ML20213G684
| 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: |
| References | |
| 0749C, 749C, SL-1283, TAC-61626, TAC-61627, NUDOCS 8611180264 | |
| Download: ML20213G684 (50) | |
Text
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 L. T. G ucwa f/vi wattim eW Inc cycem 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 8611180264 861114 i*
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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 circuits?
I 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 These two exemption requests are similar to the exemption already granted 4
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 minimal lighting is necessary to traverse between buildings and to close i
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 2
located within 20 ft of these valves is approximately 69,000 BTU /ft,
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 west side.
The circuit located in panel 2H21-Pl73 should be adequately i
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 to the water curtain separation criteria.
I 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 suppression system.
Each pump motor has two spray nozzles rated at 135'F, I
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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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
s l
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' L'
- 15 minutes from the time the PE0 is notified until the N0A is
~
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
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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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3
- 30 minutes following a reactor scram.(a)
- 30 minutes following a reactor scram.(a) i t
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The limiting factor for needing the diesel-generators is the RCIC room coolers.
i 0745C E-8 09/10/86 i
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LOCATION Path 45. Unit 2/E-3 8T41 60004-0 f9M 89.A 2
- 9 IT47-eOOe64 19W 2
ue acscT cmAT moos rea w rouowcrua.
Purpose of Jumper:
Start DW Coolers n n-6 *SA4 n n-ooosen 64 Af sacc et24-SdEZ. AT LOCAfsose Doaseto2.96TAtt TW rCLLouvC
\\
.AArptse
[g TM__
70___
Tf"RWAL ff47-6007'A-2 ssM mA2
. EUMj '. J,~_
_ '_ m TT47-60078-2 ret l
Required Tools:
I ue ac:rf emn eacuois ran Tic
' n%"'.','***
I i
i 1.' Standard Screwdriver I
- 2. Jumpers (Alligator. Clips)
I el AT TM* rettovec.t,oCAL.TTANTUts.
ecTAu. 74 roue c.a cats.
I
- 3. F ash ight la toCAT~ w To w g
4, l
nu.
no rna 3
800$A-2 1
s 5
rT 47,.
coprnot 8
3 300 0-2 FRAME 18
)
Panel-600/280 VAC HCC 1R24-SD12 M2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 [18 19 20 l
l.
I-f 4
3 i
a 4..=
.=-
e s
n a:
l Location 130RFR02 I
Compartment Frame 18. Too Como.
y a
A/
i b
/
. J t w E x.s i
Jj;!
- i g
fg3 C
l
i WT
-> i c.
f) ntsfAAf DaTwtLL COOLot rnoutB As FOLLows.
a.
es an sons.Arca AvaAnurr
! t'. I e)n rue es4 ue ess, etActeTd 'I"'E"* ""'
SEND OPERATOR,l&C TECH)
Omnt COase systru suo man 3R ELECTRICIAN TO RESTART DRYWELL CHA.I.ERS AND
[
E W aj'Eg" M5"&^'*
COOLING FANS rams.
a.r tw rm (OCA ovenner surcw s LNOTE 16 A
CAU 3 )
es0PERaTrvt 04 esACCC3%etr. iKM PROCEID AS FOLLori to STAAf TK Derwat C00Les FAM5e of AT 6dCC M24-50s. AT LOCAfsow OO9eE3.ev5f ALL 18( FOLLowrc ru.
tc w to
'c-'t FLOWCHART /
gig'4^
J
."3 LOCATION Path 45. Unit 2/E-3 (747-8004A-6 f148 M'I (747-600e6 4 stes N
ye RCst? CRCLat egAKrJts roft 74.
, conc raus.
EUM Purpose of Jumper: Start DW Cooiers ad AT adCC st26-50t?. A7 LOCATOf.
DORP *m2 etSTALL T4 r0LLOweC
.AMrotse fa tm to 7%
EU2' i M-e
"^*
'EU'.*00$*i(E" _- h
~,
l Required Tools:
l
,a o.,,t', W = =>= as 'Ca x l
I
=5 nn-.00eA-2
""~
l 1.' Standard Screwdriver I
r w rcilo 40en. reartms.
I 2 Jumpers -(Alligator Cl.ips) l
'5ta te ' M ru a's petas-l
- 3. F1ashiight I
tocera n = u.
To m 8747 00W402 0
3 g
4*
l no. -2 l
l a00$A 00, 0
3 l
80096-2 c1-)
FRAME 19 Panel' 600/280 VAC MCC 1R24-S012 Y2 3
4 5
6' V,
7._8 9
10 11 12 13 1.4 15 ~16 17 18 19. 20 4
E f.
1 Location 130RFR02 Compartment Frame 19. Top Como. -
D W
A s
~
/
.j
/
A t.luMftr.s 8
If II0 e
C
t (6FiE-2s N
SEND OPERATOR rm a
, joNrER YEuYo* """' **
- START RCIC ROOM COOLER T ]%,y rEto'E"c'To" *ra"7 r"Noo# Plt'icC u oTE 2s /
j 4
(
, y,flc %, o,, y i m s <c-n n e *c-1 e
.aost e=R 4e FLOWCHART /
LOCATION Path 45/M7. Unit 9 mic es T3 LOCALLY START T){ iPO OR ROC CUoLERS PCRroRW TtC roLLoWNGe
' E lj @o " " " " " E^C" C * '" '
Purpose of Jumper: Start RCIC Coolers
- C e fe,w p m W A TM _ Jt M.Pm 4 --
Ot2/
rr = Dit" son"& ooarn24 ISIS's5
- 2. @,ggMay7,T 'Artn sterLr l
Required Tools:
- l em m m r.ts= y vir vr
[0CAmtf I
i ree ro4oA sTama l
- 1. Standard Screwdriver I
kvsoo44 5.".<oni US$"r*s i
- 2. Jumpers (Alligator Clips)
I W
a rT 4*sa arwma emca:s 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
)
.h r
. ~~-
7 Ei E
- ==. :..anu
=
=
mar a
w
=m:
=
-r
. m
=-
Location 130RFR14 Compartment Frame 4, Top Comp.
