is:

' 20 minutes f om the, time the Plant ctquipment Operator (PE0) is notified until the cooler is in operation

- 20 minutes from the . time 'the PE0 is notified until the cooler is in V

operation' ,

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- 15 minutes from the time the PE0 is notified until the N0A is

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comp 1ete_ ,

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- 10 minutes from the time \the PE0 is notified until the MOA is compl6te n J

0745C E1 04/10/86 -

.- . . - =__ -.

m i

ENCLOSURE TO GPC LETTER SL-1283 (Continued)

APPENDIX R EXEl@ TION REQUES,T, The diesel-generator M0As must be performed on each diesel-generator required for operation; however, only one diesel-generator is needed per unit for hot shutdown.

The time following shutdown when the M0As must be performed is:

- 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following a scram, after the RHR pumps are started.

- (See Section 1.7.1.2. ) 40 minutes following a reactor scram. RCIC is needed within 10 minutes of a scram. RCIC coolers are needed within 30 minutes of starting RCIC. This is a very conservative calculation. Work is in progress because of the proposed station blackout rule to either provide de-powered room coolers or to justify no cooling for a period of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3

- 30 minutes following a reactor scram.(a)

- 30 minutes following a reactor scram.(a) i t

j a. The limiting factor for needing the diesel-generators is the RCIC room coolers.

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9 LOCATION : Path 45. Unit 2/E-3 IT47-eOOe64 19W 89.A 2 2 ue acscT cmAT moos rea w rouowcrua. - ,

n n-6 *SA4 n n-ooosen Purpose of Jumper: Start DW Coolers 64 Af sacc et24-SdEZ. AT LOCAfsose -

Doaseto2.96TAtt TW rCLLouvC \

.AArptse . .

[g TM__ 70___ Tf"RWAL ff47-6007'A-2 ssM TT47-60078-2 ret _ '_ mA2 m *

. EUMj ' . J,~_ .

l Required Tools: I ue ac:rf emn eacuois ran Tic

' n%"' .','***

I i

""-****-* i 1.' Standard Screwdriver !

el AT TM* rettovec .t,oCAL I 2. Jumpers (Alligator. Clips) I ecTAu. 74 roue c .a.TTANTUts.

cats. I 3. F ash ight la toCAT~ w To w g 4, .

nu. no rna 3 s l

800$A-2 5

coprnot 8 3 1 rT 300 47,.

0-2

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FRAME 18

. Panel- 600/280 VAC HCC 1R24-SD12 M2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 [18 19 20 l

l. .- -

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f

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3 ,

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a 4..= .=- .. .

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l Location 130RFR02 .

I Compartment Frame 18. Too Como.

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f) ntsfAAf DaTwtLL COOLot rnoutB As FOLLows.

a. es an sons .Arca AvaAnurr '

SEND OPERATOR,l&C TECH)

! t'. I e)n rue es4 ue ess, etActeTd 'I"'E"* ""'

Omnt COase systru suo man 3R ELECTRICIAN TO RESTART DRYWELL CHA.I.ERS AND

[ E W aj'Eg" M5"&^'* COOLING FANS rams.

a.r tw rm (OCA ovenner surcw s es0PERaTrvt 04 esACCC3%etr. iKM LNOTE 16 A CAU 3 )

PROCEID AS FOLLori to STAAf TK Derwat C00Les FAM5e of AT 6dCC M24-50s. AT LOCAfsow OO9eE3.ev5f ALL 18( FOLLowrc ru. tc w to 'c-'t gig'4^ "J ."3 FLOWCHART /

LOCATION (747-8004A-6 (747-600e6 4 f148 stes M'I N

Path 45. Unit 2/E-3

ye RCst? CRCLat egAKrJts roft 74.

, conc raus. .

EUM Purpose of Jumper: Start DW Cooiers ad AT adCC st26-50t?. A7 LOCATOf. .

DORP *m2 etSTALL T4 r0LLOweC *

.AMrotse .

fa tm to 7%

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'EU'.*00$*i(E"

=5

_- l Required Tools: l

,a o.,,t' , W = =>= as 'Ca x l nn-.00eA-2 I

""~ l 1.' Standard Screwdriver I r w rcilo 40en. reartms.

'5ta I 2 Jumpers -(Alligator Cl.ips) _ l _

te ' M ru a's petas-tocera n = u. To m l 3. F1ashiight I 8747 a00$A 00W402 0 3 g 4* .

l no. -2 00, 0 . 3 l l l 80096-2 c ,

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Panel' FRAME 19 Y2 600/280 VAC MCC 1R24-S012 . -

3 4 5 6' 7 4 ._8 _ _ . 9 10 11 12 13 1.4 -

15 ~16 17 18 19 . -20 V,

_

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f.

1 Location 130RFR02

, Compartment Frame 19. Top Como. -

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.j / A t.luMftr.s 8 If e ,

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SEND OPERATOR joNrER YEuYo* """' ** * ""

START RCIC ROOM COOLERj T ]%,y rEto'E"c'To" *ra"7 r"Noo# 4 Plt'icC -

u oTE 2s / ,

( ..

, y ,flc % e, o, , y i m s <c-n n e *c-1

.aost e=R 4e FLOWCHART /

mic es LOCATION -- Path 45/M7. Unit 9 T3 LOCALLY START T){ iPO OR ROC CUoLERS PCRroRW TtC roLLoWNGe

' E lj @o " " " " " E^C" C * '" ' *C Purpose of Jumper: Start RCIC Coolers e fe,w p m W A TM _ Jt M.Pm 4 -- Ot2/ -

rr = Dit" son"& ooarn24 ISIS's5

2. @,ggMay7,T 'Artn sterLr l Required Tools:

- l em m m r.ts= y vir vr

[0CAmtf I i ree ro4oA sTama 1. Standard Screwdriver W

kvsoo44 rT 4*sa 5.".<oni arwma US$"r*s a

emca:s i l

2. Jumpers (Alligator Clips)

I I

l 3. 5/16" Nut Driver !

I 4. Flashlight !

I I FRAME 4-Panel 600/280 VAC MCC 2R24-5011

... 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15

, 16 17 18 19 20

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Location 130RFR14 !

Compartment Frame 4, Top Comp.

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A ._ -

/g q E REIOTE START OF RCIC ROO M COOLER u5 l A 500 s

! Nun __ z z eis p_a f w__ l s

ru ci CABLE .SP/?EAD R O o rr7

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9 m ATTACHMENT 5

)

PROCEDURE STEPS FOR REMOTE SHUTDOWN IN SEQUENTIAL ORDER This attachment contains all steps, notes, cautions and fire notes required to shut down both units to the Cold Shutdown Condition under Appendix R fire emergency conditions only. The information is listed in the order the operators should execute the procedure.

Due to the nature of the Appendix R Training the route through the Flowchart has been predetermined with only one exception, i.e., near the exit point for Path 45 the scenario is branched into two possible-paths depending upon whether or not the RPV water level is under control. The instructor should cover both of these branching points.

a

.]

l

! \

l AS-1 Rev. A i

1 . _ . . - - - - - . -- ,. . . - - . - . _ - - - _ - - - - - - . . - - - - - - - - . - - - . . -- - - . . -

- C(bFD EM EORGIA POWER COMPANY 3lE0-E0P-002-25 HATCH NUCLEAR PLANT TIVE REVISION O l sFlTE NOV I,1986 APPROVED BY: DATE DEPT MGR.

GEN.MGR.

ANY SCRAM /T o~

~

r 1 NANUAL SCRAM gi L J I PLACE MODE SWITCH TO 3 REFUEL - NOTE STATUS OF REFUEL MODE SELECT A_

g PERMISSIVE LIGHT g r 7 PLACE MODE SWITCH TO ' -

SHUT DOWN O)

L J

F =

is NO CONTROL ROOM -

f ACUATION REQUIRED

Ab L J E YES "o AS E PN AT LOCATION DORAR16 AND 2

D-l ^""ed'Eu!E Of"ELERo$2Cr "# . -

l kEMOR SUPERVISOR SEND STA

^ '

CNuNN$CAUsSNS BE EN b gPANEL 2Ca2-POOIAND TSC;

$1"TOYNN s T -

FIRE 27 O# YO"ER TO 3EP j IF FIRE IN MAIN CONTROL ROOM, CABLE SPREADING- ROOM OR COMPUTULROOM AND IF MANUAL START OF DlESELS 2A OR 2C ISENOR SN. -PERVISOR NOTIFY, 15 REQUIRED THf_N PROCEED AS FOLLOWS IN ADDITION STA TO INITIATE TO DlESEL PROCEDURE 3450-R43-001-2S:

EMCROENCY CALL IN L1ST + 6,9a FOR DIESEL 2A ORSN$$fNTfkb",S - OPEN BRKR 14 AT 2R25-S004 TO ISOLATE

' j g3' REMOTE CIRCUITS O$ALNCATIOhS NRANTJ ---------- - FLASH GENERATOR AFTER DIESEL IS RUNNING--BY l

o PLACING LOCAL START SWITCH TO REMOTE 27 g l I 7 - PLACE VOLTAGE REGULATOR IN AUTO BY OPENING

' SEND OPERATOR TO LOCATION LINK TAl-T IN 2R43-P00lA AND JUMPER TERMINALS OOTETO TO OC SwcR 2R22-SO66 g- TAl-8 AND TAl-9 L_

U $N.S$nalhR $$ J FOR DIESEL 2C 50TIFY OPERATOR AT LOCATION - OPEN BRKR 14 AT 2R2S-S006 TO ISOLATE

" REMOTE CIRCUITS sPDS E R 0 C Sw" 6f Qg sga (PN - FLASH GENERATOR AFTER DIESEL IS RUNNING BY 2H2 P248; I 7 - PLACE VOLTAGE REGULATOR IN AUTO 8Y OPENING

AT PANEL 2H21-PIT 3 LINK TAl-l IN 2R43-P00!C AND JUMPER TERMINALS AT LOCATION 13ORARis C *_ J TAl-8 AND TAI-9

< * ""e "RRE4^a"'"' ;

T

\A/ e

A I ON PANEL 2C82-POOf AT '

LOCATION 83ORAR66 PLACE

'C$

NUCLEAR BOILER INSTRUMENT SwlTCH TO EMERC POSITION AND MONITOR REACTOR PARAMETERS CAUTION 10 cAu lo A ' ' i _

ALL AUTOMATIC PROTECTION TRIPS ARE REMOVED AND ALL ECCS INTERLOCKS ARE DEFEATED WHEN THE EMERGENCY I 7 !

