ML20035H068
| ML20035H068 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/23/1993 |
| From: | Fiedler J, Lawson S, Regis A COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| DSSP-0100-A, DSSP-100-A, NUDOCS 9305030065 | |
| Download: ML20035H068 (22) | |
Text
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- NUCLEAR STATION FROCEDURE ROUTING f
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Register No.
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(Sig and return this form to the DOSR CLERK.)
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I hereby acknowledge receipt of the above.
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1 DAP 09-02 II REVISION 27~
FORM 9-2B PROCEDURE HISTORY I
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l Procedure Narrt.er:
Posted Procedure Locations:
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Supportive Ref erences (letters, temporary change request, commitEnts, analysis):
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DSSP
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DRESDEN SAFE SHUTDOWN PROCEDURES
,q Proc.
Rev.
DOSR Review No.
Title L
Date pate 010-1 Safe Shutdown Paths for Extensive Rev. 2 9/89 9/91 Plant Damage
- 0100-A Hot Shutdown Procedure - Path A Rev. 05 4/93 4/95 0100-Al Hot Shutdown Procedure - Path A-1 Rev. 04 12/92 12/94 0100-B Hot Shutdown Procedure - Path B Rev. 04 12/92 12/94
- 0100-B1 Hot Shutdown Procedure - Path B1 Rev. 04 12/92 12/94
- 0100-A2/B2 Hot Shutdown Procedure - Path A2/B2 Rev. 05 3/93 3/95
~
- 01J0-C Hot Shutdown Procedure - Path C Rev. 05 12/92 12/94 j
- 0100-CR Hot Shutdown Procedure - Control Room Rev. 03 4/93 4/95 Evacuation (Safe Shutdown Cart)
- 0100-D Hot Shutdown Procedure - Path D Rev. 04 2/93 2/95
- 0100-E Hot Shutdown Procedure - Path E Rev. 06 2/93 2/95 100-El Hot Shutdown Procedure Path El DELETE 4/88
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0100-F Hot Shutdown Procedure - Path F Rev. 04 6/92 6/94 100-F1 Hot Shutdown Procedure Path F1 DELETE 4/88
- 0200-L LPCI/CCSW Cold Shutdown Method Rev. 02 2/93 2/95 200-S Shutdown Cooling Cold Shutdown Method Rev. 1 4/88 4/90
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(SDC) 4 C)
APR 231993
'c esp u u m s 1 of 1 m
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=N UNIT 2
- DSSP 0100-A REVISION 05
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HOT SHUTDOWN PROCEDURE - PATH A Q
Requirements:
1..
2.
3.
Safe Shutdown Report, Dresden Units 2 and 3 (Fire Protection Program Documentation Package, Volume 3, Book 1).
Special Controls / Reviews:
i Posted Procedure - This is a Controlled Posted Procedure. Any authorized change will be brought to the attention of the Department Supervisor or an Operating Engineer, as applicable.
/^s A. Regis Originator N/A Independent Reviewer / Verifier (If Applicable)
J. Fiedler Department Procedure Writer S. Lawson Department Supervisor h??Nb APRE31993 7-~
k-1 of 19 e
k UNIT 2
- DSSP 0100-A i
REVISION 05 HOT SHUTDOWN PROCEDURE - PATH A A.
PURPOSE:
1.
This procedure provides guidelines to achieve Dresden U2 hot shutdown, directed from the Control Rocm, using Hot Shutdown Path A, following a fire in which critical plant components were rendered inoperable.
2.
This procedure uses the following components:
e Isolation Condenser with makeup from Condensate Storage Tank (CST), firewater, or Service Water (SW).
2/3 D/G and U2 electrical power train.
e 2A CRD Pump to provide U2 reactor makeup water.
e 2A Service Water Pump.
B.
USER
REFERENCES:
1.
Procedures:
o a.
DSSP 0010-01, Determining Safe Shutdown Paths.
7 b.
DSSP 0100-T11, Cooldown Tables.
c.
DSSP 0100-T14, Minimum CST Inventory for RPV Makeup.
d.
DSSP 0200-T3, Diesel Generator 2/3 Local Manual Start.
g C.
SUPPLEMENTS:
1.
Attachment A, U2 NSO Actions.
2.
Attachment B, U2 SS Actions.
3.
Attachment C, U2 EA Actions.
4.
Attachment D, Inside HVO Actions.
5.
Attachment E, Center Desk NSO Actions.
6.
Checklist A, Shift Engineer Tracking, D.
PREREOUISITES:
1.
Applicable portion of DSSP 0010-01 has been completed.
2.
Shif t Engineer has directed performance of this procedure.
E.
PRECAUTIONS:
1.
Fire damage may cause spurious events to occur and/or require the manual operation of various components.
2.
