ML103220485
| ML103220485 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/08/2010 |
| From: | Exelon Corp |
| To: | Office of Nuclear Reactor Regulation |
| Billoch-Colon A, NRR/DORL, 301-415-3302 | |
| Shared Package | |
| ML103210488 | List: |
| References | |
| DOP 1000-07, Rev 01 | |
| Download: ML103220485 (14) | |
Text
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 1 of 14 ALTERNATE SHUTDOWN COOLING REQUIREMENTS:
Technical Specifications.
INDEPENDENT TECHNICAL REVIEW:
Disciplines NPPT RO RE/QNE CH RS I&C M&ES Required:
[X] [X] [ ] [ ] [ ] [ ] [X]
Unit 1 Review Required:
[ ] YES [X] NO Special Reviews:
NONE.
PLANT OPERATIONAL REVIEW COMMITTEE (PORC):
PORC REQUIRED
[ ] YES [X] NO APPROVAL AUTHORITY:
Shift Operations Superintendent (SOS), or designee POST PERFORMANCE REVIEWS:
NONE.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 2 of 14 ALTERNATE SHUTDOWN COOLING A.
PURPOSE:
This procedure provides an alternate means, Alternate Shutdown Cooling, to remove decay heat from the Reactor when the Shutdown Cooling (SDC) or support systems are unavailable AND other means of maintaining reactor coolant temperature below 212F are inadequate.
B.
USER
REFERENCES:
1.
Technical Specifications:
a.
Section 3.3.6.1, Primary Containment Isolation Instrumentation.
b.
Section 3.3.6.2, Secondary Containment Isolation Instrumentation.
c.
Section 3.4.7, SDC System - Hot Shutdown.
d.
Section 3.4.8, SDC System - Cold Shutdown.
e.
Section 3.4.9, RCS Pressure and Temperature (P/T) Limits.
f.
Section 3.5.2, ECCS - Shutdown.
g.
Section 3.9.8, SDC - High Water Level.
h.
Section 3.9.9, SDC - Low Water Level.
2.
Technical Specification Surveillance Requirements:
a.
SR 3.5.2.1.a, ECCS - Shutdown.
3.
Procedures:
a.
DOA 0201-04, Loss of Vessel Flange, Shell or Recirculation Loop Temperature Recorders During Heatup or Cooldown.
b.
DOA 1000-01, Residual Heat Removal Alternatives.
c.
DOP 1500-02, Torus Water Cooling Mode Of Low Pressure Coolant Injection System.
d.
DOP 3300-05, Condenser Level Control.
C.
SUPPLEMENTS:
1.
Attachment A, Reactor Cooldown Monitoring.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 3 of 14 D.
PREREQUISITES:
1.
DOA 1000-01 has been executed AND is incapable of maintaining reactor coolant temperature < 212F.
2.
Torus intact AND at Panel 902-3, LI 2-1602-3, TORUS LVL, has been verified > 10 feet 4 inches (Tech Spec 3.5.2, SR 3.5.2.1.a).
3.
At least one (1) ADS valve is available for use.
4.
Reactor pressure < 150 psig.
5.
Reactor level as designated per Unit Supervisor for current plant conditions.
SRO Peer Check (Initial/Date) __________/___________
6.
At least one (1) LPCI AND two (2) CCSW pumps are available for reactor injection AND torus cooling.
7.
SDC System is NOT in operation.
8.
Personnel evacuated from the Primary Containment.
9.
Unit is in Mode 3 OR 4.
E.
PRECAUTIONS:
NONE.
F.
LIMITATIONS AND ACTIONS:
1.
Moderator temperature change shall NOT exceed 100°F averaged over one (1) hour.
2.
Maintain reactor vessel metal temperatures to the right of the limit lines of Tech Spec Figure 3.4.9-2.
3.
Prior to AND during the fill of the main steam lines, reactor pressure is required to be maintained < 45 psig.
4.
Prior to raising reactor water level above the reactor flange, the differential temperature between the reactor coolant and the reactor head flange must be < 230°F.
5.
Reactor coolant temperature must be > 166°F when water is first applied to the flange area. After the flange is covered then moderator temperature is allowed to drop below 166°F. This temperature band is only applicable during forced cooldown of the reactor flange.
6.
Maintain temperature of reactor vessel flange and head flange 83F when vessel head bolting studs are under tension.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 4 of 14 G.
PROCEDURE:
1.
Monitor reactor vessel moderator AND metal temperatures. Log on Attachment A to ensure Tech Spec limits are met.