I lillllllllllllllllllb
+4 oem uns Pere Rne2 Il l I I I I l l l l l l l l l l l ! Ii'~
O f1MS x
m Gh M s
w II)0Il#hN !IIIII N Il+-
4c 8
A
REIOTE START OF RCIC ROO M COOLER
/g q E u5 l
A 500 s
Nun __
p_a f w__ l z z eis s
CABLE.SP/?EAD R O o rr7 ru ci
,,,m f')~~3 5
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i i
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~
,~ ro.sr.cr
'"' 4"
' fit b, b.e AREA s2m ru vym s
l "v s
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ent,,.ns ve.s 7 r e. t.
- e. i s vi.
pn
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3
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t 1
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-et co~ wr -- et
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ett -,ws-,
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tm n
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OPErl Ur4K l
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72 73 he
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point? cou7/!at ccuicn capsort co"ros <c pl c4-tute:ic:snt:
-~
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TO C fC U C. r v.*
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P4 t~iO 4C o LL w reic ruviWoorr s-A cooaa arcooso s
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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 3lE0-E0P-002-25 EORGIA POWER COMPANY HATCH NUCLEAR PLANT REVISION O
l sFlTE NOV I,1986 TIVE 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_
PERMISSIVE LIGHT g
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 PN E
2 AT LOCATION DORAR16 AND D-l
^""ed'Eu!E Of"ELERo$2Cr "#
l kEMOR SUPERVISOR SEND STA CNuNN$CAUsSNS BE b
^ '
EN gPANEL 2Ca2-POOIAND TSC;
- $1"TOYNN s
T FIRE 27
- YO" O
ER TO 3EP j
IF FIRE IN MAIN CONTROL ROOM, CABLE SPREADING-ROOM OR COMPUTULROOM AND IF MANUAL START OF DlESELS 2A OR 2C SENOR SN. -PERVISOR NOTIFY, 15 REQUIRED THf_N PROCEED AS FOLLOWS IN ADDITION I
TO DlESEL PROCEDURE 3450-R43-001-2S:
+ 6,9 STA TO INITIATE EMCROENCY CALL IN L1ST a
FOR DIESEL 2A ORSN$$fNTfkb",S
- OPEN BRKR 14 AT 2R25-S004 TO ISOLATE g3' REMOTE CIRCUITS j
- FLASH GENERATOR AFTER DIESEL IS RUNNING--BY O$ALNCATIOhS NRANT l
J PLACING LOCAL START SWITCH TO REMOTE o
27 g
- PLACE VOLTAGE REGULATOR IN AUTO BY OPENING l
I 7
SEND OPERATOR TO LOCATION LINK TAl-T IN 2R43-P00lA AND JUMPER TERMINALS OOTETO TO OC SwcR 2R22-SO66 g-TAl-8 AND TAl-9 U $N.S$nalhR $$
FOR DIESEL 2C L_
J 50TIFY OPERATOR AT LOCATION
- OPEN BRKR 14 AT 2R2S-S006 TO ISOLATE REMOTE CIRCUITS R 0 C Sw" 6f sPDS E
s
- FLASH GENERATOR AFTER DIESEL IS RUNNING BY Qg ga (PN 2H2 P248;
- PLACE VOLTAGE REGULATOR IN AUTO 8Y OPENING I
7 AT PANEL 2H21-PIT 3 LINK TAl-l IN 2R43-P00!C AND JUMPER TERMINALS AT LOCATION 13ORARis C *_
TAl-8 AND TAI-9 J
- ""e "RRE4^a"'"' ;
T
\\A/
e
A I
ON PANEL 2C82-POOf AT LOCATION 83ORAR66 PLACE NUCLEAR BOILER INSTRUMENT 'C$
SwlTCH TO EMERC POSITION AND MONITOR REACTOR PARAMETERS CAUTION 10 cAu lo A ' '
ALL AUTOMATIC PROTECTION TRIPS ARE REMOVED AND ALL i
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)
'CD POSITION.
AVAILABLE L
J l K YkA ARE 44-YOU HERE YES-PATH 18 FROM SPOS NOT[AND l
AV LE NO
/
CAN REACTOR POWER N0i EVEL SE DETERMIN L
J YES I
1
~.
PC Nh ARE 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 I REACTOR PRESS BELOW
[S hD T W INT A 3f BELOW IST*F 1090 PSIC THE HEAT C APACIT Y i--,,___-
JST *F TO 159+ *F 900 PSIG TEMPERATURE LIMIT ;
160 *F TO 169+ *F 600 PSIG 170 *F TO IT9+ *F 300' PSIG
( NOTE B q 180 *F TO 189+ *F 200 PSIC FSEND OPERATOR TO DCTERMsHEl ABOVE 190*F 13 5 PSIG OPERABE.fTY OF REACTOR WATER *pj LEVEL INSTR ON RACKS 2H2 MOO 4 AND PCO5 AT LOCATION g 158RERiT AND L58HER2 7
F J
^
i B
CAUTION 9 i
DIAG Df IF SPDS AND PROCESS COMPUTER ARE NOT AVAILABLE AND CAN NO REACTOR WATER FOR CONDITIONS SHOWN BELOW ACTUAL REACTOR VESSEL LEVEL 7
MAY BE BELOW THE LOWER IN$TRUMENT TAP. USE ANY 3
LEVEL SE DETERMINED AVAILABLE DRYWELL RTD.
L CAU9j~"-~~~-~~~~
DRYWELL INDICATED LEVEL YESE TEMPERATURE LEVEL INSTRUMENT LOCATION F
7 i"Df ABOVE 125'F BELOW 2821-N024A,8 158RER16
"^$
-107 IN 2821-NO3tA PS YES TEMPORARY O PERMANENT LOSS OF hNORm4AL AREA LICMTNG RACK 2H21-P004)
(
j ABOVE !25'F BELOW 2821-N025A,8 158RHR22
% NO
-107 IN (ON RPS 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 i
+
(
RPS i
%vQFIED ALARMS INDICATE RACK A FIRE ANYWH E%
NO
'N u
s
\\
's
'g N
FIRE I I AND SHIFT SUPERVISOR NOTIFY OPERATION N
SUPERVISOR ON SHIFT IF FIRE IN CONTAMINATED AREA, NOTIFf HEALTH PHYSICS TO RESPOND TO FIRE SCENE.