In worst case conditions, reactor vessel makeup and decay heat removal must be initiated within 30 minutes of initiating event.
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2 of 19 I
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II UNIT 2 i
- DSSP 0100-A i
RIVISION 05
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E.
3.
When using radios, radio should be held in hand. Using coil-cord f
( )
microphono may impair reception.
e Direct radio contact may not be possible. In such cases, required communications must be relayed.
4.
Due to damage to security multiplexer cables, nonal entrance through security doors may be prevented.
5.
This procedure should be followed only in the event that normal or emergency procedures are insufficient.
F.
LIMITATIONS AND ACTIONS:
1.
Keys for high rad areas, CB locks, and security doors are obtained from the Shift Engineer's office as necessary.
2.
Keys for high-high rad areas are obtained from the Rad-Chem office as necessary.
3.
Copies of DSSPs, radios, flashlights, protective clothing, masks or air packs, pyrometers, etc., are obtained from Safe Shutdown t
Egyipment Cart (near BUS 25, north of Auxiliary Electric Equipment Room).
4.
Steps in this procedures are based on analysis of each component used considering severe fire damage in any fire area of the plant.
Under any given fire situation, total functional loss of all equipment in a fire area may not occur.
This procedure should be performed at the discretion of the
(-~/)
Shift Engineer, or other qualified Senior Reactor Operator serving as the Controlling Supervisor.
s_
5.
Certain steps or conditions within this procedure may contradict normal license conditions or Technical Specification requirements, as stated in 10 CFR 50.54x:
'A licensee may take reasonable action that departs from a license condition or Technical Specification requirements in an emergency when this action is immediately needed to protect the public health and safety and no action consistent with the license conditions and Technical Specifications that can provide adequate or equivalent protection is immediately apparent."
This action "shall be approved, as a minimum, by a licensed Senior Reactor Operator (SRO) prior to taking the action."
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3 of 19 l
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Ib UNIT 2
- DSSP 0100-A REVISION 05 G.
FROCEDURE:
l NOTE I
i 1.
U2 Nuclear Station Operator (NSO) will normally coordinate actions of I other shift personnel, under direction of the Shift Engineer, after initial actions are complete.
2.
Initial actions of U2 NSO (Nuclear Station Operator), U2 Shift Supervisor (SS), and U2 Egaipment Assistant (EA) are performed concurrently.
3.
Checklist A, Shift Engineer Tracking, is provided to assist in g
tracking procedure progress.
.e 1.
Direct U2 NSO to enter Attachment A, U2 NSO Actions, and perfom regaired actions.
2.
Direct U2 SS (Shift Supervisor) to enter Attachment B, U2 SS Actions, and perform required actions.
3.
Direct U2 EA (Equipment Assistant) to enter Attachment C, U2 EA Actions, and perform required actions.
4.
Direct Inside High Voltage Operator (HVO) to obtain a copy of Attachment D, Inside HVO Actions, in preparation for possible actions.
5.
Direct Center Desk NSO to obtain a copy of Attachment E, Center Desk NSO Actions, in preparation for possible actions.
6.
Check procedure progress on Checklist A, Shift Engineer Tracking.
H.
DISCUSSION:
1.
This procedure is developed with attachments for shift personnel having actions to perfarm, with the main procedure body developed for the Shift Engineer or other qualified, licensed Senior Reactor Operator in control of evolutions performed.
2.
Checklist A, Shift Engineer Tracking, provides checkoffs for the Shift Engineer to assist in tracking plant conditions and status of major evolution completion during the performance of the procedure.
3.
Attachment A, U2 NSO Actions, provides an overview of the evolutions being performed and the approximate sequence, once initial actions have been performed. Details of specific actions are given in the appropriate shift personnel attachments.
4 of 19
I 'L '
UNIT 2
- DSSP 0100-A REVISION 05
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W.
WRITER'S
REFERENCES:
\\m /
c 1.
NRC Information Notice No. 87-50, Potential LOCA at high and low pressure interf aces f rom fire damage.
2.
Title 10 Code of Federal Regulations (CFR):
a.
b.
Safe Shutdown Report, Dresden Units 2 and 3 (Fire Protection Program Documentation Package, Volume 3, Book 1).
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U 5 of 19 t
1
l *. I ATTACHME!C A UNIT 2
- DSSP 0100-A U2 NSO ACTIONS REVISION 05 p'
1.
Manually scram reactor by depressing MANUAI, SCRAM CH A MQ MAICAL SCRAM
\\
CH B pushbuttons.
e DO NOT reset scram until RPV makeup source other than CRD is available.
1 CAUTION l
Open relief valves cause a loss of reactor vessel inventory.
2.
Place ADS INHIBIT switch in INHIBIT.
3.