NOTE Steps G.2 and G.3 may be performed concurrently if condensate is being used to fill the reactor vessel.
CAUTION Do NOT raise level above the main steam lines (conservatively 100 inches indicated) UNTIL reactor pressure is < 45 psig.
2.
IF available, THEN utilize condensate system to fill the vessel to below the main steam lines (conservatively 100 inches).
Monitor main condenser hotwell level AND makeup as necessary (DOP 3300-05).
3.
Start maximum available torus cooling (DOP 1500-02)
(approximately 10 kgpm LPCI flow through each test loop).
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 5 of 14 G.
4.
Close the following valves:
MO 2(3)-220-1, MSL DRN ISOL VLV.
MO 2(3)-220-2, MSL DRN ISOL VLV.
AO 2(3)-220-46, HEAD VENT VALVE.
AO 2(3)-220-47, HEAD VENT VLV.
MO 2(2)-1301-1, RX OUTLET ISOL.
MO 2(3)-1301-2, RX OUTLET ISOL.
MO 2(3)-2301-4, STEAM ISO VLV.
MO 2(3)-2301-5, STEAM ISO VLV.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 6 of 14 G.
5.
IF injection will be routed through B LPCI loop, THEN:
a.
Close MO 2(3)-1501-38B, TORUS CLG/TEST.
CAUTION IF MO 2(3)-1501-38A is throttled open > 36 seconds, THEN the LPCI system SHALL be declared inoperable.
b.
Throttle open MO 2(3)-1501-38A, TORUS CLG/TEST, UNTIL desired flow rate is obtained (approximately 5000 gpm per pump).
c.
Close MO 2(3)-1501-21B, LPCI VLV.
d.
Verify ONE of the following conditions:
(1)
Reactor Recirculation pumps are in operation OR (2)
The following valves are closed:
(a)
MO 2(3)-0202-5A, 2(3)A PP DISCH VLV (b)
MO 2(3)-0202-5B, 2(3)B PP DISCH VLV CAUTION Do NOT exceed 100F/hour cooldown rate.
e.
Place ONE of the ERV keylock switches in MAN:
2(3)-0203-3B, 2(3)B ERV.
2(3)-0203-3C, 2(3)C ERV.
2(3)-0203-3D, 2(3)D ERV.
2(3)-0203-3E, 2(3)E ERV.
f.
Open MO 2(3)-1501-22B, INJ VLV.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 7 of 14 CAUTION 1.
Do NOT exceed 5000 gpm per LPCI pump as indicated on FR 2(3)-1540-7, LPCI SYS TOTAL FLOW.
2.
Do NOT exceed reactor pressure of 150 psig.
3.
Do NOT cycle ADS valves when flooded.
4.
Do NOT raise level above the main steam lines (conservatively 100 inches indicated) UNTIL reactor pressure is < 45 psig.
G.
5.
g.
Throttle open MO 2(3)-1501-21B, LPCI VLV, to achieve a slow increasing reactor level AND cooldown rate 100F/hr.
h.
Throttle closed MO 2(3)-1501-38A, TORUS CLG/TEST, to maintain LPCI pump flow < 5000 gpm per pump or to increase LPCI injection.
i.
Control reactor cooldown rate 100F/hr by controlling LPCI injection flow by:
Throttling MO 2(3)-1501-21B, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38A, TORUS CLG/TEST.
j.
Control Reactor pressure < 150 psig, but high enough to keep the ERV open by:
Throttling MO 2(3)-1501-21B, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38A, TORUS CLG/TEST.
k.
Control reactor level AND pressure when moderator temperature can be maintained between 180 and 200F.
CAUTION When raising level it is possible, because of off normal calibration conditions, to quench the reactor vessel shell without a corresponding decrease in vessel flange temperature.
l.
IF reactor level approaches 185 inches indicated reactor level, THEN monitor reactor vessel shell temperature for signs of a sharp increase in shell cooldown rate.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 8 of 14 G.
5.
m.
IF indicated reactor level reaches 190 to 210 inches, THEN stop level increase.
n.
IF additional ERV flow is required, THEN open an additional ERV by placing ONE of the ERV keylock switches in MAN:
2(3)-0203-3B, 2(3)B ERV.
2(3)-0203-3C, 2(3)C ERV.
2(3)-0203-3D, 2(3)D ERV.
2(3)-0203-3E, 2(3)E ERV.
o.
Control reactor cooldown rate 100F/hr by controlling LPCI injection flow by:
Throttling MO 2(3)-1501-21B, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38A, TORUS CLG/TEST.
p.