I,. NOTIFY 3 [5l SECURITY TO
.SO.UND, FIRE ALARM J
lMAKE FIRE ANNOUNCEMENT l' {
FROM ANY PAGE STATION d 3 TIMES l
1 CHIEF AND 2 WAY RADIOS DISPATCH FIRE BRIGADE Al WITH OUAlfFIED BRIGADE e
y IST NOTIFY UNIT I SHIFT dl A
T MAY ECT UNIT I SHUTDOWN j
85 Nl NO VERIFIED FIRE LOCATED IN REACTOR BLDC YES
\\
- 8/
F IF SMOKE IS OBSERVED IN 3 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 IPUMP HOUSE TO VERIFY OR SEND OPERATOR TO FIREl 6(
INDICATED FOR AREA INVOLVED:
START DIESEL FIRE PUMPS AREA ACTION cog 2AANDB J
DG SWGR ROOM 2E ISOLATE PUMPS 2Y52-C001A (2AD 1is gc SEND OPERATOR TO 4160V l 6\\
S R R22-S EN VA S
4 0 C*
eLoO OO RATE 2R43-F007E.2R43-F008A, BRKRS TO START MOTOR 2R43-F008C,2R43-F008E FIRE PUMP IX43-COOi
- CLOSE VALVES 2R43-F0070, 2R43-F0088,2R43-F008D IMAK UN ECKS OF FIRE PUMP OPERATION AND 2YS2-C00
( 0 OF DIESEL FUEL SUPPLY J
- 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)
START UP 1 l
- OPEN VALVES 2R43-F007A. 2R43-F007C 2R43-F008A AND 2R43-F008C YES AND OPERATION OF
- 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 DG 2C DAY TANK ROOM DE-ENERCl2E FUEL Olt TRANSFER PUMPS w
- - - --u m - - r
/
2YS2-C00lC (2CD AND 2YS2-Ci0lC (2C2)
\\
7 AT 2R24-SO25, FRAME 7F AND f
2R25-5027 FRAME 7F SEND OPERATOR TO DIESEL I
/
DG 2A BATTERY ROOM DE-ENERG!ZE PUMP 2Y52-C101A (2A2) AT
/
2R24-5027, FRAME 7E BLDG TO DETERMWE Fg Ho IF g/
PR l
DG 2C BATTERY ROOM DE-ENERG!ZE PUMP 2Y52-C10lC (2C2) AT t
J
! /
2R24-5027, FRAME 7F.
( FIRE 1
/
DG 2A ENGINE ROOM DE-ENERGlZE PUMPS 2YS2-C00!A (2AU HAS (32, / l AND 2YS2-C10lA (2A2), AT 2R24-SO25 ggy gTgF CA ION NO.
FRAME TE AND 2R24-5027, FRAME 7E' N
i v
R DO 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' P
g 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 OR COMPUTER ROOM THEN
~
s
-CLOSE DIESEL GENE'.RATOR 2A METER SHORTING LINKS IN s
PANEL 2R43-P00!A OR JUMPER TERMINALS TA2-4 TO TA2-5 r33
~
DIES S 2A,2C YESj TO TA2-6 TO TA2-7 IN PANEL 2R43-P00lA AND 18 STARTED AND RUNNING AT
-CLOSE DlESEL GENERATOR 2C METER SHORTINOTINKS IN I
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 lE F25 rDC P R Y lg3 R
TO CAB 2D(2R25-SOO4) gAND CA8 2F(2R25-SOO6))
W
~
fl8E 27 JF FIRE IN MAIN CONTROL ROOM, CABLE SPREADING-ROOM OR r FIRE 27
\\
f COMPUTER ROOM'N PROCEED AS IS REQUIRED THi AND IF MANUAL START OF DIESELS 2A OR ts0TFY OPERATOR AT DIESEL'I etoo TO ATTEMPT local START Ig3 TO DESEL PROCEDURE 34SO-R43-001-2S:
OF DIESELS 2A,2C OR 18
%.s' y PER 34SO-R43-001-2S j,
FOR DESEL 2A g
- OPEN BRKR 14 AT 2R25-S004 TO ISOL TE YES is REMOTE CIRCUlTS 2C N ETED 2A
- FLASH GENERATOR AFTER DIESEL IS RUNNING 41Y NO R AT 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
- FLASH GENERATOR AFTER DESEL IS RUNNING BY FROM EITHER AVAILASLE SAT PLACING LOCAL START SWITCH TO REMOTE f M FROM MESEL 2A F RUNNING A
- PLACE VOLTAGE REGULATOR IN AUTO BY OPENING f LNOTE 23 $
CAU 3 J N
LINK TAl-l IN 2R43-P00lC AND JUMPER TERMINALS If NOTIFY OPERATOR AT N.
's TAl-8 AND TAl-9 i
govy w g 2g2g g 5 g
s t_AT N N 2P4 w
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 AS POSSIBLE TO ENSURE PSW SUPPLY TO DESELS.
- 2. LOWER DESEL GENERATOR FREQUENCY TO 58 HZ AND i
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 \\
ALL FRAMES a"
\\
i
\\
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)
DESEL CONTINUOUS T DAY 068 HOURN COMPONENT SW_gfL FRAME 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 i
490 560
! RHR PUMP B (2 Ell-C0028) 2G (2R22-S007) 8 2A 2C
-~
490 560
'THE HIGHER 7 DAY RATING 15 BASED UPON A fEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE l
CONTINUOUS Rf TM: A TnTit ne me um me rm
-r
6 E
fNOTIFY OPERAeTOR AT 440V WGR 2R22-SOOS IN DESEL SL TO VERFY OR CLOSE 4860V FEED g (BRKR TO 2R23-SOO3 (FR8)J FFIRE 28
9 AGE SWGR (2R22-SOO7320 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 l4 TO OPERATE BRKR TO g 9 START PLANT SERVICE (WAT ER PUMP 2P41-COO 4By (NOTIFY OPERATOR AT 4660V WGR 2R22-SOOT H OESEL SL c,a_
VERFY OR CLOSE 4860v T
BRKR TO 2R23-SOO4 (FR2)
O IS NO DfESEL IB REQUIREO FOR UNIT 2 SHUTOOWN YES FIRE 32 IF FIRE IN MAIN CONTROL ROOM CABLE SPREADING-ROOM OR COMPUTER ROOM, THEN PER$0RM THE FOLLOWING:
88
-OPEN BRKRS 16 AND 29 ON 2R25-S00L guy 4 goy p
-OPEN BRKRS 17 AND 19 ON 2R25-5002.