Place Electromatic Relief Valve control switches in OFF:
e 2-203-3B, 2B ERV.
l 2-203-3C, 2C ERV.
e 2-203-3D, 2D ERV.
2-203-3E, 2E ERV.
2-203-3A, 2A TARGET ROCK.
4.
Close Main Steam Isolation Val'ves (MSIVs):
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NOTE l
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l Makeup to the shell side of the Isolation Condenser must be j
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initiated within 20 minutes of Isolation Condenser operation.
j J
i S.
Open MO 2-1301-3, RX INLET ISOL, to initiate Isolation Condenser.
6.
Verify Isolation Condenser valve lineup:
e AO 2-1301-17, VENT VLV closed.
e AO 2-1301-20, VENT VLV closed.
e MO 2-1301-2, RX OUTLET ISOL open.
MD 2-1301-1, RX OUTLET ISOL open.
j e
MD 2-1301-4, RX INLET ISOL open.
i D
6 of 19 i
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ATTACHMENT A UNIT 2
- DSSP 0100-A U2 NSO ACTIONS (Continued)
REVISION 05
[^
7.
Report completion of initial actions to Shift Engineer.
i'u e
l NOTE l
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l U2 EA initial actions are to open the supply breakers to MO 2..
A.
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RX OUTLET ISOL, and MO 2-1201-1A, RX OUTLET BYP, at MCC 28-1.
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CAITTION Automatic RWCU isolation may not occur.
Ensure RWCU Isolation by verifying ONE of the following valve lineups:
B.
A.
MO 2-1201-1, RX OUTLET ISOL, closed, MG MO 2-1201-1A, RX OUTLET BYP, closed.
93 B.
MO 2-1201-2, INLET ISOL, closed, ME2 MO 2-1201-3, AUX PP SUCT, closed. C (W-1).
9.
H RWCU valve positions cannot be verified from Control Room, QE RPV level cannot be maintained, THEN, direct Inside HVO 'High Voltage Operator) to verify MO 2-1201-2, U2 AUX PMP BYP MOV, closed locally.
10.
Notify Shift Engineer of RWCU isolation verification.
11.
While monitoring RPV Level and Pressure using multiple indication, throttle MO 2-1301-3, RX INLET ISOL, to minimize shrinkage and loss of O
reactor vessel inventory through cpen safety / relief valve (s).
t Establish and maintain a coaldown rate of s IS*F/ hour (use DSSP 0100-711, Cooldown Tables).
Record level and pressure at 10 minute intervals on DSSP 0100-711.
~
12.
H Control Room RPV Pressure and Level indication is NC7T available, THEN direct Center Desk NSO to monitcr reactor pressure and level locally per Attachment E, Center Desk NSO Actions.
i 13.
E offsite power is not wailable, THEN verify D/G 2/3 auto-start and D/G 2/3 TO BUS 23-1 ACB closed using Control Room indication and alarms.
H Control Room Indication is not available, E EE direct Inside HVO to verify D/G 2/3 auto-start and auxiliaries.
14.
Place control switches in PULL 'IV-LOCK to remove loads from BUS 23-1:
e 2A SDC PP.
2C SDC PP.
2A LPCI PP.
28 LPCI PP.
2A CORE SPRAY PP.
e 2A RWCU RECIRC PP.
2A RBCCW PP J
8 7 of 19
Ib ATTACIEENT A UNIT 2
- DSSP 0100-A U2 NS') ACTIONS (Continued)
REVISION 05 O
15.
Verify BUS 23-1 TO TR 28 ACB and TR 2B To BUS 28 breakers closed.
(b 16.
Direct U2 SS to verify BUS 23-1 configuration locally.
17.
E offsite power is not available, THEN verify the following breakers on BUS 23 are open:
TR 21 TO BUS 23 ACB.
e TR 22 TO BUS 23 ACB.
18.
Place control switches in PULL-TO-LOCK to remove BUS 23 loads:
2A CCSW PP.
e 2B CCSW PP.
2A COND/ BOOST PP.
2B COND/ BOOST PP.
2A CIRC WTR PP.
2B CIRC WTR PP.
BUS 23 TO TR 25 ACB.
19.
Close BUS 23 & BUS 23-1 TIE ACB.
20.
Direct U2 SS to verify proper BUS 23 configuration locally.
21.
Notify Shift Engineer BUS 23-1 and BUS 23 aligned.
22.
Maintain Isolation Condenser shell side level as follows:
A.
Start 2A COND TRANSFER PP.
B.
Monitor ISOL CONDR LVL, LI 2-1340-2.
C.
H Control Room isolation condenser level indication is not available, THEN direct U2 EA to monitor Isolation Condenser Level locally.
D.
Throttle MO 2-1301-10, COND FILL INLET, as necessary to maintain Isolatim Condenser level.
23.