Control Reactor pressure < 150 psig, but high enough to keep the ERVs open by:
Throttling MO 2(3)-1501-21B, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38A, TORUS CLG/TEST.
q.
Control reactor level AND pressure when moderator temperature can be maintained between 180 and 200F.
r.
WHEN desired to terminate Alternate Shutdown Cooling, THEN:
(1)
Close MO 2(3)-1501-22B, INJ VLV.
(2)
Place all ADS valve Keylock switches to AUTO.
(3)
Terminate torus cooling (DOP 1500-02).
(4)
Exit this procedure.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 9 of 14 G.
6.
IF injection will be routed through A LPCI loop, THEN:
a.
Close MO 2(3)-1501-38A, TORUS CLG/TEST.
CAUTION IF MO 2(3)-1501-38B is throttled open > 36 seconds, THEN the LPCI system SHALL be declared inoperable.
b.
Throttle open MO 2(3)-1501-38B, TORUS CLG/TEST, until desired flow rate is obtained (approximately 5000 gpm per pump).
c.
Close MO 2(3)-1501-21A, LPCI VLV.
d.
Verify ONE of the following conditions:
(1)
Reactor Recirculation pumps are in operation.
OR (2)
The following valves are closed:
(a)
MO 2(3)-0202-5A, 2(3)A PP DISCH VLV.
(b)
MO 2(3)-0202-5B, 2(3)B PP DISCH VLV.
CAUTION Do NOT exceed 100F/hour cooldown rate.
e.
Place ONE of the ERV key locks in OPEN:
2(3)-0203-3B, 2(3)B ERV.
2(3)-0203-3C, 2(3)C ERV.
2(3)-0203-3D, 2(3)D ERV.
2(3)-0203-3E, 2(3)E ERV.
f.
Open MO 2(3)-1501-22A, INJ VLV.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 10 of 14 CAUTION 1.
Do NOT exceed 5000 gpm per LPCI pump as indicated on FR 2(3)-1540-7, LPCI SYS TOTAL FLOW.
2.
Do NOT exceed reactor pressure of 150 psig.
3.
Do NOT cycle ADS valves when flooded.
4.
Do NOT raise level above the main steam lines (conservatively 100 inches indicated) UNTIL reactor pressure is < 45 psig.
G.
6.
g.
Throttle open MO 2(3)-1501-21A, LPCI VLV, to achieve a slow increasing reactor level AND cooldown rate 100F/hr.
h.
Throttle closed MO 2(3)-1501-38B, TORUS CLG/TEST, to maintain LPCI pump flow < 5000 gpm per pump or to increase LPCI injection.
i.
Control reactor cooldown rate 100F/hr by controlling LPCI injection flow by:
Throttling MO 2(3)-1501-21A, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38B, TORUS CLG/TEST.
j.
Control Reactor pressure < 150 psig, but high enough to keep the ERV open by:
Throttling MO 2(3)-1501-21A, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38B, TORUS CLG/TEST.
k.
Control reactor level AND pressure when moderator temperature can be maintained between 180 and 200F.
CAUTION When raising level it is possible, because of off normal calibration conditions, to quench the reactor vessel shell without a corresponding decrease in vessel flange temperature.
l.
IF reactor level approaches 185 inches indicated reactor level, THEN monitor reactor vessel shell temperature for signs of a sharp increase in shell cooldown rate.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 11 of 14 G.
6.
m.
IF indicated reactor level reaches 190 to 210 inches, THEN stop level increase.
n.
IF additional ERV flow is required, THEN open an additional ERV:
2(3)-0203-3B, 2(3)B ERV.
2(3)-0203-3C, 2(3)C ERV.
2(3)-0203-3D, 2(3)D ERV.
2(3)-0203-3E, 2(3)E ERV.
o.
Control reactor cooldown rate 100F/hr by controlling LPCI injection flow by:
Throttling MO 2(3)-1501-21A, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38B, TORUS CLG/TEST.
p.
Control Reactor pressure < 150 psig, but high enough to keep the ERVs open by:
Throttling MO 2(3)-1501-21A, LPCI VLV.
AND/OR
Throttling MO 2(3)-1501-38B, TORUS CLG/TEST.
q.
Control reactor level AND pressure when moderator temperature can be maintained between 180 and 200F.
r.
WHEN desired to terminate Alternate Shutdown Cooling, THEN:
(1)
Close MO 2(3)-1501-22A, INJ VLV.
(2)
Place ALL ADS valve keylock switches to AUTO.