CONTROL TRANSFER SWITCHES ON THE' REMOTE SHUT 00WN IS -

PANELS ARE PLACED IN THE EMERGENCY (EMERG OR EMER)

SPDS > 'CD POSITION.

AVAILABLE '

L J l K YkA ARE 44-YOU HERE YES- '

FROM PATH 18 SPOS LENOT[AND AV l

NO

/

CAN REACTOR POWER N0i

EVEL SE DETERMIN L J

_ , , . YES

, I 1

, ~.

ARE PC Nh ALL CONTROL YES j RODS INSERTED PAS i POSITION O I 1

NO u

NOTE 8 HEAT CAPACITY TEMoERATURE LIMIT SUPPRESSION POOL MAXIM'fM REACTOR

{ TEMPERATURE . PRESSURE

[S hD T W INT A 3f BELOW IST*F 1090 PSIC I

( NOTE B q REACTOR PRESS BELOW THE HEAT C APACIT Y TEMPERATURE LIMIT ;

i-- ,,___- JST *F TO 159+ *F 160 *F TO 169+ *F 170 *F TO IT9+ *F 900 PSIG 600 PSIG 300' PSIG 180 *F TO 189+ *F 200 PSIC FSEND OPERATOR TO DCTERMsHEl ABOVE 190*F 13 5 PSIG OPERABE.fTY OF REACTOR WATER LEVEL INSTR ON RACKS 2H2 MOO 4

pj - '

AND PCO5 AT LOCATION g 158RERiT AND L58HER2 ; _.

7 F

. . - - - - - - -- - _ _ _ _ _ _ _ _ _ J

^

i 1 B

CAUTION 9 i DIAG 7 NO CAN REACTOR WATER Df IF SPDS AND PROCESS COMPUTER ARE NOT AVAILABLE AND 3

LEVEL SE DETERMINED > FOR CONDITIONS SHOWN BELOW ACTUAL REACTOR VESSEL LEVEL MAY BE BELOW THE LOWER IN$TRUMENT TAP. USE ANY AVAILABLE DRYWELL RTD.

L CAU9j~"-~~~-~~~~

DRYWELL INDICATED LEVEL YESE . TEMPERATURE LEVEL INSTRUMENT LOCATION F 7

"^$ ABOVE 125'F BELOW 2821-N024A,8 158RER16 YES TEMPORARY O i"Df -107 IN 2821-NO3tA PS

PERMANENT LOSS OF >.

hNORm4AL AREA LICMTNG RACK 2H21-P004)

( j ABOVE !25'F BELOW 2821-N025A,8 158RHR22

-107 IN (ON RPS

% NO r INSTR RACK 2H21-P005)

ABOVE (25 *F BELOW 2C82-R005 130RAR16

-107 IN (ON REMOTE SHUTDOWN PANEL 2C82-P00!)

ABOVE 285*F BELOW 2821-N042A 158RER16

+26 IN (ON RPS INSTR RACK 2H21-P004)

F FIRE I ABOVE 400*F BELOW 2821-NO36 130RFR23 NOTIIC TION + ( RPS i

YES i BEEN RECEIVED OR DO WT

%vQFIED ALARMS INDICATE RACK A FIRE ANYWH E% ' 2H21-P010)

NO

'N u s

\ 's NOTIFY OPERATION

, 'g N N FIRE I IF FIRE IN CONTAMINATED AREA, NOTIFf HEALTH PHYSICS SUPERVISOR ON SHIFT I AND SHIFT SUPERVISOR TO RESPOND TO FIRE SCENE.

3 [5l SECURITY TO I, . NOTIFY

.SO.UND, FIRE ALARM J

l'd{

FROM ANY PAGE STATION lMAKE FIRE ANNOUNCEMENT 3 TIMES l DISPATCH FIRE BRIGADE Al WITH OUAlfFIED BRIGADE y e 1 CHIEF AND 2 WAY RADIOS NOTIFY UNIT I SHIFT dl IST A T MAY UNIT I SHUTDOWN ECT j

NO 85 Nl VERIFIED FIRE LOCATED IN REACTOR BLDC YES

\

F IF SMOKE IS OBSERVED IN 3

8/

i

. REACTOR BLDG VENT SUPPLY SENO i OPERATOR TO WCC2R24-sol 5 AT -

LOCATION 185RFR23 TO TRIP t FANS 2T4l-COOlA AND B J l

\c /

'y 0

FIRE 14 IF FIRE N DIESEL BUILDING THEN TAKE ACTION SEND OPERATOR TO FIREl 6( INDICATED FOR AREA INVOLVED:

IPUMP HOUSE START DIESEL FIRE PUMPS cog 2AANDB J TO VERIFY OR AREA DG SWGR ROOM 2E ACTION ISOLATE PUMPS 2Y52-C001A (2AD SEND OPERATOR TO 4160V l S R R22-S 6\ EN VA S 4 0 C*

1is gc eLoO OO RATE BRKRS TO START MOTOR FIRE PUMP IX43-COOi ;

2R43-F007E.2R43-F008A, 2R43-F008C,2R43-F008E

- CLOSE VALVES 2R43-F0070, 2R43-F0088,2R43-F008D UN ECKS OF '

2YS2-C00 IMAKFIRE PUMP OPERATION AND OF DIESEL FUEL SUPPLY J

( 0

- OPEN VALVES 2R43-F007C 2R43-F00TE,2R43-F008A AND

2R43-F008C

- CLOSE VALVES 2R43-F007D AND 2R43-F0088 DG SWGR ROOM 2G ISOLATE PUMPS 2Y52-C101A (2A2) AND 2YS2-C10lC (2C2)

YES START UP AND OPERATION OF 1l ,

- OPEN VALVES 2R43-F007A. 2R43-F007C 2R43-F008A AND 2R43-F008C

- CLOSE VALVES 2R43-F0078 AND MOTOR OR OtESEL FIRE 2R43-F0088 PUMPS VERIFIED +

DG 2A DAY. TANK ROOM DE-ENERGIZE FUEL Oll TRANSFER PUMPS NO 2YS2-C001A (2AD AND 2YS2-Cl01A (2A2)

AT 2R24-5025, FRAME TE AND 2R25-5027 FRAME 7F w - - - --u m - - r DG 2C DAY TANK ROOM DE-ENERCl2E FUEL Olt TRANSFER PUMPS

/

\

SEND OPERATOR TO DIESEL I /

f 7

2YS2-C00lC (2CD AND 2YS2-Ci0lC (2C2)

AT 2R24-SO25, FRAME 7F AND 2R25-5027 FRAME 7F DG 2A BATTERY ROOM DE-ENERG!ZE PUMP 2Y52-C101A (2A2) AT BLDG TO DETERMWE 2R24-5027, FRAME 7E t

PR Fg Ho IFJ g/ l

/

DG 2C BATTERY ROOM DE-ENERG!ZE PUMP 2Y52-C10lC (2C2) AT -

! / 2R24-5027, FRAME 7F .

( FIRE 1 / DG 2A ENGINE ROOM DE-ENERGlZE PUMPS 2YS2-C00!A (2AU N

HAS (32, / l AND 2YS2-C10lA (2A2), AT 2R24-SO25 i ggy gTgF CAv ION R DO NO . FRAME TE AND 2R24-5027, FRAME 7E' LARus wDICATE A DG1C ENGINE ROOM DE-ENERG!ZE PUMPS 2YS2-C00lC (2CD N DIESEL 8LDC AND 2YS2-C101C (2C2), AT 2R24-S025' FRAME 7F AND 2R24-5027, FRAME 7F YES f FIRE 30 SEND OPERATOR TO DtESEL' g P BLDG TO DETERWWE DIESEL g3 FIRE 30 2A,2C OR 18 RUN AND ,.

' IF FIRE IN MAIN CONTROL ROOM, CABLE SPREADING-ROOM t LOADING STATUS ; ~

s OR COMPUTER ROOM THEN s -CLOSE DIESEL GENE'.RATOR 2A METER SHORTING LINKS IN r33 ~

' PANEL 2R43-P00!A OR JUMPER TERMINALS TA2-4 TO TA2-5 DIES S 2A,2C YESj -

TO TA2-6 TO TA2-7 IN PANEL 2R43-P00lA AND 18 STARTED AND RUNNING AT I

-CLOSE DlESEL GENERATOR 2C METER SHORTINOTINKS IN SPEED PANEL 2R43-P00lC OR JUMPER TERMINALS TA2-4 TO TA2-5 NO TO TA2-6 TO TA2-7 IN PANEL 2R43-P001C TO PREVENT FIRE DAMAGE TO DIESEL GENERATOR METERING.

SEND ASSISTANCE TO OPE O IN OCA ART OF DIESELS j I

NOTIFY OPERATOR IN R Y lg3 R lE F25 rDC P TO CAB 2D(2R25-SOO4)

, gAND CA8 2F(2R25-SOO6))

W .

~

fl8E 27 r FIRE 27 \ JF FIRE IN MAIN CONTROL ROOM, CABLE SPREADING- ROOM OR ts0TFY OPERATOR AT DIESEL'I IS REQUIRED THi AND ROOM'N IF MANUAL START OF DIESELS 2A OR etoo TO ATTEMPT local START Ig3 OF DIESELS 2A,2C OR 18 fTO COMPUTER DESEL PROCEDURE 34SO-R43-001-2S:

PROCEED AS y PER 34SO-R43-001-2S j,%.s' %

FOR DESEL 2A g - OPEN BRKR 14 AT 2R25-S004 TO ISOL TE YES is REMOTE CIRCUlTS 2A 2C N ETED NO R AT - FLASH GENERATOR AFTER DIESEL IS RUNNING 41Y PLACING LOCAL START SWITCH TO REMOTE NO

/

' - PLACE VOLTAGE REGULATOR N AUTO BY OPENNG LINK TAl-7 IN 2R43-P00lA AND JUMPER TERMINALS

! TAl-8 AND TAl-9 FOR DIESEL 2C (FIRE 2e ~ !