Prepare 2A CRD PP for RPV Makeup water as follows:
A.
H U3 Turbine Building Closed Cooling Water (TBCCW) is NOT available, THEN direct Inside HVO to align valves for alternate cooling of 2A CRD Pump from Service Water.
B.
WHEN alternate cooling valves are aligned, THEN close MO 2-301-2A, 2A PP DISCH VLV.
(1)
H control and/or indication is not available from the Control Room, THEN direct Inside HVO to check MO 2-0301-2A, 2A CRD PMP r?.SCH VLV, closed at 2A CRD Pump.
(2)
H MO 2-0301-2A is not closed, THEN direct Inside HVO to manually close MO 2-0331-2A, 2A CRD PMP DISCH VLV, per Attachment D, Inside HVO Actions.
8 of 19 A
1 it' ATTACHMENT A UJIT 2
- DSSP 0100-A U2 NSO ACTIONS (Continued)
REVISION 05
[')
24.
E 10 2-301-2A, 2A PP DISCH VLV has remote control, THEN perform the Q
following:
A.
Start 2A CRD PP.
B.
Open MO 2-301-2A, 2A PP DISCH VLV.
(1)
Monitor 2A CRD Pump amps.
{2)
Ensure 2A CRD Pump motor current does not exceed 34 amps.
CAUTION H control of MO 2-301-2A, 2A PP DISCH VLV, is NOT available from the Control Room, THEN careful coordination between U2 NSO and Inside HVO is required to start 2A CRD Pump.
25.
H 10 2-301-2A, 2A PP DISCH VLV, does NCrr have remote control and/or indication, THEN perform the following:
A.
Start 2A CRD PP from the Control Room.
B.
Direct Inside HVO to:
(1)
Manually open MO 2-0301-2A, 2A CRD PMP DISCH VLV.
(2)
Monitor amp meter on local panel 2252-76, (on wall north of
~
r CRD pump).
(3)
Ensure CRD Pump motor current does not exceed 34 amps.
C 26.
Notify Shift Engineer that 2A CRD Pump started.
27.
Direct U2 EA to manually throttle 2-0301-9A, 2A CRD FILTER INLET VLV, or 2-0301-9B, 2B CRD FILTER INLET VLV, to maintain reactor level at +8 inches to +40 inches.
Center Desk NSO will direct operation from local indication if Control Room instrumentation is not available.
CAUTION Service Water must be initiated within 1 1/2 hours after CRD Pump start.
I 28.
H no Service Water Pumps are running, THEN direct Inside HVO to align Service Water valves to preclude Service Water Pump runout.
29.
E no Service Water Pumps are running, WHEN notified by Inside HVO that i
Service Water valves are aligned, THEN perform the following:
A.
Start 2A SW PP.
B.
Notify Shift Engineer that 2A SW PP is in cperation.
t 4
1 9 of 19 i
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I=L ATTACH GNT A UNIT 2
- DSSP 0100-A U2 NSO ACTIONS (Continued)
REVISION 05 l
f P
(
NME j
CST level can be monitored in U2 RX Feed Pump Room if Control Room l
l indication is not available.
l l
s J
L.
30.
Continue to provide Isolation Condenser makeup by monitoring CST level:
A.
E CST level approaches 12 ft, THEN direct Inside HVO to align CST to 2/3 B Contaminated Condensate Storage Tank and 1A CST.
B.
IE CST inventory is approaching the appropriate line on the DSSP 0100-T14, Minimum CST Inventory for RPV Makeup graph, THEN perform the following:
(1)
Open MO 2-4102, SERV WTR VLV, to maintain Isolation Condenser shell side level.
(2)
Stop 2A COND TRANSFER PP.
C.
J_E additional Isolation Condenser make-up water is required, THEN direct Inside HVO to open 2-3906, SW SUPPLY TO FIRE PROTECTION, in the Cribhouse.
31.
Notify Shift Engineer after stable Hot Shutdown conditions have been established.
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10 of 19
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II ATTACHMENT B UNIT 2
- DSSP 0100-A l
e U2 SS ACTIONS REVISION 05 i
9 O
1.
At Reactor Building 250Vdc MCC 2A, open all load breakers EXCEPT for the following Isclation Condenser valve breakers:
Cubicle H-1, 2-1301-3 U2 ISCL CDSR COND OUTLET OTBD ISOL.
e Cubicle H-2, 2-1301-2 U2 ISOL CDSR STEAM INLET OTBD ISOL.
2.
Verify the following breakers are closed at de MCC 2A:
Cubicle H-1, 2-1301-3 U2 ISOL CDSR COND OUTLET OTBD ISOL.
e Cubicle H-2, 2-1301-2 U2 ISOL CDSR STEAM INLET OTBD ISOL.
3.
