Text

Public Version of Revised Offnormal & Emergency Operating Procedures,Including Procedures 1-0910032 Re Auxiliary Transformers Offnormal Operation & 2-1010030 Re Loss of Instrument Air
	ML20080P384
Person / Time
Site:	Saint Lucie
Issue date:	09/01/1983
From:	Petrie L; FLORIDA POWER & LIGHT CO.
To:	;
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ML17214A470	List: ML20080P384;
References
	PROC-830901, NUDOCS 8310060494
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Page 1 of 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 1 0FF-NORMAL OPERATING PROCEDURE NO. 1-0910032 REVISION 1

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1.0 TITLE

AUXILIARY TRANSFORMER OFF-NORMAL OPERATION 2.0 REVIEW AND APPROVAL:

Reviewed by Plant Nuclear Safety Committee June 27 19 1 Approved by K. N. Harris Plant Manager June 28 1974 Revision 1 Reviewed by Facility Review Group #u n e. 42./ 19 PJ Approved by MMM Ym Plant Manager 7' 2.5~- 1913 3.0 PURPOSE AND DISCLSSION:

3.1 This procedure provides instructions to follow in case of a malfunction or loss of auxiliary transformers 1A and/or 1B in order to minimize possible damage and outage time.

3.2 Since failure of the auxiliary transformer may cause a loss of power not only in the plant but in the 240KV switchyard as well, it is important that prompt action be taken to determine the cause of any malfunction and/or alarm and its solution.

3.3 In order to minimize the possibility of damage and/or injury, no mechanical or electrical interlock should ever be intentionally overridden nor should any feeder breaker that has tripped due to an automatic protective feature be reclosed until the cause has been determined and corrected or isolated. _

4.0 SYMPTOMS

Indications of a malfunction and/or loss of an auxiliary transformer can

, be any one or more of the following:

4.1 Auxiliary transformer IA differential current trip, window C-8 4.2 Auxiliary transformer IA fault pressure trip, window C-18 4.3 Auxiliary transformer 1A alarm panel, window C-48 4.4 Auxiliary transformer 1A 4KV ground, window C-28 /R1 4.5 4KV switchgear (svgr.) 1A2 feeders overload trip, window B-41 /R1 4.6 Auxiliary transformer breaker failure backup trip, window C-9 4

FOR INFORMAT10H 00LY This document is not controlled. Before use, wify inferrnation with a controlled document.

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ST. LUCIE UNIT 1 l

OFF-NORMAL OPERATING PROCEDURE NO. 1-0910032, REVISION 1 AUIILIARY TRANSFORMER OFF-NORMAL OPERATION t

4.0 STMPTOMS

(continued) 4.7 Auxiliary transformer 1A 6.9KV ground, window C-38 m

4.8 6.9KV swgr. lAl feeders overload trip, window B-42 4.9 6.9KV swgr. lAl dif ferential current trip, window B-3 4.10 4KV swgr.1A2 dif farential current trip, window B-13

, 4.11 6.9KV swgr.1A1/4KV swgr. IA2 undervoltage, window B-23 4.12 6.9KV/4KV swgr. IA1/1A2/1A3/1AB differential lockout relays failure, window B-4 4.13 Auxiliary transformer 1B differential current trip, window C-10 1

4.14 Auxiliary transformer 1B fault pressure trip, window C-20 4.15 Auxiliary transformer 1B alarm panel, window C-50 4.16 Auxiliary transformer 1B 4KV ground, window C-30 4.17 4KV 1B2 feeders overload trip, window A-41 l 4.18 Auxiliary transformer IB 6.9KV ground, window C-40 4.19 6.9KY swgr.131 feeders overload trip, window A-42 l 4.20 6.9KV svgr.1B1 differential current trip, window A-3 4.21 4KV swgr.1B2 differential current trip, window A-13 4.22 6.9KY swgr.1B1/4KV swgr.132 undervoltage, window A-23 4.23 6.9KV/4KV swgr.1B1/1B2/183 differential lockout relays failure, window A-4 l .