- OPEN BRKR 14 AT 2R25-S006 TO ISOLATE REMOTE CIRCulTS swoR 2s 2E g3 FROM EITHER AVAILASLE SAT

- FLASH GENERATOR AFTER DESEL IS RUNNING BY f M FROM MESEL 2A F RUNNING A PLACING LOCAL START SWITCH TO REMOTE N

f LNOTE 23 $ CAU 3 J - PLACE VOLTAGE REGULATOR IN AUTO BY OPENING i

If NOTIFY OPERATOR AT govy w g 2g2g g 5 N.

g 's s .

LINK TAl-l IN 2R43-P00lC AND JUMPER TERMINALS TAl-8 AND TAl-9 t_AT w N N 2P4 C N y

I \

l \ N s

( \ NOTE 23 f IF THE DESEL GENERATOR OUTPUT BREAKER FAILS TO FRE 28 AUTOMATICALLY CLOSE. THEN VERIFY DESEL GENERATOR IS AT RATED SPEED AND VOLTAGE AND ATTEMPT TO CLOSE-IF FIRE N MAN t'ONTROL ROOM, CABLE SPREADNG-ROOM OR PUT BREAKER BY ANY OR ALL OF THE FOLLOWNG COMPUTER ROOM AM) DESEL 2A OR 2C HAVE NOT TED TO TIElR 8 4860V EMERGENCY -80S THEN PERFORM THE FOLLOWNG FOR THE AFFECTED BUS: L PLACE 0UTPUT BREAKER CONTROL SWITCH ON PANEL P652-TO CLOSE RESTORE SWGR 2E(2R22-SOOS) AM) 20(2R22-SOOT) AS QUICKLY 2. LOWER DESEL GENERATOR FREQUENCY TO 58 HZ AND i AS POSSIBLE TO ENSURE PSW SUPPLY TO DESELS.

LNE UP THE SWGR AS FOLLOWS ' READJUST TO 60HZ AND CHECK FOR BREAKER CLOSURE 2E(2R22-SOOS) OPEN 30A CONTROL POWER SKRS FOR 3. LOCALLY CLOSE THE OUTPUT BREAKER BY PUSHING UP '

ALL FRAMES ON THE LIFT TO CLOSE PLUNGER AT THE BREAKER CABINET CLOSE BKRS: STA SERVICE TRANSF. 2C FRAME 2 PLANT SERVICE WATER PbMP 2A, FRAME 4 \

POTENTIAL TRANSFORMER, FRAME.,5 \

~

OPEN ALL OTHER BKRS. \

! 20(2R22-S007) OPEN 30A CONTROL POWER SKRS FOR

\

i ALL FRAMES a" \

' \

CLOSE BKRS: STA SERVICE TRANSF. 2D FRAME 2 \

i PLANT SERVICE WATER PUMP 28, FRAME 5

, POTENTIAL TRANSFORMER, FRAME 6 g g

OPEN ALL OTHER BKRS. \

THEN CLOSE GENERATOR FEEDERS DG1A FRAME 6 OF 2E(2R22-SOOS)

[ '

CAUTION 3 DG 2C FRAME T OF 20(2R22-S007)

VERFY DIESEL GENERATOR LOADNG DOES NOT EXCEED THE

!-CLOSE THE 30A CONTROL POWER BREAKERS FOR THE FOLLOWING RATNGS FOLLOWING A LOSS OF OFFSITE POWER

! FOLLOWING-COMPONENTS WHEN THEY ARE REQUIRED FOR TO AVOID DESEL OVERLOAD. AMPERAGE NDICATIONS ARE

, OPERATION AND DIESEL LOADNC IS ADEQUATE, THIS WILL I LOCATED ON PANEL R43-P00lN EACH DESEL GENERATOR ROOM.

j ALLOO OPERATION AT THE REMOTE SHUTDOWN PANELS: I RATNGS (AMPERES)

COMPONENT SW_gfL FRAME DESEL CONTINUOUS T DAY 068 HOURN IA 490 560 i RHR SERVICE WATER 2B 2 Ell-C0018 20 (2R22-S007) 3

' RHR SERVICE WATER PUMP 2D 18 490 560

i. (2 Ell-COOID) 2012R2 '-S007) 4 IC ,.,

490 560

! RHR PUMP B (2 Ell-C0028) 2G (2R22-S007) 8 2A 490 560 i

! 2C

-~

490 560

'THE HIGHER 7 DAY RATING 15 BASED UPON A fEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE l - CONTINUOUS Rf TM: A TnTit ne me um me rm -r THE

6 E

440V fNOTIFY TO WGR 2R22-SOOS VERFY OR OPERAeTOR IN DESEL SL AT CLOSE 4860V FEED g (BRKR TO 2R23-SOO3 (FR8)J FFIRE 28 VERIFY OR TE POWER TO 4460@' , , , - #d

SWGR (2R22-SOO7320 9 AGE FRCW EITHER AVAILABLE SAT 1*

OR FROW DESEL 2C F RUNNNG LNOTE 23 $ CAU 3 J I NOTIFY OPERATOR AT '

4'60V SWOR 2R22-SOOT TO OPERATE BRKR TO l4 g 9 START PLANT SERVICE (WAT ER PUMP 2P41-COO 4By (NOTIFY WGR 2R22-SOOT OPERATOR H OESEL SL AT c,a_ 4660V T

VERFY OR CLOSE 4860v BRKR TO 2R23-SOO4 (FR2)

NO IS O DfESEL IB REQUIREO FOR UNIT 2 SHUTOOWN YES FIRE 32 IF FIRE IN MAIN CONTROL ROOM CABLE SPREADING-ROOM OR COMPUTER ROOM, THEN PER$0RM THE FOLLOWING:

- 88 -OPEN BRKRS 16 AND 29 ON 2R25-S00L guy 4 goy p -OPEN BRKRS 17 AND 19 ON 2R25-5002.