At Reactor Building 250Vdc MCC 2B, open all load breakers EXQEPT for the i
following isolation condenser valve breakers:
e Cubicle M-1, 2-1301-10 U2 ISOL CDSR CNTAM DEMIN WATER FILL STOP VLV.
Cubicle N-1, 2-4102 U2 ISOL CDSR FIRE SYSTEM FILL STOP VLV.
4.
Verify the following breakers are closed at de MCC 2B:
Cubicle M-1, 2-1301-10 U2 ISOL CDSR CNTAM DEMIN WATER FILL STOP VLV.
I Cubicle N-1, 2-4102 U2 ISOL CDSR FIRE SYSTEM FILL STOP VLV.
5.
At Turbine Building 250Vdc MCC #3, verify breakers are closed:
Cubicle A-1, 3-8350-3 U3 250VDC BATTERY TO MAIN BUS #3.
Cub.cle I-2, U2 250VDC REAC"rOR BUILDING MCC #2B (MAIN FEED).
6.
Report de Systems aligned to U2 NSO and Shift Engineer.
7.
Align SWGR 28 (Reactor Building third floor, southeast corner) as follows:
g A.
Pull all control fuses located in SWGR 28 Cubicles F-1 and F-2.
B.
Manually trip the following breakers on SWGR 28:
Cubicle A-1, 2-5734A 2A DRYWELL COOLER.
Cubicle A-2, 2-5734B 2B DRYWELL COOLER.
Cubicle A-3, 2-5734F 2F DRYWELL COOLER.
Cubicle A-4, 2-5734G 2G DRYWELL COOLER.
Cubicle B-1, 2-7828-7 480V REACTOR BLDG MCC 28-7.
o Cubicle B-3, 2-5702A 2A SOUTH TURBINE BLDG SUPPLY FAN.
l Cubicle B-4, 2-5701A 2A MOTOR GENERATOR SET SUPPLY FAN.
e Cubicle C-3, 2-5704A 2A REACTOR BUILDING EXHAUST FAN.
Cubicle D-1, 2-1902A 2A FUEL POOL COOLING PUMP.
Cubicle D-2, 2-5703A 2A REACTOR BUILDING SUPPLY FAN.
o Cubicle D-3, 2-5703C 2C REACTOR BUILDING SUPPLY FAN.
Cubicle D-4, 2-1206 U2 REACTOR WATER CLEANUP AUXILIARY PUMP.
Cubicle E-3, 2-7329 BUS 28-29 TIE.
11 of 19 i
Ib
-ATTACHMENT B UNIT 2 l
- DSSP 0100-A U2 SS ACTIONS (Continued)
REVISION 05
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NOTE l
j Maintenance handle and ratchet for manually closing 480V breakers are l l
located in Safe Shutdown Equipment box at SWGR 29.
l 8
J L
8.
C.
Verify the following SWGR 28 breakers are closed:
i e
Cubicle E-2, MAIN FEED FROM BUS 23-1.
e Cubicle C-1, 2-7828-1 480V REACTOR BUILDING MCC 28-1.
Cubicle C-2, 2-7828-2 480V REACTOR BUILDING MCC 28-2.
-)
e Cubicle C-4, 2-7828-3 4 80V REACTOR BUILDING MCC 2 8-3.
t 8.
Report SWGR 28 aligned to U2 NSO and Shift Engineer.
9.
WHEN notified by U2 NSO, THEN verify BUS 23-1 configuration locally:
A.
E offsite power is not available, THEN verify Cubicle 14, STAND-BY D/G 2/3 FEED (VIA 4KV BUS 40) breaker is closed.
B.
Verify the following BUS 23-1 breakers tripped:
o Cubicle 1, 2-1002C 2C SHUTDOWN COOLING PUMP.
Cubicle 2, 2-3701A 2A RBCCW COOLING WATER PUMP.
Cubicle 3, 2-1002A 2A SHUTDOWN COOLING PUMP.
C Cubicle 5, 2-1502B 2B LPCI PUMP.
g
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Cubicle 6, 2-1205A 2A REACTOR WATER CLEANUP RECIRCUIATION r
I PUMP.
~ l Cubicle 10, 2-1401A 2A CORE SPRAY PUMP.
e Cubicle 11, 2-1502A 2A LPCI FUMP.
{
C.
Verify Cubicle 7, 2-7328 REACTOR BUILDING 480V SWGR 28 breaker closed on BUS 23-1.
D.
Notify U2 NSO BUS 23-1 verification cc:::plete.
L 10.
WHEN notified by U2 NSO, THEN verify BUS 23 configuration locally:
r A.
E offsite power not arailable, THEN verify BUS 23 breakers
^ '
tripped:
Cubicle 3, MAIN FEED FROM UNIT AUX TRANSFORMER 21.
l Cubicle 12, RESERVE FEED FROM RESERVE AUXILIARY TRANSFORMER 22.