0 SWca GR22-SOO5
-S006 OR NSOO
-VERIFY OR CLOSE THE FOLLOWING BRKRS ON 2R23-S003 2E,2F;oR 20 (600V SWGR 2C)
- ^
COMPONENT FRAME
\\..-
/ 7
,. YES ~
s i
FFIRE 32 ESSENTIAL TRANSF 28 CABINET 2A 2M
-y REACTOR BLD A MCC 2C 3M l
SEND OPERATOR TO LOCAT R.
~~~
DIESEL BLDG MCC 2A 68 f
130TETl4 TO. VERFY OR TE D4 BATTERY CHARGER 2C 78 POWER :TO ' 600Y SWOR y
y BATTERY CHARGER 28 7M l
t 2R23-SOO3 (2C) -
g
/
BATTERY CHARGER 2A TT
/
4160/600V STA. SERVICE TRANSFORMER 2C 8
r FIRE 32 - ~
49'
-VERIFY OR OPEN ALL OTHER BRKRS ON 2R23-5003.
13 TCT D4-i
~VhFY R CLO E THE FOLLOWING BRKRS ON 2R23-S g
POWER TO 600V SWOR g
2R23-SOO4 (2D)
COMPONENT FRAME CA[2R2PC ^T 8
A Y CHARGER 2D 3
T 830TDTt3 T OPEN SRER 29 Di BATTERY CHARGER 2E 3M TO BYPASS LOSP LOAD SHED BATTERY CHARGER 2F 38 g
FOR 600V SUS 2C 600/208V MCC 28 ESS. DIV 2 4T DIESEL BLOG MCC 2C TB FSEND OPERATOR TO 12SVOC' i
ESSENTIAL TRANSFORMER 2C CABINET 28
~A CAB 2R25-SOO2 AT. LOCATION f30 TOT!3 TO OPEN BRER t9
-VERIFv OR OPEN ALL OTHER BRKRS ON 2R23-S004.
TO BYPASS LOSP LOAD SHED g
FOR'GOOV BUS'20 J,
I
'l SENO OPERATOR TO R2$
YTO 5%
S VER OR START RBCCW PUMP 2P42-COOtA OR IC g
j f
SEND OPERATOR TO S
R2 O
TO E 4-VERFY OR START RSCCW PUMP 2P42-COOtB j'
g (SEND OPERATOR TO LOCATION 7 130 TOT!3 TO VERFY OR TIE POWER TO VITAL AC BUS I E +-
2R25-SO63 FROM SWOR
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 cLEC AN TO E T
FANS.
dEND DRYWELL CHILLERS ANO f3
- 2. IF THE DRYWELL COOLING SYSTEM FAN LOCA COOLNQ FANS OVERRIDE SWITCH IS INOPERATIVE OR INACCESSIBLE, THEN PROCEED AS FOLLOWS i
L NOT E e6 4 CAU 3 J TO START THE DRYWELL COOLING FANS:
t F VERpFY OR RESTORE 7) c) AT MCC 2R24-S0lt, AT LOCATION 130RFRl4 INSTALL THE FOLLOWING 825/250V STATION SERVICE BATTERY CHAROES TO lb JUMPERd:
34 N 4Y-25
- T FAN TERMINAL TO TERMINAL g
\\
2T47-B007A 18Al 18Al7 2T47-C00lA 18Cl 18C2 g
2T47-COO 2A 22Cl 22C3 b) AT MCC 2R24-S012 AT LOCATION l'\\
130RFR24, INSTALL IHE FOLLOWING is JUMPERS:
ANY 4460V f
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 2T47-8008A 2R27-S007 1
17 ripRE 3e g
2U 2C
\\
2T47-8008B R27- 08 l
17 O 4 i
MO 0
^"
"op E 2T47-8009A 27-09 l
17 No ERS j 2T47-8009B 2R27-SO10 1
17
^
FNFORM OPERATOR W DIESEL 3
/
1 13ORHR24 SLDC TO NOTIFY SieFT SUPERVISOR
/
AND TRIP ANY DIESEL WHOSE
\\
B. (PRIMARY CONTAINMENT CHILLED WATER SYSTEM JACKET WATER TEMPERATURE CANNOT BE STARTED WITHIN 15 MINUTES OF ANY
\\
SYSTEM SHUTDOWN)
/
L REACHES 7t2*F
/
\\
1.
ON PANEL 2Hil-P700 PLACE THE LOCA OVERRIDE SWITCH (2P64-S3) TO OVERRIDE
\\
h I
AND START THE PRIMARY CONTAINMENT
\\
CHILLED WATER SYSTEM PER y
g
\\
\\
\\
\\
\\
PROCEED AS FOLLOWS TO START THE
\\
\\
DRYWELL CHILLERS:
c)*0 PEN THE FOLLOWING LINKS TO OVERRIDE
\\
\\
TRIP SIGNALS FOR BOTH CHILLERS:
g
\\
LINK LOCATION CHILLER g
\\
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
\\
\\
FIRE 31
(
{0MPUTER ROOM, AND IF ADEOgATE DIESEL COOLNCr-CAN FIRE W MAN CONTROL R00 CABLE SPREADING-ROOM 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 FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER VALVE BKR LOCATION VALVE LOCATION TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE
]P41-F316B 2R24-SO25, COMPT 4D PSW VALVE PIT 2A LOCATED ON PANEL R43-P00llN EACH DIESEL GENERATOR ROOM.