0 SWca GR22-SOO5

-S006 OR NSOO -VERIFY OR CLOSE THE FOLLOWING BRKRS ON 2R23-S003 2E,2F;oR 20 *.- (600V

- SWGR 2C) -

- - ^

COMPONENT FRAME

\..-FFIRE / 7 32 s , . YES ~

ESSENTIAL TRANSF 28 CABINET 2A 2M i , -y -

~~~ ' REACTOR BLD A MCC 2C 3M l SEND OPERATOR TO LOCAT R .

f DIESEL BLDG MCC 2A 68 130TETl4 TO. VERFY OR TE POWER :TO ' 600Y SWOR D4 y BATTERY CHARGER 2C 78 y BATTERY CHARGER 28 7M l t 2R23-SOO3 (2C) - g / BATTERY CHARGER 2A TT

/ 8 r FIRE 32 - ~ 49' ' 4160/600V STA. SERVICE TRANSFORMER 2C

-VERIFY OR OPEN ALL OTHER BRKRS ON 2R23-5003.

13 TCT POWER TO 600V SWOR D4- i ~VhFY g R CLO E THE FOLLOWING BRKRS ON 2R23-S g 2R23-SOO4 (2D) ; COMPONENT FRAME 8

CA[2R2PC ^T T 830TDTt3 T OPEN SRER 29

$ Di A Y CHARGER 2D BATTERY CHARGER 2E 3

3M TO BYPASS LOSP LOAD SHED BATTERY CHARGER 2F 38 g FOR 600V SUS 2C ; 600/208V MCC 28 ESS. DIV 2 4T DIESEL BLOG MCC 2C TB FSEND OPERATOR TO 12SVOC' i ESSENTIAL TRANSFORMER 2C CABINET 28 ~A CAB 2R25-SOO2 AT. LOCATION -VERIFv OR OPEN ALL OTHER BRKRS ON 2R23-S004.

f30 TOT!3 TO OPEN BRER t9 !'

TO BYPASS LOSP LOAD SHED g FOR'GOOV BUS'20 J, I SENO OPERATOR TO 'l -

VER S R2$

OR START RBCCW YTO 5%

g PUMP 2P42-COOtA OR IC j f SEND OPERATOR TO S R2 O TO E 4-VERFY OR START RSCCW g PUMP 2P42-COOtB j' (SEND OPERATOR TO LOCATION 7 130 TOT!3 TO VERFY OR TIE POWER TO VITAL AC BUS I E +-

2R25-SO63 FROM SWOR

( 2R23-SOO4 OR 2R23-SOO3 ) '

i.... .

TO REST ART DRYCELL C00LitoC. PROCEED AS FOLLOOS:

A. I. ON PANEL 2Hil-P654 AND P657 PLACE DRYWELL COOLWG SYSTEM LAND llFAN LOCA OVERRIDE SWITCHES TO BYPASS AND r 3 VERIFY OR ST ART THE DRYWELL COOLING FANS.

dEND cLEC AN TO E T .

DRYWELL CHILLERS ANO COOLNQ FANS f3 2. IF THE DRYWELL COOLING SYSTEM FAN LOCA OVERRIDE SWITCH IS INOPERATIVE OR i INACCESSIBLE, THEN PROCEED AS FOLLOWS CAU 3 J t L NOT E e6 4 TO START THE DRYWELL COOLING FANS:

F VERpFY OR RESTORE 7) c) AT MCC 2R24-S0lt, AT LOCATION 825/250V STATION SERVICE 130RFRl4 INSTALL THE FOLLOWING BATTERY CHAROES TO lb JUMPERd:

T FAN TERMINAL TO TERMINAL g 34 N 4Y- 25

\ 2T47-B007A 18Al 18Al7 g 2T47-C00lA 18Cl 18C2 2T47-COO 2A 22Cl 22C3 b) AT MCC 2R24-S012 AT LOCATION is l'\ 130RFR24, INSTALL IHE FOLLOWING ANY 4460V f JUMPERS:

g NO SWGR (2R22-SOO5 FAN TERMINAL TO TERMINAL R22-SOOG OR 2R22-SOOT \

2E,2F, OR 20 ENERClZED 2T47-80078 18 81 1882 FROM EIT SAT \ 2T47-C00lB 19Al 19A2 YES 2T47-C0028 23a 23C3 I c) AT THE FOLLOWING LOCAL STARTERS, t INSTALL THE FOLLOWING JUMPERS:

FAN STARTER TERMINAL TO TERMINAL ripRE 3e g 2T47-8008A 2R27-S007 1 17 2U 2C \ 2T47-8008B R27- 08 l 17 i

0 MO

^"

O 4 "op E ! 2T47-8009A 27- 09 l 17 No ERS j

^

FNFORM OPERATOR W DIESEL 3 2T47-8009B 2R27-SO10 1 17

/ SLDC TO NOTIFY SieFT SUPERVISOR 1 13ORHR24

/ AND TRIP ANY DIESEL WHOSE JACKET WATER TEMPERATURE

% \ B. (PRIMARY CONTAINMENT CHILLED WATER SYSTEM CANNOT BE STARTED WITHIN 15 MINUTES OF ANY

/ L REACHES 7t2*F ;; \ SYSTEM SHUTDOWN)

/ \ 1. ON PANEL 2Hil-P700 PLACE THE LOCA OVERRIDE SWITCH (2P64-S3) TO OVERRIDE

\

hy I AND START THE PRIMARY CONTAINMENT

\

g CHILLED WATER SYSTEM PER

\ 34SO-P64-001-2S

\ \ 2. IF THE LOCA OVERRIDE SWITCH IS

\ INOPERATIVE OR INACCESSIBLE THEN

\ PROCEED AS FOLLOWS TO START THE

\ \ DRYWELL CHILLERS:

c)*0 PEN THE FOLLOWING LINKS TO OVERRIDE

\

g

\ TRIP SIGNALS FOR BOTH CHILLERS:

g

\ LINK LOCATION CHILLER

\

I TBi-12 PANEL 2H21-P230 2P64-BOO 6A g g TBI-12 PANEL 2H21-P232 2P64-80068 b) DEPRESS THE LOCAL ON-STOP BUTTON OR

\ \ TURN THE ON-STOP SWITCH ON PANEL

\ \ 2Hil-P700 TO THE ON POSITION FOR

,a PRIMARY CONTAINMENT CHILLER

\ \ 2P64-8006A OR 2P64-80068 s

FIRE 31 (

FIRE W MAN

{0MPUTER CONTROL ROOM, AND R00 IFCABLE SPREADING-ROOM ADEOgATE DIESEL COOLNCr-CAN OR \

\

.40T BE MAWTANED THEN SEND OPERATOR TO VERIFY OR ' ^ '"

(ANUALLY CLOSE PSW T/B ISOL VALVES 2P41-F3l6A AND

,P41-F3168 AND RADWASTE DILUTION VALVE 2P41-F310: VERIFY DIESEL GENERATOR LOADING DOES NOT EXCEED THE VALVE BKR LOCATION FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER VALVE LOCATION TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE P4l-F316A 2R24-SO25, COMPT 4D PSW VALVE PIT 2A LOCATED ON PANEL R43-P00llN EACH DIESEL GENERATOR ROOM.

]P41-F316B 2R24-SO27, COMPT 4D PSW VALVE PIT 2B RATINGS (AMPERES)

.P41-F310 2R24-S010, COMPT 2A WTAKE VALVE PIT DIESEL CONTINUOUS 7 DAY (168 HOUR)*

IA 490 560 IB 490 560 IC 490 560 2A 490 560

- 2C 490 560

THE HIGHER 7 DAY RATING IS BASED UPON A fEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR WITH A LOAD OF 490 TO 560 AMPERES IS ALLOWED.

NOTE 23 b IF THE DIESEL GENERATOR OUTPUT BREAKER FAILS TO AUTOMATICALLY CLOSE THEN VERIFY DIESEL GENERATOR IS AT RATED SPEED AND VOLTAGE AND ATTEMPT TO CLOSE g 3 THE OUTPUT BREAKER BY ANY OR ALL OF THE FOLLOWING g3 METHODS:

PRn$[ABOVE I. PLACE OUTPUT BREAKER CONTROL SWITCH ON PANEL L63 PSic P652 TO CLOSE

2. LOWER DIESEL GENERATOR FREQUENCY TO 58 HZ AND L

E NO J *- ' / READJUST TO 60HZ AND CHECK FOR BREAKER CLOSURE

/ 3. LOCALLY CLOSE THE OUTPUT BREAKER BY PUSHING UP ON THE LIFT TO CLOSE PLUNGER AT THE BREAKER

/ CABINET

/ /

if REO'D SEND OPERATOR TOl /

S'" E* '"

'#0ftvE Ed"IO D8ERMEE 6(e /

/

" vTaES se'47S"sl6A.e.CE r

/

/ NOTE 16

/ TO RESTART DRYWELL COOLING. PROCEED AS FOLLOWS:

A. 1. ON PANEL 2Hil-P654 AND P657 PLACE

/ DRYWELL COOLING SYSTEM l AND ll FAN

/ LOCA OVERRIDE SWITCHES TO BYPASS AND VERIFY OR START THE DRYWELL COOLING

/ FANS.

/ 2. IF THE DRYWELL COOLING SYSTEM FAN LOCA OVERRIDE SWITCH IS INOPERATIVE, OR -

'~~

/ lNACCESSIBLE, THEN PROCEED AS~FOLLOWS " -

/ TO START THE DRYWELL COOLING FANS:

/ a) AT MCC 2R24-50!!, AT LOCATION x / 130RFRl4, INSTALL THE FOLLOWING FFIRE 23 X / JUMPERS:

Oc O MmNT SERVICE WATER DIVISION l AND b:1

. FAN 2T47-8007A TERMINAL 18Al TO TERMINAL 18Al7 i 5 HEADER PRESSURES FROW 2T47-C00!A 18Cl 18C2 i L 2P41-P1-ROO3 AND ROO6 J 2T47-C002A 22Cl 22C3 l b) AT MCC 2R24-5012, AT LOCATION PLANT $ *7 130RFR24, INSTALL THE FOLLOWING SERVICE WATER NO! JUMPERS:

^" "

PRES BO E ,

FAN TERMINAL TO TERMINAL 60 PSIC 2T47-80078

! 18 81 1882 l

g5 ,

'/ 2T47-C00lB 2T47-C0028 19Al 23Cl 19A2 23C3

/

r SEND OPERATOR OR I & Cb" TECHP#CIAN OR ELECTRICIAN c) AT THE FOLLOWING LOCAL STARTERS.

/ INSTALL THE FOLLOWING JUMPERS:

"T L l CHELERS FANS q FAN STARTER TERMINAL TO TERMINAL ;

PER 34SO-P64-OOf-25 J 2T47-8008A 2R27-S007 1 17 i (NOTE 66 q ~

2T47-8008B 130RHRl4 2R27-SOO8 l 17 F INSTRUCT OPERATOR TO 7 ., 130RHR24 IMMEDIATELY REPORT ANY d fi / 2T47-8009A 2R27-5009 l 17 PROBLEMS ENCOUPfTERED WITH I 13ORHRl4 RESTART OF ALL DRYWELL i 2T47-8009B 2R27-S010 1 17 (CHILLERS AND COOLINC FANSJ 130RHR24 B. (PRIMARY CONTAINMENT CHILLED WATER SYSTEM ScRvicE B7 CANNOT BE STARTED WITHIN 15 MINUTES OF ANY

,NO ATER TURSINE BLDG -SYSTEM SHUTDOWN) s (PSW T/B tSOu VALVES 1. ON PANEL 2Hil-P700 PLACE THE LOCA 44-F366A. B. C. OVERRIDE SWITCH (2P64-S3) TO OVERRIDE OS AND START THE PRIMARY CONTAINMENT 3 CHILLED WATER SYSTEM PER YES I 34 SO-P64-001-25 E L HAS L T) 7- CI C 2. IF THE LOCA OVERRIDE SWITCH IS YES A TEMPORARY OR INOPERATIVE OR INACCESSIBLE, THEN MANENT LOSS OF NORMA PROCEED AS FOLLOWS TO START THE AREA UCHTINo DRYWELL CHILLERS:

a)*0 PEN THE FOLLOWING LINKS TO OVERRIDE i TRIP SIGNALS FOR BOTH CHILLERS:

LINK LOCATION CHILLER CH y ~

~

TBI-12

' TBI-12 PANEL 2H21-P230 PANEL 2:121-P232 2P64-B006A 2P64-80068 b)~ DEPRESS THE LOCAL ON-STOP BUTTON OR TURN THE ON-STOP SWITCH ON PANEL 2Hil-P700 TO THE ON POSITION FOR PR! MARY CONTAINMENT CHILLER D 2P64-8006A OR 2P64-80068

, YW I

NOTE I

, N0 AYWELL PRESSURE _ GROUP 1 ISOLATIONS

> N PAsOvE ts3 PSto KEY RAMETER ANSW ONLY VALVES NORMALLY OPEN AND IN LINES GREATER THAN TES 4 [N. DIAM. AND OUTSIDE THE DRYWELL ARE LISTED HERE.

A COMPLETE LIST IS AVAILABLE WHEN YOU ENTER THE END YES PATH MANUAL.

wAS g7 VALVE LOCATION _ DESCRIPTION ES ,$y" $ west 0

2821-F028A 130RBRl9 OyTBOARD MSIV I' KEY PARAMETER 2821-F0288 13ORBRl8 OUTBOARD MSIV ANSWERED '

- 2821-F028C 13ORBR2O OUTBOARD MSIV y '

- 2B21-F028D 130RBR19 OUTBOARD MSlv NO -

ISEND OPERATOR TO LOCATIOM 130TOTl2 CAB 2C71-POOi TO g7 OPERATE 800 AMP BRKR CS2A (AN) TO MOMENTARILY DEENERGlZE RPS BUS 2A j L NOTE I q NOTIFY OPERATOR AT LOCATIOd 13070T82 CAB 2C71-POOf TO OPERATE 100 AMP BRKR 67 CB2B (AX) TO MOMENTAR!LY q DEENERGlZE RPS BUS 28 y Y FlRE l g[ !

OTIFICATI N BE ECErVED OR DO VERfF W'EE ~ ~ ~ ~ ~ ~ '

IF FIRE IN CONTAMINATED AREA, NOTIFf HEALTH PHYSICS ALA MS NDICATE A FIRE TO RESPOND TO FIRE SCENE.

L j NO K

/

NOTIFY OPERATIONS I SUPERVISOR ON SHIFT AND

1. SHIFT SUPERVISOR 7

HOTIFY SECURITY TO SOUND dq 1 FIRE ALARM J

FROM ANY PACE STATION M;

lMAKE3 TIMES FytE ANNOUNCEMENT

.D,tSPATCH TH - leF,Rmm IRE B.RIOADE ICMEF- ANDnl 2 WAY HADIOS NOTine sHrT SueERvlS00 1ON UNIT JOF FIRE STATUS AS IT MAY EFFECT LNT I SHUTDOWN j VERFIED FIRE M NO LOCATED IN REACTOR BLDO YES

. W _

r '

'\

f F IF SWOKE IS OBSERVED W 7 REACTOR SLD0 VENT SUPPLY SEND OPERATOR TO WCC 2R24-Sot 5 !d AT LOCATION 195RFR23 TO TRP L FANS 2T41-COOIA AND 8 )

]

SEND OPERATOR TO FREl p

1 PUMP HOUSE TO VERIFY OR START DIESEL FRE PUMPS O(43-COO 2A AND COO 28 j SEND OPERATOR TO 3 4160V $ WOR (IR22-SOO5HE I - q ATbBR TO START l OTOR FRE PUMP D(43-COOJ MSTRUCT OPERATOR TO WAKE 7 FREQUENT CHECKS OF FIRE PUWP OPERATION AND OF C9 DESEL FUEL SUPPLY j f

I l

YES,, STARTUP Ate OPERATION OF

($

f

WOTOR OR DIESEL FRE

t. S vERinED !'

/ , L;m . a

+

IS CD

.NO THE MAN TUR8ME INVOLVED N THE DENTIFIED ,,

l

..~:. '

. YES . .FRE.. w . -

. _ _ _ _ g .'

FFRE 23 k\

SEND OPERATOR To LOCATIOtB l 83ORLRf9 TO DETERMINE '

PLANT. SERVICE WATER DivtS40N l A#G E HEADER PRESSURE FROM 8

L. - 2941-Pt-ROO3 OR ROO6 ) y F 7 l\

'~

',-- ptAur 84, s s

. . SERVICE WATER - NDI* \

4 OfvtS80N"I AND E HEADER SURES A80V M *

\

g 60 Psic s g

L J ,

N 6-J: YES NOTE 23 1

FSee OPERATOR TO LOCAT Oil 11 IF THE DIESEL GENERATOR OUTPUT BREAKER FAILS TO

' M..

52TCT15 TO VERIFY OR OPEN RSCCW PUMP DISCH VALVE g -

AUTOMATICALLY CLOSE. THEN VERIFY DIESEL GENERATOR IS AT RATED SPEED AND VOLTAGE AND ATTEMPT TO CLOSE

, THE OUTPUT BREAKER BY ANY OR ALL OF THE FOLLOWING L 2P42-FOO5A,8 OR C '; METHODS:

PhSTRuCTOPf570RATLOcATxwn .

I. PLACE OUTPUT BREAKER CONTROL SWITCH ON PANEL 82TCT15 TO DETERWINE FROM g4 P652 TO CLOSE

hYCH p

& WITN OPEN OtSCH VALVEg bS "

h 2. LOWER DIESEL GENERATOR FREQUENCY TO 58 HZ AND

- READJUST TO 60HZ AND CHECK FOR BREAKER CLOSURE r- ,

F (, 3. LOCALLY CLOSE THE OUTPUT BREAKER BY PUSHING UP RSCCW

gg! ON THE tift TO CLOSE eLuNcER AT THE BREAKER HEADER PRESSURE CABINET g

ABOVE 90 PSIO L J

.-YES K .-

W

v ISEND OPERATOR TO 125VDC CA8 2R25-SOOI AT LOCATION L30 TDT!3 TO OPEN BRKR 29 TO BYPASS LOSP LOAD SHED FOR

[7 q 600V SUS 2C J ISEND OPERATOR TO 125VDC' CAB 2R25-SOO2 AT LOCATION 'g/>

130 TDT!3 TO OPEN BRKR 19 TO .

BYPASS LOSP LOAD SHED FOR t 600V SUS 20 J FSEND OPERATOR TO SWGR7 2R23-SOO3 AT LOCATION -7 130TETl5 TO OPERATE BRKRS T

TO START RDCCW PUMPS

( 2P42-COOIA OR IC J fSEND OPERATOR TO SWGRT

2R23-SOO4 AT LOCATION 130TETt5 TO OPERATE BRKRS TO START R8CCW PUMP M

t 2P42-COOtB J fSEND OPERATOR TO LOCATIOM M2TCT15 TO DETERMINE FROM 2P42-PI-ROO3A,8 OR C R8CCW PUMP DISCH 6r7

( PRESSURE J RBCCW N7 NO PUMP DISCHARGE PRESSURE A80VE TO PSIG YES F SEND OPERATOR TO SWGR 2R22-SOOI AT LOCATION !

130THT22 TO OPERATE BRKRS 'b 7 TO TRIP RECIRC MC SET t 2831-COOIA J f SEtc OPERATOR TO SWOR 7 2R22-SOO2 AT LOCATION 130THT22 TO OPERATE BRKRS IIu 7 TO TRIP RECtRC MC SET t 2836-COOes J F SEND OPERATOR TO MCC 7 2R23-SOU AT LOCATION gI 14TTAT23 TO OPERATE BRKRS TO TRIP RWCU PUMPS

L 2G31-COO!A AND18 )

ISEND OPERATOR TO LOCATION E3ORWt2A TO MCC 2R24-SO22 FR8 J AND INSTALL JUMPER BETWEEN (7 TERMINALS 186 AND IST

" ,7 t TO CLOSE 2G36-FOO4 y

( I SEND OPERATOR TO 41 GOV 7

{

SWOR (2R22-SOO512E ROOM M DIESEL SLDC TO NTE ORKRS tTO TRIP CRD PUMP 2CD-COOIAJ

['[

I SEND OPERATOR TO 4460V 7 SWGR (2R22-SOO632F ROOM l

i N DESE1 BLDC TO OPERATE BRKRS ff f/

(TO TRIP CRD PUMP 2 Cal-COOej I SEND OPERATOR TO SWGR 7 l

2R23-S004 AT LOCATION 130TCTl4 TO OPERATE BRKRS

(((

i TO TRIP R8CCW PUMP 2P42-COOtBJ

~

+ *

3 ,

FlRE 22 IF FIRE IN MAIN CONTROL ROOM, CABLE SPREADING-ROOM OR COMPUTER ROOM, T}iEN OPEN THE FOLLOWING DRYWELL PNEUMATICS rSEND OPERAYOR TO SwCR3 VALVES BY DE-ENERGlZING THEM:

2R23-SOO3 AT LOCATION VALVE 130TETl4 TO OPERATE BRKRS DE-ENERGlZE AT TO TRIP RBCCW PUMPS M7 2P70-F00lA 2R25-S00L BRKR 35 L 2P42-COOIA ANDIC ) 2P70-F004 2R25-S.064,BRKR 6 g

2PTO-F066 2R25-5064 BRKR 6 SE D OP A T LOCA ION3 p' 2P70-F005 2R25-5065,BRKR 23 2P70-F067 2R25-5065.BRKR 23 DRYWELL PNEUMATIC SUPPLY PRESSURE FROM 2PTO-Pi-NOOp f

/

FLRE 2 g5 DRYwELL Jf- TES

/

PNEUMATIC SUPPLY ABOVE TO Pf G N_0 h

/ '

I SEND OPERATOR WITH A THERMOMETER TO MONITOR FUEL POOL TEMP AND WITIATE FUEL POOL COOLING #F s

['[

g REOUIRED %

s CAU 11 ) s ISEND OPERATOR TO WCC 2R24-SOO' N A DN H

^' ' '

^'vERFFr Od hi? ES"Y0Ett R7 MONITOR FUEL POOL COOLING SYSTEM OPERATION.

PNEUMATIC COMPRESSORS q 2PTO-COQA AND 8 j HAS gg NOTIFICATION g4 BEEN RECElVED OR DO LARMS INDICATE A FIRE IN CRD CORNER 00 YES

\

ISEND OPERATOR TO LOCATIOM I!2TCTl2 TO DETERMINE f f i CONTROL AR HEADER PRESSURE f*(#

l ( FROM 2P52-Pi-R308 g,

~

i l -

t r ,

l NO CONTROL N7 AIR HEADER

PRESSURE ABOVE TO PSIC L J

% YES

\

j flF REQUIRED SEND OPERATOR 3 l TO YARD TO PLANT SERVICE o

!ATER VALVE PIT TO DETERMINE T

i. POSITION OF (PSW T/8 ISOL)

L VALVES 2P41-F316 A, 8, C, D j L

* ~. & FT '

l

\

L 1 b .

A .. 1 ARL QQ NO LANT SERVf ; -

ATER (P1W T/p ISOL ; c. _ ,

ISOLATION VAJES 2P41-F316A, 8, C, D '

YES OPEN , ,

4 E

\ '

NOTE 2i l 8" "

2R23YOO3A L A O '] IF A LOSS OF CONTROL AIR HAS CCIT#D, O THCtd ISGi/ATC 130TET14 TO OPERATE BRKRS TO TRIP AIR COMPRESSOR J3 %

- THE FOLLOWING -fGE PROTECTION SPRFALERS IF NO FIRE EXISTS W THEIR ' SPRINKLED AREAS. '

2P56-COOIA "

c '-

(NO1c 2e g "

DT ,

AREAS .,lSOL ATON VALVE,

!!EACTOR FEED PUMP A 2U43-Fi 17 ? T ll2 TAT 19 CSEND OPERATOR TO SwuR 3

~

r:EACTOR' FEED PUMP B

~ ' '

130TY l4' Y CNR KRS 6 f,.ONDITIONEREACTOR FEED PUMP OIL TO Tree AIR COMPRESSORS ,