B.
Verify BUS 23 Cubicle 2, 2-6763-1 BUS 23-1 FEED, breaker closed.
)
12 of 19
)
a 1
r
I.c ATTACHMENT B UNIT 2
- DSSP 0100-A U2 SS ACTIONS (Continued)
REVISION 05 10.
C.
Verify BUS 23 breakers tripped:
Cubicle 5, 2-1501-44B 2B CONTAINMENT COOLING SERVICE WATER.
Cubicle 6, 2-4401B 2B CIRCULATING WATER PUMP.
I I
Cubicle 7, 2-1501-44A 2A COICAINMENT COOLING SERVICE WATER PUMP.
Cubicle 8, 2-3302A/3401A 2A CONDENSATE PUMP AND CONDENSATE BOOSTER PUMP.
i e
Cubicle 10, 2-3302B/3401B 2B CONDENSATE PUMP AND CONDENSATE BOOSTER PUMP.
Cubicle 11, 2-4401A 2A CIRCULATING WATER PUMP.
Cubicle 13, 2-7325 TURBINE BU'.LDING 4 00V SWGR 25.
D.
Notify U2 NSO BUS 23 verification complete.
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.j 13 of 19
1['
ATTACHMENT C UNIT 2
- DSSP 0100-A U2 EA ACTIONS REVISION 05 1.
Ali gn MCC 28-2 (located in Turbine Building by Hydrogen Seal Oil Unit) t I
as follows:
A.
Rack out all load breakers on MCC 28-2 EXCEPT Cubicle D-5, 2-3319A 2A CONDENSATE TRANSFER PUMP, by I
B.
Verify MCC 28-2 Cubicle D-5, 2-3319A 2A CONDENSATE TRANSFER PUMP, breaker is closed.
2.
Align MCC 28-3 (located in Turbine Building by Hydrogen Seal Oil Unit) as follows:
A.
Rack out all load breakers on MCC 28-3 EXCEPT Cubicle D-1, 2/3-3903 UNIT 2/3 DIESEL GEN COOLING WTR PUMP (NORMAL FEED).
B.
Verify MCC 28-3 Cubicle D-1, 2/3-3903 UNIT 2/3 DIESEL GEN COOLING WTR PUMP (NORMAL FEED), breaker is closed.
3.
Align MCC 28-1 (Reactor Building ground floor by accumulators) :
A.
Rack out all load breakers on MCC 28-1 EXCEPT those listed in Step 3.B.
B.
Verify the following MCC 28-1 breakers are closed:
o Cubicle F-1, 2/3-5203 UNIT 2/3 DIESEL OIL TRANSFER PUMP.
o Cubicle G-3, 2/3 5790 UNIT 2/3 DIESEL GENERATOR ROOM SUPPLY FAN.
i Cubicle J-3, 2-1301-4 U2 ISOIATION CONDENSER RX INLET ISOL e
VLV.
e Cubicle J 4, 2-1301-1 U2 ISOLATION CONDENSER RX OUTLET ISOL VLV.
i 5
r
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l NOTE i
1 l
Isolation Condenser water level should be maintained within sightglass viewing range.
l*
t 4.
JI directed by U2 NSO, THEN perform the following at Isolation Condenser:
A.
Open Isolation Condenser Sightglass Isolation Valves:
e 2-1301-39, U2 ISOL CDSR SIGHT GLASS HI SIDE SV.
2-1301-40, U2 ISOL CDSR SIGHT GLASS LO SIDE SV.
2-1301-633, U2 ISOL CDSR SIGHT GLASS HI SIDE ROOT.
2-1301-634, U2 ISOL CDSR SIGHT GLASS LO SIDE ROOT.
i B.
Monitor Isolation Condenser level locally and report status to U2
- NSO, f
S.
WifEN directed by U2 NSO (or CENTER DESK NSO), THEN manually throttle 2-0301-9A, 2A_CRD FILTER INLET VLV, QB 2-0301-9B, 2B CRD FILTER INLET VLV, (Reactor Building ground floor by drywell personnel access), as directed, to maintain reactor level at +8 inches to +40 juches).
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Ik ATTACHMENT D UNIT 2 i
- DSSP 0100-A INSIDE HVO ACTIONS REVISION 05 f
1.
H directed by U2 NSO, THEN verify RWCU Isolation locally.
Q 2-1201-2, U2 AUX
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A.
H U2 RBX is accessible, THEN manually close MO PUMP BYP MOV, in RWCU pipe chase (entrance on EL 570 f t).
i B.