P4l-F316A 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 THE OUTPUT BREAKER BY ANY OR ALL OF THE FOLLOWING g
3 METHODS:
g3 PRn$[ABOVE I. PLACE OUTPUT BREAKER CONTROL SWITCH ON PANEL P652 TO CLOSE L63 PSic
- 2. LOWER DIESEL GENERATOR FREQUENCY TO 58 HZ AND J *-
/
READJUST TO 60HZ AND CHECK FOR BREAKER CLOSURE L
E NO
/
- 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.
/
/
lNACCESSIBLE, THEN PROCEED AS~FOLLOWS " -
'~~
/
TO START THE DRYWELL COOLING FANS:
/
a) AT MCC 2R24-50!!, AT LOCATION
/
130RFRl4, INSTALL THE FOLLOWING x
FFIRE 23 X
/
JUMPERS:
Oc O MmNT b:1 FAN TERMINAL TO TERMINAL 2T47-8007A 18Al 18Al7 SERVICE WATER DIVISION l AND i
5 HEADER PRESSURES FROW 2T47-C00!A 18Cl 18C2 i
L 2P41-P1-ROO3 AND ROO6 J 2T47-C002A 22Cl 22C3 l
PLANT
$ *7 b) AT MCC 2R24-5012, AT LOCATION 130RFR24, INSTALL THE FOLLOWING SERVICE WATER NO!
JUMPERS:
^"
FAN TERMINAL TO TERMINAL PRES BO E 60 PSIC 2T47-80078 18 81 1882
'/
2T47-C00lB 19Al 19A2 l
g5
/
2T47-C0028 23Cl 23C3 r SEND OPERATOR OR I & Cb" c) AT THE FOLLOWING LOCAL STARTERS.
TECHP#CIAN OR ELECTRICIAN
/
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
130RHRl4
~
2T47-8008B 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 B7 CANNOT BE STARTED WITHIN 15 MINUTES OF ANY ScRvicE
,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
' TBI-12 PANEL 2:121-P232 2P64-80068 TBI-12 PANEL 2H21-P230 2P64-B006A y
~
~
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
YW I
NOTE I
, N0 AYWELL PRESSURE
_ GROUP 1 ISOLATIONS AsOvE ts3 PSto KEY N
ONLY VALVES NORMALLY OPEN AND IN LINES GREATER THAN P RAMETER ANSW 4 [N. DIAM. AND OUTSIDE THE DRYWELL ARE LISTED HERE.
TES A COMPLETE LIST IS AVAILABLE WHEN YOU ENTER THE END YES PATH MANUAL.
wAS g7 VALVE LOCATION
_ DESCRIPTION ES
,$y" $ west 2821-F028A 130RBRl9 OyTBOARD MSIV I
0 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 67 OPERATE 100 AMP BRKR CB2B (AX) TO MOMENTAR!LY q DEENERGlZE RPS BUS 28 y Y FlRE l g[
OTIFICATI N BE EE ~ ~ ~ ~ ~ ~
ECErVED OR DO VERfF W'
IF FIRE IN CONTAMINATED AREA, NOTIFf HEALTH PHYSICS ALA MS NDICATE A FIRE TO RESPOND TO FIRE SCENE.
L j
NO K
/
1.
NOTIFY OPERATIONS I
SUPERVISOR ON SHIFT AND SHIFT SUPERVISOR 1
HOTIFY SECURITY 7
dq TO SOUND FIRE ALARM J
lMAKE FytE ANNOUNCEMENT FROM ANY PACE STATION M; 3 TIMES ICMEF-AND 2 WAY HADIOS nl
.D,tSPATCH F, IRE B.RIOADE TH - le Rmm 1ON UNIT JOF FIRE STATUS NOTine sHrT SueERvlS00 %
AS IT MAY EFFECT LNT I SHUTDOWN j
M VERFIED FIRE 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 )
]
1 PUMP HOUSE TO VERIFY OR SEND OPERATOR TO FREl p
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 C9 PUWP OPERATION AND OF f
DESEL FUEL SUPPLY j
I l
STARTUP
($
YES,,
Ate OPERATION OF f
- WOTOR OR DIESEL FRE t.
S vERinED
/
, L;m.
a CD
+
IS
.NO THE MAN TUR8ME INVOLVED N l
THE DENTIFIED
. YES..FRE.. w. -
..~:.
g.'
k\\
FFRE 23 SEND OPERATOR To LOCATIOtB l
83ORLRf9 TO DETERMINE PLANT. SERVICE WATER DivtS40N l 8
A#G E HEADER PRESSURE FROM
.. L. - 2941-Pt-ROO3 OR ROO6 )
y l\\
F 7 84, s ptAur s
'~
.. SERVICE WATER -
NDI*
\\
4 OfvtS80N"I AND E HEADER M
\\
g SURES A80V 60 Psic s
g
- L J
N 6-J: YES NOTE 23 F ee OPERATOR TO LOCAT Oil 11 IF THE DIESEL GENERATOR OUTPUT BREAKER FAILS TO 1
S AUTOMATICALLY CLOSE. THEN VERIFY DIESEL GENERATOR
' M..
52TCT15 TO VERIFY OR OPEN g IS AT RATED SPEED AND VOLTAGE AND ATTEMPT TO CLOSE RSCCW PUMP DISCH VALVE
, 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 bS h
- 2. LOWER DIESEL GENERATOR FREQUENCY TO 58 HZ AND p
& WITN OPEN OtSCH VALVEg READJUST TO 60HZ AND CHECK FOR BREAKER CLOSURE r-
, F (,
- 3. LOCALLY CLOSE THE OUTPUT BREAKER BY PUSHING UP ON THE tift TO CLOSE eLuNcER AT THE BREAKER RSCCW gg!