2P58< 00e A m K J (NOTE 24 '

MYDROGEN SEAL Oil STSTEM 2U43-F0iS AT ll2TITl9 f5END OPERATOR TO LOCATIOR MAIN TURBINE Olt RE.5ERVrfR s '

2Z43-Flot' AT ll2TH Tl3 Il2TFTI3 TO DCTERMINC

. OPERASILITY STATUS OF ,

g3 m i i '

(THE ' UNITS i AIR COMPRfitSORSj l (NOTFY OPERATOR AT L&;ATION3 h ^

If2TFT13 TO DETERhirE -

UH1T l CONTROL AIFl.

HEADER PRESSURE Fh0M

/~ 3 s L IPSI-PI-591,593 OR 595 J T l CONTR b '

NO AIR HEADER PRES $UR :

ABOVE TO PSIG AND AY I LNT I AIR COMPRES$NtS i N RATi # '

YES l.

I

SEND OPERATOR To L OCATION 13ORSRis TO DETERMihE INSTR 3

AIR /NITROCE.N LINE PRESS FROM 2P5r-PI-NOOS j INST AIR / YES NITROGEN LINE PRESS ABOVE TO PSiG g 4

.s

, s

'4 6END OPERATOR TO LOOATIO) 130TET23 PANEL 2N2f-POOtA TO VERIFY OR OPEh COND , ['[3 DEMIN BYPASS VALVE 2t(b-FON

( (SYS SYPASS -VALVC j i h

W s

r ,

NO

---1 IS SPDS OPERATIONAL AND MANNED

>I L J K YES .

\

I SEND GPERATOR TO '

LOCATION 83ORHR2r TO DETERWii4E THE POSITIOb OF VALVES 2Dil-F050 h3 g AND 2Dil-FOS 2 y ARE N0 NO y,tygj F^8 2D C OR 2Dil-FOS 2 AUTO

-F050 b3 1 CLOSED YES IS DRYWELL YES t/3 PRESSURE ABOVE 1.63 PSIG ww-m- .

NO : .- I b

/

F SEND OPERATOR TO 7

'*"^ N SBCN NB 2T46 NOOIA TO DEPRESS SYSTEM g RESET PUSHBUTTON j NOTE 2 i CROUP 2 ISOLATIONS LOC T S N TY M ALL JUWPER BETWEEN TERWfNAL M{

ONLY VALVES NORMALLY OPEN AND N LINES GREATER THAN Tas-as AND T83-16 N 4 W. DIAM. AND OUTSIDE THE DRfwELL ARE LISTED HERE.

q SBGT CAB 2T46-DoctA > A COMPLETE LIST IS AVAILABLE WHEN TOU ENTER THE END PATH MANUAL.

DID 74 VALVE LOCATION DESCRPTION S8GT FAN 2T46-DOOtA START YES{l 2G11-FOl9 87RFR21 DW EQUlPMENT l Syyp py;jp i DISCHARGE

'~

(140TFY OPERATOR 185RAR?3 TO GOAT TOLOCAT%

CAB '

gy 2746-D0018 ON SBCT FAN TO .I Q

DISCHARGE NSTALL JUWPER BETWEEN 2Cll-F003 120RERt9 DW FLOOR DRAW QERWINALS T82-3 AND T82-M s SUMP PUMP y

rhoTFY 185RAR23 OPOLATOR AT CAS 2T46-DO AT LOCAT@OtB yb , 2Gil-F004 120RERt9 DW FLOOR DRAW AT S8CT FAN TO WSTALL JuuPER SUMP PUMP BETWEEN TERWWALS TB3-ts '

l

/ DISCHARGE VALVE j (AND T83-16 TO START FAN) p GROUP S ISOLATIONS PRi l / pg3g.FOO4 F 158RHR19 RWCU OUTBOARD i

VERIFY OR CLOSE I4- ISOLATION GROUP 2 ANO 5 ISOLATION VALVES j l t NOTE 2 4 SEND OPERATOR TO LOCATION OR w SU LY PRESSURE FROM 2PTO-Pi-NOO DRY ELL YES .

PNEUMATIC SUPPLY i* ABOVE TO PStG V

V

-% D:AcT -

RE TOR YESI PRESSURE BE CAUTION 7 DOERMINED L 4- DO NOT OPERATE SAFETY RELIEF VALVES MANUALLY !F NO SUPPRESSION POOL LEVEL IS LESS THAN 58 INCHES.

/

I /

I / I 7 g5 R5.[ ACTOR PRESSURETRND]

BEING AUTOMATICALLY NO /

4 /

AtNTAINED ABOVE 850 PSI AND BEgw 340 PSIG y /

YES 8 /

d /

/

/ m

/DN PANEL 2C82-POOi AT LOCATIOrli

/

lDORAR)6 PLACE MANUAL BLOWDOWN] FIRE 26

[h/

VALVE 282t-FO(30. F AND C EMERGENCY 1 l CONTROL TRANSFER SwlTCH TO j / IF FIRE IN MAIN CONT 60L ROOM, CABLE SPREADING ROOM OR L EMERCENCY (EMERC) POSITION j / COMPUTER ROOM l r BRKR 10 ON 2R2$ SOO2 AND IF REQUIRED TO TRIP HPCIT FAT PANEL 2C82-POOI OPtRATE7 uANuAL BLOWDOwH VALVES / /f .'

2OFOt3D. F OR C AS REOlme TO MAINTAN REACTOR PRESSURE !

( BO.Ow 040 PSIC \

'N CAU T J \

t SENO DPERATOR TO 7 LOCATION 13ORFR23 TO VERO OR CLOSE SCRAM DISCH VOLUME (VENT) ISOLATION l MSiv NSURE YES 35B )

REOUIRED BY A PREVIOUS SEND OPERATOR TO 7 TEP ON THIS FLOW LOCATION DORHRIS TO VERFY PATH 7g OR CLOSE SCRAM DISCH

%m NO

. VOLUME (VENT) ISOLATION VALVE 2Cff-FO35A J g

SEND OPERATOR TO 7 m

LOCA110N 8TRBRt5 TO VERFY OR CLOSE SCRAM DtSCH VOLUME (DRAIPO ISOLATION VAtVE 2 Cit-FO3T j

/

CT NOTIFY ON CALL HNP WATER LEVEL NO MANAGEMENT AND l ELOW +go ES SYSTEM LOAD DISPATCHER

, K7 l YES NOTIFY L AB FOR POST

^M OtNE AM E l T REQUIRED SEND OPERATORl AND OF P TO YARD TO PLANT SERVICE s CREATER THAN 15 %

'!ATER VALVE PIT TO DETERW4NE A7 J POSITION OF (PSW T/B ISOL) r

( V ALVES 2P41-F366A, B, C, D J 00 TO END PATH MANUAL 45. SECTION 450 ARE t ROCEDWE 45.450 j g7 ANT SERVICL

r. NO ATER (PSw T/B iSOL

. - ISOLATION VALVES 4jQ 2P4f-F3tGA. B. C. D TE 1

\o/

f'T]

SEND OPERATOR 70 l 13ORFR24 TO %

1LOCATI HPCIVAL E4-FOu j LOCATSO NRR24 6

NCli [VE 4 -FO I J

AT PANEL 2C82 POOi AT LOCATIO) w eO E -

CAUTION 8 I

ueJ - '~# F VALVES DO NOT OPERATE FROM THE REMOTE SHUTDOWN

" PANELS, OPERATE THEM LOCALLY.

AT PANEL 2Ca2-Pool AT LOCATM ,

GE Y R TRA FER h I'E E Stsuf50SPTR'"'"'

x CAu 8 ;

HAS O OTIFICATION BE NO RECOVED OR DO ALARMS NDICATE A FIRE IN CIC R YES ,

NO RCIC S AVAILABLE YES F FIRE 24 (FIRE 24 \ IF FIRE IN MAIN CONTROL ROOM CABLE SPREADLNG-ROOM OR 1 COMPUTER ROOM.THEN SEND AN OPERATOR TO THE 83 C A S RT fN l., TORUS ROOM TO ASSIST IN PERFORMING THE FOLLOWING STEPS TO START RCIC ILCAT RCIC BAR COND VAC %

PUWP AND CONDENSATE PUMP; f. '-

OPEN BRKR 14 ON 2R25-S001 R10R TO STARTING RCiC VERIFY OR MANUALLY OPEN THE ROC ACUUM BREAKERS h SOhT4 ON 1ATPANEL2C82-Pool 2E51-FOIO VAL j

VALVE 2ESI-F104 BRKR LOCATION 2R24-S0!!

2R24-Sole, COMPT COMPTITB 15A VALVE LOCATION 122RBRl9 AT PANEL 2C82-POOI 2ESt-F105 122RBR19 5 M6 ACE THE ROC TUR8 FLOW CONTROL AND TURBlNE TRlP AND I PowYO.sNAA$E V LVES 2E51-F012 AND 2E51-FOl3 #

7 ae HROTTLE VALVE TRANSFER SWITCHES TO EMERG ON 2C82-P001 OPEN BRKR 12 ON 2R25-S001TO REMOVE POWER TO THE GOVENOR AND ALLOW MANUAL RESTART AT 2C82-P00L THIS ALSO AT PAtEL 2C82-POOf Cf.-CNERGlZES THE RCtC TACHOMETER. CONTROL RCIC SPEED (0h BY OBSERVING RCIC FLOW I VERIFY OR OPEN RCIC LUBE Olt COOLING VALVE 2E51-F046 y i V RI STEAM SUPPLY VALVES 2E51-FOOT AND 2E56-FOO8j AT PANEL 2C82-POOISET l R

CONTROLLER TO MS Mh iRCIC FLOW MANUAL WITH OEMAND SET FOR 300 CPM J

~

I

bt#T FFE 21 IF FIRE IN MAIN CONTROL ROOM, CABLE SPREADING ROOM OR COMPUTER ROOM,THEN

-VERIFY RUNN!NG OR START RCIC PUMP ROOM COOLER.

3 PERFORM THE FOLLOWING TO START 2T41-8004A AT MCC

~

T BN IP %h IPLACE AND THROTTLE VALVE SWITCH TO OPEN J

-OPEN BRKR 4C

-OPEN LINKS 4C(PI) 4C(2), 4C(NI), 4 C(3R), 4C(iO), 4C(II)

AND 4C(3G)IN THd TOP COMPT OF FRAME 4 RCthkA TO TU NE [Vi 6 -JUMPER THE INTERNAL SIDE OF TERM!NALS 4C-PI AND 4C-2 VALVE 2E51-F045 AND l# ^

fBOTHON SAMC 1 CH

/

IN THE TOP COMPT OF FRAME 4C

-CLOSE BRKR 4C RCIC YES /

START SUCCESSFUL ,

NOTE 26 NG .

TO' LOCALLY START THE HPCI OR RCIC COOLERS PERFORM NO /

/ THE FOLLOWING

l. INSTALL THE JUMPER INDICATED FOR EACH CCOLER TO BE j STARTED

/ COOLER MCC/ BREAKER LOCATION JUMPER f 2T41-8004A 2R24-S0ll/FR4C 30RFR14 4CITO 4C2 rFIRE ?l SEND OPERATOR g_"-/ ' 2T41-8004B 2T41-B005A 2T41-B005B 2R24-S0!2/FR2C 2R24-50ll/FR7C 2R24-S012/FRSC

.30RFR24 30RFRl4 130RFR24 2CITO 2C2 TClTO TC2 SCITO SC2 TO VERIFY OR START RCIC ROOW 2. VERIFY OR OPEN THE PLANT SERVICE WATER SUPPLY COOLER;' s VALVE FOR EACH COOLER STARTED esoyc as q FAT PANEL 2C82-POOL ADJUST 7 N / COOLER PWS SUPPLY VALVE LOCATION RCIC SPEED OR TEST SYPASS N #

% / 2T41-8004A 2P41-F040A 87RARl4 VALVE POSITION TO CONTROL 70 7 2T41-80048 2P41-F040B 87RARl4 L RCIC FLOW N / 2T41-8005A 2P41-FCS A 87RGR25 2T41-B0058 2P41-F035B 87RGR25

[s cAU i4;

,s I AT PANEL 2C82-POOI 3\ / N OPERATE RCIC TEST SYPASS \ f A

^ \

L W V V? E5-O#* N7 /