H U2 RBX is not accessible, THEN verify closure of PCV 2-1217, U2 RWCU PCV, by removing instrument air to U2 RBX by closing 2-4705-504, INST AIR ISOL VLV TO THE U2 RX BLDG (Turbine Bldg EL I
- (W-1) 517 ft by instrument air compressor).
2.
E offsite power is not available, WHEN directed by U2 NSO, TEEE verify emergency power as follows:
A.
Verify 2/3 D/G auto-start, o
E 2/3 D/G did not auto start, THEN start 2/3 D/G per DSSP 0200-T3, Diesel Generator 2/3 Local Manual Start.
B.
Verify 2/3 VENTILATION FAN started.
C.
Verify DIESEL COOLING WATER PUMP 2/3 flow on FI 2/3-3941-882A (located on the west end of the north wall of the 2/3 D/G Room).
Expected flow rate is approximately 1000 gpm.
3.
E directed by U2 NSO, THEN align valves for alternate cooling of 2A CRD Pump from Service Water:
A.
Verify valves open:
e 2/3-3?99-348, U2 & U3 CRD PMPS SW ALT CM SUPPLY SV (Turbine Building ground floor west of MCC 27 1).
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e 2-3999-359, U2 CRD PMPS SW ALT CM RETURN SV (south of EHC unit).
r NOTE 1
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Following valves are located at foot of stairs in CRD Pump Room.
l L.
__.a B.
Unlock and clone valves:
i e
2-3899-205, U2 CRD PMPS TBCCW SUPPLY HDR SV.
1 e
2-3899-204, U2 CRD PMPS TBCCW RETURN HDR SV.
C.
Verify valves closed:
e 2-3999-360, U2 CRD PMPS SW ALT CM INLET DRN VLV.
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2-3999-361, U2 CRD PMPS SW ALT CLG OUTLET DRN VLV.
D.
Unlock and open valves:
2-3999-357, U2 CRD PMPS SW ALT CM INLET SV.
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2-3999-349, U2 CRD PMPS SW ALT CLG INLET SV.
2-3999-348, U2 CRD PMPS SW ALT CLG OUTLET SV.
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e 2-3999-358, U2 CRD PMPS SW ALT CLG OUTLET SV.
j E.
Notify U2 NSO that CRD Cooling Valves aligned.
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Ib ATTACHMENT D UNIT 2
- DSSP 0100-A INSIDE HVO ACTIONS (Continued)
REVISION 05 O
4.
E directed by U2 NSO, THEN verify MO 2-0301-2A, 2A CRD PMP DISCH VLV, Q
closed at 2A CRD Pump.
I E MO 2 - 03 01-2A, 2A CRD PMP DISCH VLV, is not closed, THEN perform the following steps to close MO 2-0301-2A, 2A CRD PMP DISCH VLV:
(1)
Rack out breaker at MCC 25-2 Cubicle J2: 2-0301-2A 2A CRD PUMP DISCHARGE VALVE.
(2)
Manually close MO 2-0301-2A, 2A CRD PMP DISCH VLV, at 2A CRD Pump discharge.
CAUTION E control of MO 2-0301-2A, 2A CRD PMP DISCH VLV, is NOT available
~
from Control Room, THEN careful coordination between U2 NSO and Inside HVO is required to start 2A CRD Pump.
5.
E control of MO 2-0301-2A, 2A CRD PMP DISCH VLV is not available from the Control Room, WHEN U2 NSO starts 2A CRD Pump from the Control Room, THEN perform the following as directed.
A.
Manually open MO 2-0301-2A, 2A CRD PMP DISCH VLV.
B.
Monitor amp meter at Panel 2252 ~16, (on wall north of CRD pump).
C.
Ensure CRD Pump motor current does not exceed 34 amps.
6.
E directed by U2 NSO (CST level f alls to 12 f t), THEN align CST to 2/3 B Contaminated Condensate Storage Tank and 1A CST as follows:
A.
Open 2/3-3327-A-500, U2 & U3 HPCI SUCT FROM 2/3A CST DNSTRM SV.
B.
Open 2/3-3346-500, U1A S'IU TO 2/3 CST X-TIE VLV.
C.
Verify 2/3-2301-12, U2 & U3 HPCI SYS SUCT FROM 2/3B CST, is open.
.~c 7.
E directed by U2 NSO, THEN open 2-3906, SW SUPPLY TO FIRE PROTECTION, in the Cribhouse.
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it t
ATTACHMENT D UNIT 2
- DSSP 0100-A INSIDE HVO ACTIONS (Continued)
REVISION 05
/
8.
IE no service water pumps are running, WHEN directed by the U2 NSO, THEN
(
verify the following valves closed to preclude Service Water Pump
_\\
runout:
o 2-3904-500, U2 TBCCW TCV INLET VLV.