CABINET g
HEADER PRESSURE 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 [7 BYPASS LOSP LOAD SHED FOR 600V SUS 2C J
q ISEND OPERATOR TO 125VDC' CAB 2R25-SOO2 AT LOCATION 130 TDT!3 TO OPEN BRKR 19 TO 'g/>
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 M TO START R8CCW PUMP t
fSEND OPERATOR TO LOCATIOM M2TCT15 TO DETERMINE FROM 2P42-PI-ROO3A,8 OR C 6r7 R8CCW PUMP DISCH
(
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 u
130THT22 TO OPERATE BRKRS II 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",7 AND INSTALL JUMPER BETWEEN (7
TERMINALS 186 AND IST 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
N DESE1 BLDC TO OPERATE BRKRS ff f/
i (TO TRIP CRD PUMP 2 Cal-COOej I SEND OPERATOR TO SWGR 7 2R23-S004 AT LOCATION
(((
130TCTl4 TO OPERATE BRKRS l
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 DE-ENERGlZE AT 130TETl4 TO OPERATE BRKRS M7 2P70-F00lA 2R25-S00L BRKR 35 TO TRIP RBCCW PUMPS L
2P42-COOIA ANDIC
)
2P70-F004 2R25-S.064,BRKR 6 2PTO-F066 2R25-5064 BRKR 6 g
3 2P70-F005 2R25-5065,BRKR 23 SE D OP A T LOCA ION p'
2P70-F067 2R25-5065.BRKR 23 DRYWELL PNEUMATIC SUPPLY PRESSURE FROM 2PTO-Pi-NOOp f
/
FLRE 2 g5 Jf /
DRYwELL
- 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
REOUIRED g
s CAU 11 )
s ISEND OPERATOR TO WCC 2R24-SOO' N
A DN H
^' FFr Od hi? ES"Y0Ett R7 MONITOR FUEL POOL COOLING SYSTEM OPERATION.
^'
vER PNEUMATIC COMPRESSORS 2PTO-COQA AND 8 q
j HAS g4 gg NOTIFICATION 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 CONTROL N7 NO 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 130TET14 TO OPERATE BRKRS J3
'] IF A LOSS OF CONTROL AIR HAS CCIT#D, THCtd ISGi/ATC L A O O
- THE FOLLOWING -fGE PROTECTION SPRFALERS IF NO FIRE TO TRIP AIR COMPRESSOR EXISTS W THEIR ' SPRINKLED AREAS. '
- AREAS
.,lSOL ATON VALVE, (NO1c 2e g DT CSEND OPERATOR TO SwuR 3
!!EACTOR FEED PUMP A
~ ' '
2U43-Fi 17 ? T ll2 TAT 19
~
r:EACTOR' FEED PUMP B 130TY l4' Y CNR 6
f,.ONDITIONEREACTOR FEED PUMP OIL KRS TO Tree AIR COMPRESSORS 2P58< 00e A m K J
(NOTE 24 MYDROGEN SEAL Oil STSTEM 2U43-F0iS AT ll2TITl9 MAIN TURBINE Olt RE.5ERVrfR s 2Z43-Flot' AT ll2TH Tl3 f5END OPERATOR TO LOCATIOR Il2TFTI3 TO DCTERMINC g3 m
. OPERASILITY STATUS OF,
i i (THE ' UNITS i AIR COMPRfitSORSj l (NOTFY OPERATOR AT L&;ATION3 h
^
If2TFT13 TO DETERhirE UH1T l CONTROL AIFl.
/~ 3 s
HEADER PRESSURE Fh0M L
IPSI-PI-591,593 OR 595 J b
T l CONTR NO AIR HEADER PRES $UR ABOVE TO PSIG AND AY I
LNT I AIR COMPRES$NtS i
N RATi #
YES l.
ISEND 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
s W
r
>I NO IS
---1 SPDS OPERATIONAL AND MANNED L
J K YES
\\
I SEND GPERATOR TO LOCATION 83ORHR2r TO DETERWii4E THE POSITIOb h3 OF VALVES 2Dil-F050 AND 2Dil-FOS 2 y
g ARE NO y,tygj F^8 C b3 N0 2D -F050 1
OR 2Dil-FOS 2 AUTO CLOSED YES IS YES t/3 DRYWELL PRESSURE ABOVE 1.63 PSIG ww-m-NO b
/
F SEND OPERATOR TO 7
SBCN NB 2T46 NOOIA N
' * " ^
TO DEPRESS SYSTEM RESET PUSHBUTTON NOTE 2 g
j i
CROUP 2 ISOLATIONS S N TY M ALL M ONLY VALVES NORMALLY OPEN AND N LINES GREATER THAN LOC T JUWPER BETWEEN TERWfNAL
{
4 W. DIAM. AND OUTSIDE THE DRfwELL ARE LISTED HERE.
Tas-as AND T83-16 N SBGT CAB 2T46-DoctA A COMPLETE LIST IS AVAILABLE WHEN TOU ENTER THE END PATH MANUAL.