t AS REQUIRED g/ FIRE 26 r r,RE 2s @ CAu os g/g\ A IF FIRE IN MAIN CONTROL ROOM CABLE SPREADING- ROOM OR

\ COMPUTER ROOM RESTORE AND MANTAN REACTOR WATER LEVEL TO D'I i

[i[7 g

\

s \

\

BRKR 10 ON S002 2R25AND IF REQUldED TO TRIP HPCITH l ABOVE O WCHES AND SELOW

( +50 INCHES '

g \

\

f CAU 23)\ g

" b \ \

CAN ~-

REACTOR WATER YE'S' ' A ( \ N CAUTION 14 LEVEL BE MAINTAINED g BOVE O WCH t j , USE A HAND HELD TACHOMETER, OR EOUIVALENT, TO CONTROL HPCI OR RCIC MINIMUM SPEED ABOVE 2250 RPM.

i \

\

' \

\ \

g CAUTION 13 g

g yIF HPCIESSION OR RCIC SUCTION AUTOMATICALLY TRANSFERS T POOL, VERIFY OR OPEN MINNUM FLOW REQRC

\

\ -.

CAUTION 23 IF INDICATIONS OR VERBAL REPORTS INDICATE THAT THE FOLLOWING SUPPRESSION POOL OR CST WATER LEVELS EXIST THEN VERIFY OR TRANSFER HPQ OR ROC SUCTION FROM THE CST TO THE SUPPRESSION POOL.

. LEVEL COMPONENT SUPP POOL ABOVE 152 IN HPCI AND ROC CST BELOW 0.5 FT HPQ AND ROC

6&

W

/ i s YES RECOvco oR 00 ALARwSN NO , ;

INDICATE A FIRE IN RHR#

N CORE SPRAY SE /

v N b.'

CAUTION 8

/

ON PANEL 2C82-POOI AT l[,, -

IF VALVES 00 NOT OPERATE FROM THE REMOTE SHUTDOWN AM.

LOCAT4ON I3ORAR16 PLACE LL RHR SYSTEM EMERGENCY d ONTROL TRANSFER SwlTCHES I O DaERGENCY (EMERtp POSITION

\ CAu 8 J

/ MISC 7 IV IF S 2OI-FOO6A,8.C AND D S

7 AT PANEL 2C82-POOi VERfY OR OPEN 12Cl-F0478![9 VALVES 2Ol-FOO4B 2Ol-FOO38 i l AND 2Ol-F0288 )

OR CLOSE VALVES 20-F0488 I AT PANELlQ2C82-POOIVERFih -

20-FOIT8 AND 20-FOws J T PANEL 2C82-POOi VERFY t20-F0278 OR CLOSE VALVES ANO 20-rO248; j

'kQ SEND OPERATOR TO 1 !

LOCATION 87RLR21 TO ,[

I 2 RTE 4o"Si !En"FO% '

AT PANEL-2C82-POOf START 19 IRNR 20-cOOe SERviCr A

OR 2a-cOOo 3WATER euweS CAu 3 ; 's CAUTION 3

~s MAS L,,9

' s,' VERIFY DIESEL GENERATOR LOADING DOES NOT EXCEED THE FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER YES OmER RHR , TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE SERYlCE WATER PUMP a LOCATED ON PANEL R43-P00l!N EACH DIESEL GENERATOR ROOM.

STARTED RATINGS (AMPERES)

N DIESEL CONTINUOUS 7 DAY (168 HOUR).

N 25 ON PANEL 2C82-POOIAT l JC 490 560 gh tj 490 560 I LOCATION (3ORARt6 START RHR PUMP 20-COO 28 2A 2C 490 560 (FIRE 25 \ *THE HIGHER T DAY RATING IS BASED UPON A YEARLY 3 \ ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE 2c ROOM IN DIESEL BLDG

-S 73 b g\ A CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR WITH A LOAD OF 490 TO 560 AMPERES IS ALLOWED.

( ITS N swoR's bE #TSR R P P Q 00 8 N

, g s

i HAS YES

P I* O-Co a FIRE 25 STARTED IF FIRE IN MAIN CONTROL ROOM CABLE SPREADING-ROOM OR

NO COMPUTER ROOM. THEN PRIOR YO STARTING RHR PUMP B j (2 Ell-CCO28) OPEN BRKR 12 ON 2R25-S102 WHICH IS INSIDE OF COMPT 228 0F 2R24-S012 TO FAIL OPEN 2 Ell-F065B

W

[FlRE 29 \.

ON PANEL 2C82-POOIAT 7 FIRE 29 LOCATION DORAR$ OPEN

'NR IF FIRE IN MAIN CONTROL ROOM. CABLE SPREADING-ROOM OR IRHRSYSTEM "Y""O CONTAINMENT

's

COMPUTER ROOM,THEN

-VERIFY RUNNING OR START DivlSION 11 RHR AND CORE SPRAY PUMP ROOM COOLER 2T41-80028. PERFORM THE FOLLOW 1NG AT PANEL 2C62-POOL q 's '

TO START:

IR TR AT EV -OPEN BKR IN 2R24-S012 COMPT IC, j

-OPEN LINKS IC(PI). IC(2), IC(NI), IC(3R), IC(10). IC(ll) AND IC(3G).

OCAT ON O ARl6 ONTOR -JUMPER THE INTERNAL SIDE OF lERMINALS IC(PI) AND IC(2)IN i SUPPRESSION POOL LEVEL M THE TOP COMPT OF FRAME IC. I AND TEMPERATURE J -CLOSE BKR IC IN 2R25-S0t2 i D AG SEND OPERATOR EVAT N O WONITOR RHR PUMP OPERATg NOTIFY OPERATOR IN SE' DIAO ST ELEVATION TO A)9

-OPEN BKR 15 ON 2R25-S06S TO ENSURE COOLING TO RHR ONITOR RHRSw TO RHR DP ON 2D-DP-NOO3B ;

YES RHRSw TO P9 RHR DP BEING MAINTAINED ABOVE 20 PSID NO I SEND OPERATOR TO WCC' 2R24-SOT 2 AT LOCATION DORFR24 TO TRIP BRKR FOR RHR VALVE 2D-F0689; I

AT PANEL 2C82-POOITMtOTTLE' 2 Ell-F0248 AS REOUIRED TO ESTABLISH DESIRED RHR FLOW j l

(SEND OPERATOR TO LOCATION 3 IO6RLR24 TO OPERATE RHR VALVE 2D-F0688 AS REQUIRED (J$

TO ESTABLISH 20 PSD RHRSW TO RHR J J

SEND OPERATOR TO 7 LOCATION 83ORFR23 TO VERIFY' OR CLOSE SCRAM DISCH b VOLUME WENT) ISOLATION "

VALVE 2CII-FO358 )

SEND OPERATOR TO 3 -

LOCATION DORHRI5 TO VERFY OR CLOSE SCRAM DISCH b IVALVE2 Cit-F035A VOLUME (VENT) ISOLATION SEND OPERATOR TO

)

, e 7

LOCATION STRBR15 TO VERFY o OR CLOSE SCRAM DISCH lb 1 VALVE 2Cil-F03T VOLUME (DRAIN) ISOLATION

)

NOTIFY ON CALL HNP fb IMANAGEMENTANDSYSTEM LOAD DISPATCHER NOTIFY LAB FOR POST SCRAM IODINE SAMPLE IANDOF POWER CHANGE F OREATER THAN 15% j MA L 5 C4 453 PROCEDURE 45.453 j 453

ATTACHMENT 6

'N UNIT 2

<, END PATH MANUAL 45.453

.)

~

.1.0 OBJECTIVE KEY AIDS The objective of this End Path Procedure is to allow the operator [ END to maintain the Reactor and plant in a safe condition while taking l PATH the plant to Cold Shutdown OR until control from the Control Room l PROCEDURE' is resumed.

l 45.453 1

2.0 ENTRY CONDITIONS -

l 2.1 1 The following conditions may exist when entering this procedure: l I

2.1.1 Reactor scram has occurred. l l

2.1.2 Control Room evacuation was required. -

l l

2.1.3 MSIV's are closed.

- l l

2.1.4 HPCI, RCIC, or CONDENSATE System is being'used for level l control.

[

2.1.5 l There may be a fire in either RHR/ CORE SPRAY Diagonals. l 1

3.0 OPERATOR ACTIONS 1 l

'a l NOTE - For return to Control Room Enter (GOP) 3460-0PS-181-2S l 1

3.1 Restore and maintain RPV water level between zero and +50 inches. l

.I I

3.2 If RPV water level cannot be maintained greater than zero inches, l FLOWCHART return to the flowchart. l 45

[

3.3 I Monitor containment ' control parameters and execute concurrently with lCONTAINMEN~

this procedure.

I CONTROL l PROCEDURE THE SUPPRESSION POOL TEMPERATURE CONTROL SECTION OF THE CONTAINMENTl CONTROL PROCEDURE IS THE ONLY PORTION OF CONTAINMENT CONTROL THAT l CAN BE EXECUTED.

]

l I

3.4 If Group 1, '2, 3, 4 or 5 isolation signal has been received, enter Contingency 45.87 to verify isolations. lCONTINGENC' IPROCEDURE l 45.87 I

3.5 If. condensate is available, maintain reactor pressure below 600 psig.l l

THE CONDENSATE SYSTEM IS NOT AVAILABLE DUE TO A LOSS OF OFF-SITE l POWER.

I

~_

A6-1 Rev. A

x ATTACHMiNT 6 (Cont'd)

KEY AIDS

\

NOTE - If SRV f ails to function as required, except for pressure. l AOP setpoints requirements, and cause is not known, then report l34AB-0PS-analysis on Attachment 2 of HOP 34AB-0PS-007-25 -

l 007-2S I

THE SRV'S WORK NORMALLY l l

CAUTION - Use SRV's only when suppression pool water level is l above 58 inches. l 1

THE SUPPRESSION POOL IS NEAR NORMAL. l 1

CAUTIE - Use sequence, G, F D for SRV operation l 1

WRITE DOWN WHICH SRV IS OPENED EACH TIME. l l

CAUTION - SRV Position indications are not direct -

l I

THE SRV'S FUNCTION NORMALLY. HOWEVER, REACTOR PRESSURE l DECREASE (RAPID DECREASE) INDICATES STUCK OPEN SRV. [

3.5.1 l If manual operation of SRV's is required, verify or place l Emergency Control Transfer Switch, for SRV's G, F and D, l to the Emergency Position. l

- 1 THIS WAS DONE ON FLOWCHART. l 1