E 2-3904-501, U2 TBCCW TCV OUTLET VLV (by U2 TBCCW HX).
e 2-3924-501, U2 TBCCW TCV BYP VLV.
e 3-3904-500, U3 TECCW HX TCV INLET VLV.
E 3-3904-501, U3 TBCCW IDE TCV OUTLET VLV (by U3 TBCCW EX).
e 3-3924-501, U3 TBCCW HX TCV BYP VLV.
~.
e 2-3906-500, U2 TURB OIL CLR TCV INLET VLV.
G 2-3906-501, U2 TDRB OIL CLR TCV OUTLET VLV (at SW Discharge Header South of Turbine Oil Reservoir).
2-3907-500, U2 TURB OIL CLR TCV BYP VLV.
o 2-3907-A-500, U2 TURB OIL CLR TCV BYP VLV.
t e
3-3906-500, U3 'mRB OIL CLR TCV INLET VLV.
E 3-3906-501, U3 TURB OIL CLR TCV OUTLET VLV (South of Turbine Oil Reservoir).
e 3-3907-500, U3 TURB OIL CLR TCV BYP VLV.
3-3907-A-500, U3 TURB OIL CLR TCV BYP VLV.
E o
2/3-3999-240, 2/3 MAX RECYCLE SERVICE WTR RETURN TO U3 DISCH HDR ISOL VLV.
2/3-3999-241, 2/3 MAX RECYCLE SERVICE WTR RETURN TO U2 DISCH HDR ISCL VLV (South of Turbine Oil Reservoir).
9.
Continue to monitor the following equipment while in operation:
e 2/3 DG FUEL OIL TRANSFER PUMP.
e SW PUMP 2A.
DIESEL COOLING WATER PUMP 2/3.
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j%
4 ATI'ACHMENT E UNIT 2 r
- DSSP 0100-A CENTER DESK NSO ACTIONS REVISION 05 1.
IE directed by U2 NSO, THEN perform the following:
A.
Monitor RX Pressure and level at one of the following locations:
i e
At INSTRUMENT RACK 2202-5 on PI 2-263-60A, U2 REACTOR PRESSURE, and LITS 2-263-59A, U2 REACTOR HIGH WATER LEVEL TRIP.
l RE e
At INSTRUMENT RACK 2202-6 on PI 2-263-60B, U2 REACTOR PRESSURE, and LITS 2-263-59B, U2 REACTOR HIGH WATER LEVEL j
TRIP.
pg At INSTRUMENT RACK 2202-7 on PI 2-263-139A, U2 REACTOR PRESSURE JP #1 LP LINE, and LI 2-263-151A, U2 REACTOR WIDE RANGE LEVEL.
Q3 At INSTRUMENT RACK 2202-8 on PI 2-263-139B, U2 REACTOR l
PRESSURE JP #11 LP LINE, and LI 2-263-151B, U2 REACTOR WIDE RANGE LEVEL.
B.
Record level and pressure at 10 minute intervals on DSSP 0100-T11, Cooldown Tables.
C.
Coordinate with U2 NSO to establish and maintain a cooldown rate of s 15'F/ hour (use Saturation Temp / Press and Cooldown Rate Guidelines table of DSSP.0100-T11, Cooldown Tables).
4 l
l D.
Direct U2 EA HVO to manually throttle 2-0301-9A, 2A CRD FILTER INLET VLV, or 2-0301-9B, 2B CRD FILTER INLET VLV, as necessary to maintain reactor level at +8 inches to +40 inches.
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I1 CHECKLIST A UNIT 2 J
- DSSP 0100-A SHIFT ENGINEER TRACKING REVISION 05 RESPONSIBLE ACTION
/
Initial Actions complete:
Manual reactor scram U2 NSO ADS in INHIBIT Safety / relief valver in CFF MSIVs closed Isolation Condenser initiated Makeup to shell side of Isolation Condenser must be initiated within 20 minutes of Isolation Condenser operation.
U2 NSO RWCU Isolation verified U2 NSO J_E offsite power not available, verify D/G 2/3 auto-start U2 NSO Start 2A CONC TRANSFER PP U2 NSO Cooldown rate s IS*F/ hour established and maintained de MCC #2A aligned de MCC #2B aligned U2 SS de MCC #3 aligned U2 SS BUS 28 aligned MCC 28-1 aligned MCC 28-2 aligned b
U2 NSO BUS 23-1 aligned
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i U2 NSO BUS 23 aligned U2 NSO Isolation Condenser shell side level maintained U2 NSO CRD Pump 2A started i
Service Water must be initiated within 1 1/2 hours after start of CRD Pump.
U2 NSO Service Water Pump 2A started (IF no SW Pumps running)
U2 NSO CST Level maintained
-r Inside HVO Service Water to Isolation Condenser make-up (IF required)
U2 NSO Stable Hot Shutdown condition REMAFJS:
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