q 74YES{l VALVE LOCATION DESCRPTION DID S8GT FAN 2G11-FOl9 87RFR21 DW EQUlPMENT 2T46-DOOtA START l
Syyp py;jp i
DISCHARGE
'~
(140TFY OPERATOR AT LOCAT%
gy 185RAR?3 TO GO TO CAB 2746-D0018 ON SBCT FAN TO
.I Q
- DISCHARGE NSTALL JUWPER BETWEEN 2Cll-F003 QERWINALS T82-3 AND T82-M 120RERt9 DW FLOOR DRAW SUMP PUMP s
rhoTFY OPOLATOR AT LOCAT@OtB y 185RAR23 AT CAS 2T46-DO 2Gil-F004 120RERt9 DW FLOOR DRAW yb,
AT S8CT FAN TO WSTALL JuuPER l
BETWEEN TERWWALS TB3-ts SUMP PUMP DISCHARGE VALVE j
(AND T83-16 TO START FAN)
/
p GROUP S ISOLATIONS PRi l /
pg3g.FOO4 158RHR19 RWCU OUTBOARD F
VERIFY OR CLOSE I4-ISOLATION i
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 7
R5.[ ACTOR PRESSURETRND]
O I
g5 N
/
4 BEING AUTOMATICALLY
/
AtNTAINED ABOVE 850 PSI AND BEgw 340 PSIG y
/
YES 8d
/
/
/
/
/
m
/
/DN PANEL 2C82-POOi AT LOCATIOrli lDORAR)6 PLACE MANUAL BLOWDOWN]
FIRE 26 VALVE 282t-FO(30. F AND C EMERGENCY [h/
1 l CONTROL TRANSFER SwlTCH TO j
/
IF FIRE IN MAIN CONT 60L ROOM, CABLE SPREADING ROOM OR BRKR 10 ON 2R2$ AND IF REQUIRED TO TRIP HPCIT L EMERCENCY (EMERC) POSITION j
/
COMPUTER ROOM SOO2 l
r
/f F T PANEL 2C82-POOI OPtRATE7 A
uANuAL BLOWDOwH VALVES
/
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 35B
)
YES REOUIRED BY A PREVIOUS SEND OPERATOR TO 7
TEP ON THIS FLOW LOCATION DORHRIS TO VERFY PATH 7g OR CLOSE SCRAM DISCH VOLUME (VENT) ISOLATION m
NO VALVE 2Cff-FO35A J
SEND OPERATOR TO 7
g LOCA110N 8TRBRt5 TO VERFY m
OR CLOSE SCRAM DtSCH VOLUME (DRAIPO ISOLATION
/
VAtVE 2 Cit-FO3T j
CT NOTIFY ON CALL HNP WATER LEVEL NO MANAGEMENT AND ES l
ELOW +go 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 ROCEDWE 45.450 ARE g7 t
j 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 1LOCATI 13ORFR24 TO HPCIVAL E4-FOu j
LOCATSO NRR24 6
NCli [VE 4 -FO I J AT PANEL 2C82 POOi AT LOCATIO) eO E w
CAUTION 8 ueJ
'~# F VALVES DO NOT OPERATE FROM THE REMOTE SHUTDOWN I
AT PANEL 2Ca2-Pool AT LOCATM PANELS, OPERATE THEM LOCALLY.
I'E GE Y R
TRA FER h
Stsuf50SPTR'"'"'
E x
CAu 8 ;
O HAS 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 ILCAT 83 C A S RT fN l.,
TORUS ROOM TO ASSIST IN PERFORMING THE FOLLOWING RCIC BAR COND VAC STEPS TO START RCIC PUWP AND CONDENSATE PUMP; f.
OPEN BRKR 14 ON 2R25-S001 R10R TO STARTING RCiC VERIFY OR MANUALLY OPEN THE ROC ACUUM BREAKERS 1ATPANEL2C82-Pool h SOhT4 VAL ON 2E51-FOIO VALVE BRKR LOCATION VALVE LOCATION j
2R24-Sole, COMPT 15A 2R24-S0!!
122RBRl9 2ESI-F104 COMPT ITB 122RBR19 I PowYO.sNAA$E V LVES AT PANEL 2C82-POOI 2ESt-F105 5
M6 ACE THE ROC TUR8 FLOW CONTROL AND TURBlNE TRlP AND HROTTLE VALVE TRANSFER SWITCHES TO EMERG ON 2C82-P001 2E51-F012 AND 2E51-FOl3 a e OPEN BRKR 12 ON 2R25-S001TO REMOVE POWER TO THE GOVENOR 7
AND ALLOW MANUAL RESTART AT 2C82-P00L THIS ALSO I VERIFY OR OPEN RCIC AT PAtEL 2C82-POOf (0h Cf.-CNERGlZES THE RCtC TACHOMETER. CONTROL RCIC SPEED LUBE Olt COOLING BY OBSERVING RCIC FLOW VALVE 2E51-F046 y
i V RI R
MS STEAM SUPPLY VALVES 2E51-FOOT AND 2E56-FOO8j l
iRCIC FLOW AT PANEL 2C82-POOISET CONTROLLER TO Mh 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 T BN IP
%h
~
THE FOLLOWING TO START 2T41-8004A AT MCC IPLACE AND THROTTLE VALVE
-OPEN BRKR 4C SWITCH TO OPEN J
-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 l#
RCthkA TO TU NE
[Vi 6
-JUMPER THE INTERNAL SIDE OF TERM!NALS 4C-PI AND 4C-2 VALVE 2E51-F045 AND IN THE TOP COMPT OF FRAME 4C fBOTHON
^
SAMC 1 CH
-CLOSE BRKR 4C
/
RCIC YES
/
START SUCCESSFUL NOTE 26 NG NO
/
TO' LOCALLY START THE HPCI OR RCIC COOLERS PERFORM
/
THE FOLLOWING
- l. INSTALL THE JUMPER INDICATED FOR EACH CCOLER TO BE STARTED j
/
COOLER MCC/ BREAKER LOCATION JUMPER f
2T41-8004A 2R24-S0ll/FR4C 30RFR14 4CITO 4C2 2T41-8004B 2R24-S0!2/FR2C
.30RFR24 2CITO 2C2 rFIRE ?l g_"-
/
2T41-B005A 2R24-50ll/FR7C 30RFRl4 TClTO TC2 SEND OPERATOR 2T41-B005B 2R24-S012/FRSC 130RFR24 SCITO SC2 TO VERIFY OR START RCIC ROOW COOLER;' s
- 2. VERIFY OR OPEN THE PLANT SERVICE WATER SUPPLY VALVE FOR EACH COOLER STARTED esoyc as q FAT PANEL 2C82-POOL ADJUST 7
/
COOLER PWS SUPPLY VALVE LOCATION 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
\\
A f
V? E5-O#* N7 /
\\
^
L W V t
AS REQUIRED g/
FIRE 26 g/g r r,RE 2s CAu os
\\
IF FIRE IN MAIN CONTROL ROOM CABLE SPREADING-ROOM OR A
BRKR 10 ON 2R25AND IF REQUldED TO TRIP HPCITH i
\\
COMPUTER ROOM D'I RESTORE AND MANTAN
\\
S002
\\
REACTOR WATER LEVEL TO s
l ABOVE O WCHES AND SELOW [i[7 g
\\
(
+50 INCHES g
\\
\\
f CAU 23)\\
g b
\\
\\
CAN YE'S' ' A
\\
N
~-
REACTOR WATER
(
CAUTION 14 LEVEL BE MAINTAINED g
BOVE O WCH j
USE A HAND HELD TACHOMETER, OR EOUIVALENT, TO CONTROL t
_. HPCI OR RCIC MINIMUM SPEED ABOVE 2250 RPM.