3.5.2 If RPV pressure cannot be maintained less than required by l manual ' operation of the SRV's enter the Alternate Pressure l Control Contingency 45.83. l I.

RPV PRESSURE CAN BE CONTROLLED WITH SRV'S. l l

3.5.3 If control air header pressure and nitrogen pressure is less l than 55 psig and decreasing, open one SRV until the reactor i is depressurized.

l 1

THE PRESSURE IS ABOVE 55 PSIG DUE TO NITROGEN BACKUP. l 3.6 If any diesel generation is not running and is required to be '

running, enter Generic System Recovery procedure 45.71 to recover l the diesel. l l

THE DIESEL' GENERATORS WERE PLACED IN SERVICE ON FLOWCHART. l 1

3.7 Investigate outside conditions for radiation levels and monitor l site releases. l l

/

A6-2 Rev. A

% ATTACHMENT 6 (Cont'd)

KEY AIDS

'1 1 3.8 If of f site release rates' e'xceed 3 ci/sec, isolate all primary 1 .

systems that are discharging into areas outside the primary and l secondary containments except systems required to shut down the l reactor or assure adequate core cooling. l l

1 l

I 3.9 If of fsite release rates exceeds 91 ci/sec and primary system is l discharging into an area outside the primary and secondary 1 containments, enter the Emergency Depressurization Contingency 45.81. l 1

I i

l l

3.10 Establish a reactor cooldown rate less than 100* per hour using lCONTINGENC' SRV's or The Alternate Pressure Control Contingency Procedure l GENCY No. 45.83.

l PROCEDURE l '45.83 THE SRV'S AND RCIC ARE USED FOR PRESSURE CONTROL. l I

NOTE - Interpret the " Temperature near reference leg vertical run" l Recirc.

as reactor coolant temperature in step 3.10. l Saturation

' l Limit

_/ l l

1 3.10.1 Use reactor saturation limit curve to record reactor coolant l Attachment temperature and plot reactor cooldown rate on Attachment 1. ,l 1 l

l

,- ; , i 1

3.11 Verify main transformer PCB's open, then manually open disconnect l CAUTION switch 179756.

l Wear l Rubber USE RUBBER GLOVES AND B00TS' l Gloves ,

l & Boots i

3.12 If there is or has been a fire, refer to the Fire Actions and l Fire and Instructions Table or enter procedure 45.155 to take l Actions appropriate action.

l & Instr.

l Table l Procedure

.l 45-155 i

NOTE - While performing GSR procedure, maintain steady reactor l cooldown rate. [

I SRV'S AND RCIC PROVIDE C00LDOWN CONTROL l l

A6-3 Rev. A

~s ATTACHMENT 6 (Cont'd)

KEY AIDS

'~} I 3.13 If any of the following' electrical systems are de-energized, enter l GSR the GSR section procedure no. 45.70 for Electrical System Recovery. (Procedure plant service water system. -

[ 45.70 System l l

4160 VAC BUS 2E l

4160 VAC BUS 2F

[

4160 VAC BUS 2G l

600 VAC BUS 2C l

600 VAC BUS 20 - -

l VITAL AC BUS l

RPS BUS 2A RPS BUS 28 l l

ESSENTIAL CABINET 2A l

ESSENTIAL CABINET 28 l

INSTRUMENT BUS 2A -

l INSTRUMENT BUS 2B l

125/250 VDC BUS 2A l '

125/250 VDC BUS 2B

[

l l

I I

3.14 If any Plant Service Water Isolation Valves listed are closed, l GSR g enter the GSR section in this manual procedure 45.60 to recover

) the plant service water system. l l Procedure 45.60

-2P41-F316A l

-2P41-F3168 l

-2P41 -F316C l

-2P41-F3160 l,

I WHEN ADEQUATE AC POWER IS AVAILABLE, EXECUTE THIS STEP.

[

.- . I 3.15 If reactor building chilled water compressor 2P64-B006A or B l GSR is not operating, en.ter GSR procedure 45.69 to restore ,drywell l 45.69 cooling.

1 I

DRYWELL COOLING CANNOT BE RESTORED UNTIL ADEQUATE AC POWER IS [

RESTORED. ,,

l I

3.16 If control Air Leader pressure (indicated on 2P52-PI-R308 at l GSR location ll2TGT12 is less than 70 psig, enter GSR procedure 45.62 l 45.62 to recover Service and Instrument Air System. [

l THE SERVICE AND INSTRUMENT AIR SYSTEM CANNOT BE RESTORED UNTIL l OFF-SITE' POWER IS RESTORED.

[

t 3.17 If. the RBCCW pumps are operating, go to step 3.18. l l

RBCCW WILL NOT BE OPERATING..

l

~

l l

A6-4 Rev. A

(

- - @dr3 ATTACHMENT 6 (Cont'd)

KEY AIDS

] 3.17.1 Enter GSR procedure'45.61 to recover RBCCW. l l GSR l 45.61 N/A -

l l

1 3.17.2 If fuel pool temperature increases to 105*F, enter GSR GSR

[

procedure 45.75 to recover fuel pool cooling. l 45.75 I

WHEN ADEQUATE AC POWER IS AVAILABLE. l l

l 3.18 If the CRD system is not operating, enter GSR procedure 45.63 to l GSR recover the CRD system. 45.63 l

I WHEN ADEQUATE AC POWER IS AVAILABLE. l l

3.19 If the Condensate System is not oparating, enter go to step 3.20.- l 1

THE CONDENSATE SYSTEM IS NOT OPERATING. l l

1 3.19.1 When reactor pressure is less than 320 psig, send an [ R0P operator to manipulate the breaker, per R0P 45.145, to l 45.145 trip the remaining condensate booster pump. l e)

~~ THE CONDENSATE B0OSTER PUMP IS NOT RUNNING BECAUSE OF l

l LOSS OF 0FF-SITE POWER.

[

PUMP l BUS LOCATION l 2N21-C0024 4160V BUS D (2R22-SOU4) 130TGT23 l, 2N21-C002B 4160V BUS 0 (2R22-5004) 130TGT23

~

l 2N21-C002C 4160V BUS (2R22-S003) 130THT23 l 1

I 3.19.1.1 On local pa,nel 2H21-P242, location 112TFT22, place. l auxiliary lube oil switch for condensate booster pumps l to HAND.

[

N/A .

I I

3.19.2 When the remaining condensate booster pump is tripped, l R0P select one of the two. remaining condensate pumps for shutdown l 45.145 and send an operator to manipulate the breaker, per R0P l 45.145, to trip the selected pump. l I

N/A l

l 1

' PUMP BUS LOCATION l 3

2N21-C001A 4160V BUS D (2R22-S004) 130TGT23 2N21 -C001 B l 4160V BUS D (2R22-S004) 130TGT23 l 2N21 -C001 C 4160V BUS C (2R22-S003) 130THT23 l A6-5 l Rev. A s

ATTACHMENT 6 (Cont'd)

KEY AIDS

-] .

I

' 3.20 When RPV pressure is less than 320 psig, start the Core Spray l R0P

. System per R0P for level control.

I 45.145 I e f l l l l

CAUTION - Do not depressurize RPV below 128 psig unless motor i driven pumps sufficient to maintain level are running l and available for injection. l y

l l

I I

3.21 When RPV pressure is less than 135 psig, start RHR in shutdown l R0P cooling per R0P 45.142.

I 45.142

. I I

I 3.21.1 i If RHR cannot be placed in Shutdown Cooling mode, enter l Contingency the Alternate Shutdown Cooling procedure in the Contingency l 45.84 Section, procedure no. 45.84.

l 1

RHR SHUTDOWN COOLING FUNCTIONS NORMALLY. l 3.22 When RPV pressure is less than 128 psig, verify closed or close l R0P HPCI steam line isolation valve 2E41-F003, per R0P 45.146. l 45.146 I

i 1

BREAKER LOCATION i VALVE LOCATION l 2R24-S022, FRAME 28~ 130RH R19 l l

l l

3.22.1 "If the torus area is inaccessible, close 2E41-F003 by 1 -

installing jumpers listed in Attachment 2. (Attachment l 2 I

I I

I 3.23 When RPV pressure is less than 75 psig, verify or- close 2E51-F007 l and F008 'f rom remote shutdown panel 2C82-P001.

l l

1 1

I 3.24 When RPV. pressure is less than 25 psig, raise water level to +60 l

,_ inches.

l A6-6 Rev. A

OVERSIZE DOCUMENT

. PAGE PULLED l SEE APERTURE CARDS .

NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS

l APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-8989 i

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ML20213G684

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