4.24 Fire pump running, window F-8 4.25 Transformer deluge operating, window F-16 4.26 Differential "fw/nw" trip, line repeat window 1 4.27 Dif ferential "fe/ne" trip, line repeat window 13 4.28 Differential "l/p" trip, line repeat window 14 4.29 OCB2W 8W43 St. Lucie Line No. 2 trip, line repeat window 4 1

j 4.30 OCB2M 8W40 St. Lucie Line No. 2 trip, line repeat window 10 4.31 Incal backup trip, line repeat window 19 4.32 OCB1W 8W33 St. Lucie Line No. I trip, line repeat window 6

, 4.33 Automatic starting of one or both diesel generators

[ 4.34 Various Control Room electrical metering and switch indicating lights

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4 4 Page 3 of 7 ST. LUCIE UNIT 1 0FF-NORMAL OPERATING PROCEDUP! NO. 1-0910032, REVISION 1 AUKILIARY TRANSFORMER OFF-NORMAL OPERATION

5.0 INSTRUCTIONS

5.1 Ioss of Auxiliary Transformer Breakers *

. 5.1.1 Indications - the following are some of the indications that will accompany a loss of an auxiliary transformer breaker:

1. Loss of power to the associated 6.9KV or 4KV swgr. /R1

2. Various alarms from Section 4.0

3. Possible loss of power to the switchyard east or west bus 5.1.2 Causes - any one of the following could cause an automatic protective trip of an auxiliary transformer breaker:

1. Current overload

2. Associated bus lockout due to currant differential

3. Generator primary trip caused by any one or more of the l following:

A. Main transformer IA or 1B fault pressure B. Main transformer 1A or 1B differential current trip C. Turbine trip D. Generator differential current trip E. Generator grcund trip F. Generator negative sequence trip G. Generator distance relay trip (carrier current)

H. Generator instantaneous rate of current rise trip I. Auxiliary transformer IA or IB differential current trip i J. Switchyard east-west beckup panel trip

4. Generator backup trip caused by any one of the following:

A. Auxiliary transformer IA or 1B fault pressure B. Main transformer 1A or 1B ground C. Turbine trip D. Generator and main transformer differential current trip E. Generator field failure F. Any auxiliary transformer breaker overcurrent trip

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ST. LUCIE UNIT 1 0FF-NORMAL OPERATING PROCEDURE NO. 1-0910032, REVISION 1 L AUIILIARY TRANSF010ER OFF-NORMAL OPERATION

5.0 INSTRUCTIONS

(continued) E 5.1 (continued) ,

5.1.3 Automatic Actions

1. Automatic closure of startup transformer breakers NOTE: If startup transformer is subsequently lost, refer to Operating Procedure 0910030, Startup Transformer Off-Normal Operation.

2. Ioss of various running equipment will cause operation of their respective protective features.

5.1.4 Operator Actions

1. If any automatic action has not occurred, the operator should manually execute the required steps.

2. Determine the cause of the trip from Section 5.1.2 and take necessary steps to correct.

3. Notify the load dispatcher of the plant conditions.

5.2 Transformer Fire

5.2.1 Indications - the following are some of the indications that could accompany a transformer fire

l

1. Possible loss of power to associated buses

2. Various alarms from Section 4.0 5.2.2 Causes for a transformer fire are numerous. A few are:

1. Shorts

2. Grounds

3. Oil leak l 4. Cooling equipment failure

( 5.2.3 Automatic Actions l

1. If a loss of power, see Section 5.1 of this procedure or l Operating Procedure 0910030.

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. Page 5 of 7 OFF-NGtMAL OPERATING PROCEDURE NO. 1-0910032, REVISION 1 -

AUXILIARY TRANSFOPJER OFF-NORMAL OPERATION

5.0 INSTRUCTIONS

(continued) 5.2 (continued) w 5.2.4 Operator Actions

1. Synchronize the startup transformers to the 6.9KV and 4.16KV buses and remove the auxiliary transformers from

~

service on the affected side (s). /R1

2. If startup transformers are not available, insure diesel generator (s) is/are loaded carrying the vital buses.

3. Sound fire alarm.

4. Notify plant personnel over the page of the nature and location of the fire.

5. Insure fire pumps are running.

6. Insure trans'for ar deluge system is operating.

7. Start diesel generator on affected side (s).

8. Notify local fire department.

9. Notify load dispatcher of plant conditions.

10. Determine if fire is internal or external to the transformer or both, if possible.

11. Open power to transformer cooling equipment (see 5.4.9 for breaker numbers).

5.3 6.9KV or 4.16KV Cround /R1 l

5.3.1 Indications - audible alarm in Control Room.

5.3.2 Causes - one or more of the following:

1. Grounded 4.16KV winding on the auxiliary transformer /R1

2. Grounded 6.9KV winding on the auxiliary transformer l 5.3.3 Automatic Actions

1. None l

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Page 6 of 7 ST. LUCIE UNIT 1 0FF-NORMAL OPERATING PROCEDURE No. 1-0910032, REVISION 1 AUXILIARY TRANSFORMER OFF-NORMAL OPERATION

5.0 INSTRUCTIONS

(continued) 5.3 (continued) .