i
\\
\\
\\
\\
\\
CAUTION 13 g
g IF HPCI OR RCIC SUCTION AUTOMATICALLY TRANSFERS T y
ESSION POOL, VERIFY OR OPEN MINNUM FLOW REQRC g
\\
\\
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
/
IF VALVES 00 NOT OPERATE FROM THE REMOTE SHUTDOWN l[,,
LOCAT4ON I3ORAR16 PLACE LL RHR SYSTEM EMERGENCY d
ONTROL TRANSFER SwlTCHES I
O DaERGENCY (EMERtp POSITION
\\
CAu 8 J
/
MISC 7 IV IF S
S 2OI-FOO6A,8.C AND D 12Cl-F0478 AT PANEL 2C82-POOi 7
VERfY OR OPEN VALVES 2Ol-FOO4B
![9 2Ol-FOO38 i
l AND 2Ol-F0288
)
I AT PANEL 2C82-POOIVERFih -
OR CLOSE VALVES lQ 20-F0488 20-FOIT8 AND 20-FOws J
t20-F0278 ANO 20-rO248; T PANEL 2C82-POOi VERFY OR CLOSE VALVES
'kQ j
I 2 RTE 4o"Si !En"FO%
1 SEND OPERATOR TO LOCATION 87RLR21 TO
,[
IRNR SERviCr WATER euweS AT PANEL-2C82-POOf START 19 20-cOOe OR 2a-cOOo 3 's CAUTION 3 A
CAu 3 ;
~s ' s,'
VERIFY DIESEL GENERATOR LOADING DOES NOT EXCEED THE MAS L,,9 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 I LOCATION (3ORARt6 START ON PANEL 2C82-POOIAT l
JC 490 560 gh tj 2A 490 560 RHR PUMP 20-COO 28 2C 490 560 (FIRE 25
\\
- THE HIGHER T DAY RATING IS BASED UPON A YEARLY 3
\\
ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE ITS N swoR bE #TSR b g\\
CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR
-S 73 A
WITH A LOAD OF 490 TO 560 AMPERES IS ALLOWED.
2c ROOM IN DIESEL BLDG
(
R P P Q 00 8 N
g i
, 's s
HAS YES I*
- P FIRE 25 O-Co a
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
\\.
IRHRSYSTEM 7
ON PANEL 2C82-POOIAT FIRE 29 LOCATION DORAR$ OPEN 'NR IF FIRE IN MAIN CONTROL ROOM. CABLE SPREADING-ROOM OR CONTAINMENT COMPUTER ROOM,THEN "Y""O
's
-VERIFY RUNNING OR START DivlSION 11 RHR AND CORE SPRAY PUMP ROOM COOLER 2T41-80028. PERFORM THE FOLLOW 1NG IR AT PANEL 2C62-POOL
's TO START:
q 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
I AND TEMPERATURE J
SEND OPERATOR
-OPEN BKR 15 ON 2R25-S06S TO ENSURE COOLING TO RHR D AG EVAT N O WONITOR RHR PUMP OPERATg NOTIFY OPERATOR IN SE' DIAO ST ELEVATION TO A)9 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; IAT PANEL 2C82-POOITMtOTTLE' 2 Ell-F0248 AS REOUIRED TO ESTABLISH DESIRED RHR FLOWj 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
)
IVALVE2 Cit-F035A SEND OPERATOR TO 3
LOCATION DORHRI5 TO VERFY OR CLOSE SCRAM DISCH b
VOLUME (VENT) ISOLATION e
)
SEND OPERATOR TO 7
1 VALVE 2Cil-F03T LOCATION STRBR15 TO VERFY o
OR CLOSE SCRAM DISCH lb VOLUME (DRAIN) ISOLATION )
IMANAGEMENTANDSYSTEM NOTIFY ON CALL HNP fb LOAD DISPATCHER IANDOF NOTIFY LAB FOR POST SCRAM IODINE SAMPLE 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
1 2.1 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.
[
l 2.1.5 There may be a fire in either RHR/ CORE SPRAY Diagonals.
l 1
3.0 OPERATOR ACTIONS 1
l l
'a 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
[
I Monitor containment ' control parameters and execute concurrently with lCONTAINMEN~
3.3 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 lCONTINGENC' Contingency 45.87 to verify isolations.
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
ATTACHMiNT 6 (Cont'd) x 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.
[
l 3.5.1 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
ATTACHMENT 6 (Cont'd)
~s
'~}
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 l
System 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 l
RPS BUS 28 l
ESSENTIAL CABINET 2A ESSENTIAL CABINET 28 l
l INSTRUMENT BUS 2A INSTRUMENT BUS 2B l
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 l Procedure
)
the plant service water system.
l 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
]
l 3.17.1 Enter GSR procedure'45.61 to recover RBCCW.
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.
l 45.63 I
WHEN ADEQUATE AC POWER IS AVAILABLE.
l 3.19 If the Condensate System is not oparating, enter go to step 3.20.-
l 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) l THE CONDENSATE B0OSTER PUMP IS NOT RUNNING BECAUSE OF l
~~
LOSS OF 0FF-SITE POWER.
[
l PUMP 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
2N21-C001A 4160V BUS D (2R22-S004) 130TGT23 l
3 2N21 -C001 B 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
i 3.21.1 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
i BREAKER LOCATION VALVE LOCATION l
2R24-S022, FRAME 28~
130RH R19 l
l l
l 1
"If the torus area is inaccessible, close 2E41-F003 by 3.22.1 (Attachment installing jumpers listed in Attachment 2.
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 inches.
l l
A6-6 Rev. A
OVERSIZE DOCUMENT PAGE PULLED 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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