(3)
Terminate torus cooling (DOP 1500-02).
(4)
Exit this procedure.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 12 of 14 H.
DISCUSSION:
1.
This procedure establishes Alternate Shutdown Cooling from the reactor when Shutdown Cooling (SDC) is unavailable. LPCI is used to provide flow from the torus to the reactor and the Relief valves provide a pathway for water to flow from the reactor to the torus. This removes heat from the reactor and deposits it in the torus. Heat in the torus is removed by use of the LPCI system in torus cooling mode.
2.
Entry into this procedure is made when the Shutdown Cooling has failed, attempts to restore SDC have failed, and back-up methods of heat removal have been attempted per the abnormal procedure for Loss of Shutdown Cooling.
3.
For implementation of this procedure, the ADS valves require pressurizing of the reactor to approximately 50 psig in order for the Target Rock to open. ERVs have been found to open with lower pressure. It is anticipated that the vessel will pressurize but is limited to < 150 psig in the Reactor vessel to stay within the assumptions made in the analysis and testing performed (reference generic report NEDE-24988-P) and the Tech Spec mode applicability for HPCI and Isolation Condenser.
4.
Engineering analysis of a water hammer event in 1985 demonstrated that the main steam lines can be filled with water provided the differential pressure between the reactor steam dome and the saturation pressure of the reactor coolant is controlled and maintained < 50 psig.
W.
WRITER'S
REFERENCES:
1.
Dresden Station NUREG 0737 Item II.D.1 Performance Testing of BWR Safety /Relief Valves, response to NRC request for additional information; E.D. Swartz letter to D.G. Eisenhut dated October 15, 1982.
2.
LS 05-83-08-035, August 25, 1983 D.L. Crutchfield letter to D.L. Farrar-
Subject:
NUREG 0737 Item II.D.1, Safety and Relief Valve Testing.
3.
NEDE-24988-P, Analysis of Generic BWR Safety /Relief Valve Operability Test Results 4.
IR 663242, IDNS Comments Regarding Raw Water Piping Issue Affects.
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 13 of 14 ATTACHMENT A REACTOR COOLDOWN MONITORING The following data must be verified to satisfy Tech Spec requirements.
The PRIMARY indication should be used when available.
The ALTERNATE indication should only be used if the primary is NOT available.
CHECK 1 During cooldown, at least once per 30 minutes, rate of change of primary system coolant AND bottom head temperatures shall be determined to be 100°F per hour. (Tech Spec SR 3.4.9.1)
< 212F Panel 902(3)-4, TR 2(3)-260-11, RECIRC LOOP TEMPS PRIMARY 212F Panel 902(3)-5, UR 2(3)-640-27, WR RX PRESS (Saturation temperature corresponding to pressure.)
< 212F None; refer to DOA 0201-04, Loss of Vessel Flange, Shell or Recirculation Loop Temperature Recorders During Heatup or Cooldown.
ALTERNATE 212F Panel 902(3)-4, TR 2(3)-260-11, RECIRC LOOP TEMPS CHECK 2 During cooldown, at least once per 30 minutes, determine that the vessel metal temperature and pressure are in the Acceptable Region of Tech Spec Figure 3.4.9-2. (Tech Spec SR 3.4.9.1)
Upper Vessel and Beltline Region PRIMARY Panel 902(3)-4, TR 2(3)-260-11, RECIRC LOOP TEMPS (Must have flow through loop. This is representative of the most restrictive beltline region metal temperatures.)
ALTERNATE Panel 902(3)-5, UR 2(3)-640-27, WR RX PRESS (Saturation temperature corresponding to pressure)
(Alternate may be used without forced Recirc flow.)
Bottom Head PRIMARY Panel 902(3)-21, TR 2(3)-263-104, Point 6, BOTTOM HEAD DRAIN (Must have flow through the line.)
ALTERNATE Panel 902(3)-21, TR 2(3)-263-104, Point 9, VESSEL BOTTOM HEAD (This must be corrected for inside surface metal temperature by subtracting 75°F from the indicated temperature.)
CATEGORY 1 UNIT 2(3)
DOP 1000-07 REVISION 01 14 of 14 ATTACHMENT A (Continued)
REACTOR COOLDOWN MONITORING Unit _______
Date ________________
Time Reactor Coolant Temperature
(°F)
Reactor Pressure (psig)
Reactor Upper Vessel Temperature
(°F)
Reactor Bottom Head Temperature
(°F)
Check 1
()
Check 2
()
Initial