5.3.4 Operator Actions

1. If time allows, synchronize the startup transformer with the affected bus (es).

2. Isolate the af fected transformet.

3. Determine the cause of the ground.

4. Notify the load dispatcher of plant conditions.

5.4 Transformer Alarm Panel Malfunction 5.4.1 Indications - audible alarm in Control Room.

5.4.2 Causes - listed in Section 5.4.4.

5.4.3 Automatic Actions

1. Fault pressure operates the generator backup trip (Section 5.1.2). All other features do not cause initiation of automatic protective features.

5.4.4 Operator Actions

1. Investigation of the elarm to determine the cause and correction as necessary of the following conditions:

A. Loss of 125V DC transformer alarm power - check the DC supply breaker and bus voltage.

B. Pressure relief device - isolate the transformer as per Section 5.3.4.

1 i C. Iow oil flow - check oil flow gage and pump l operation.

D. Atmoseal tank low oil level - inspect liquid level gage mountad on transformer. If level is low, reduce load on transformer and inspect for leaks.

l If any oil leaks are found, isonte the transformer as per Section 5.3.4.

E. Top oil temperature (900C) or thermal relay (hot spot) (1200 C) - shift fans and pump to manual. If alarm persists, isolate the transformer per Section 5.3.4.

F. Gas Detector - isolate the transformer as per Section 5.3.4.

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Page 7 of 7 ST. LUCIE UNIT 1 0FF-NORMAL OPERATING PROCEDURE NO. 1-0910032, PJEVISION 1 AUZILIARY TRANSFORFMR OFF-NORMAL'OPERATICN j

5.0 INSTRUCTIONS

(continued) 5.4 (continued) 5.4.4 (continued) - ,

1. (continued)

G. Loss of Cooling Power (1) Check thermal circuit breakers to pump and fans ON.

(2) Check CB-8 master circuit breaker to fans ON.

(3) Insure 480V AC normal and/or alternate power is available and supplying the cooling equipment.

(4) If fans and pump cannot be restarted, reduce transformer load. If high temperature alarm is reached, isolate the transformer per Section 5.3.4.

H. Loss of Control Power (1) Check fans and pump.

(2) Check control circuit breaker 8C ON.

(3) Check control fuse, replace if necessary.

(4) If fans and pump c'nnot a be restarted, reduce transformer load. If high temperature alarm is reached, isolate transformer per Section 5.3.4.

I. Ioss of Source il or Source' #2' and/or transfer to standby power - check controls, fans and pump operating. Then check 4807-MCC breakers.

NORMAL ALTERNATE 1A 40814 41605 1B 41609 , 40804 /R1 1

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Page 1 of 12 i

FLORIDA POWER & LIGHT COMPANY i ST. LUCIE UNIT 2 j OFF-NORMAL OPERATING PROCEDURE NO. 2-0110030 REVISION 3 l

1.0 TITLE

CEA 0FF-NORMAL OPERATION AND REALIGNMENT 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group March 10 1983 Approved by C. M. Wet,hy Plant Manager March 10 19E Revision 3 Reviewed by FRG d o e urf #7 19 lI Approved by M //)!f/2 M M _- Plant Itanager MN .2 5~-19 Q 3.0 PURPOSE AND DISCUSSION: 0

3.1 Purpose

This procedure provides instructions for operator action during abnormal operation and realignment of Control Element Assemblies (CEA) while in Modes 1 or 2. /R3

3.2 Discussion

1. The action statements applicable to a stuck or untrippable CEA, to two or more inoperable CEAs and to a large misalignment

(>15 inches) of two or more CEAs, require a prompt shutdown of tIIe reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of Shutdown Margin.

2. For small misalignments (<15 inches) of the CEAs in a given group, there is 1) a small effect on the time d. pendent. long term power distributions relative to those used in generating LCOs and LSSS setpoints, 2) small effect on the available Shutdown Margin, and 3) a small af fact on the ejected CEA worth used in the safety analysis. Therefore, the action statement associated with small misalignments of CEAs permits a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time interval during which attempts may be made to restore the CEA to within its alignment requirements. The one hour time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropri' ate cdrective action to realign the CEAs and (3) minimize the effects of xenon redistribution.

FOR INFORMATION ONLY iliis document is not controlled. Before use, yerify inkmtion with a controlled document.

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'. Page 2 of 12 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE No. 2-0110030, REVISION 3 CEA 0FF-NORMAL DPERATION AND REALIGNMENT 3.0 PURPOSE AND DISCUSSION: (continued) 3.1 (continued)

3. Overpower margin is provided to protect the core in the event of a large misalignment Q15 inches) of a CEA. However, this misalignment would cause distortion of the core power distribution. This distribution may, in turn, have a <

significant effect on 1) the available Shutdown Margin, 2) the time dependent long term power distributions relative to those >

used in generating LCOs and LSSS setpoints, and 3) the ejected l CEA worth used in the safoty analysis. Therefore, the action )

statement associated with the large misalignment of a CEA l requires a prompt realignuent of the misaligned CEA.

4 The action statements applicable to misaligned or inoperable CEAs include requirements to align the operable CEAs in a given group with the inoperable CEA. Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LCO and LSSS setpoints. However, extended operation with CEAs significantly inserted in the core may lead to perturbations in

1) local burnup, 2) peaking factors, and 3) available Shutdown Margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO and LSSS setpoint determination. Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverre conditions from developing.

4.0 3YMProMS

4.1 Upon observation from ADS, digital position indicators, or data processor, one or more CEAs are misaligned, dropped, or slipped.

4.2 CEA position +/-4 inch deviation (ADS) alarm 4.3 CEA position +/-4 inch (DDPS) alarm (Dropped CEA only) 4.4 CEA position +/-8 inch (DDPS) alarm (Dropped CEA only) 4.5 CEA motion inhibit alara 4.6 Dropped CEA CEDMCS alarm 4.7 Auto Withdrawal Prohibit alarm 4.8 CEA PDIL and PPDIL (DDPS) alarms (Dropped CEA only) 4.9 CEA PDIL and PPDIL (ADS) alarms 4.10 Group out of sequence (ADS) alaru 4.11 Group out of sequence (DDPS) alarm (Dropped CEA only) 4.12 REG CEA short term, steady state insertion alarm l /R3 l

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, Page 3 of 12 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0110030 REVISION 3 MA 0FF-NORMAL OPERATION AND REALIGNMENT

5.0 INSTRUCTIONS

5.1 ONE OR HORE CEA(s) INOPERABLE OR MISALIGNED FROM ANY OTHER CEA IN ITS GROUP BT MORE THAN 7.0 INCHES EUI LESS THAN OR EQUAL TO 15.0 INCHES 5.1.1 Immediate Automatic Actions -

1. CEA motion inhibit.

5.1.2 Ismediate Operator Action:

1. Place CEDMCS control panel in OFF.

2. Deteraire if any mismatch exists between reactor power and turbine power. If a mismatch exists, adjust turbine power te equal reactor power.

5.1.3 Subsequent Operator Action:

1. Determica from symptoms and CEA position indications the cause of the inoperability or if the CEA is operable but miseligned, in accordance with Appendix "B". During the determination of the cause of the misaligned CEA, maintain reactor power at or below the level of step 5.1.2.2.

2. Ensure automatic functions have initiated.

3. Within one hour, perform the following:

a) Restore to operable status within its specified alignment requirements (within 7.0 inches of other CEAs in its group) per Appendix A.

O, E.

b) Declare the CEA inoperable and assure the Shutdown Margin requirements of T.S. 3.1.1.1 are satisfied.

Operation in Modes 1 and 2 may continue pursuant to the requirements of T.S. 3.1.3.6.

l 1. Align the remainder of the CEAs in the group to within 7.0 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown in T.S. Figure 3.1-2.

2. Ihe Shutdown Margin requirement of Specifiestion 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , gR, c) Be in Hot Standby within six hours.

I CAUTION: If a CEA becomes misaligned by 15 inches or more, but does not drop while performing the above instruction, proceed to Section 5.2. If l a CEA drops while performing the above i instruction, proceed to Se:: tion 5.3

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. ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE No. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT 5.0 INSTRUCTIONS : (continued) 5.1 (continued). i 5.1.3 (continued)

4. Upon ascertaining that plant conditions are normal, __

return to the desired operating power level in accordance with OP 2-0030123. The guidelines for ASI oscillation control should be impltmented appropriately.

5. If excessive frictica or mechanical interference prevents movement of the CEA or the CEA is untrippable, ensure appropriate Shutdown Margin within one hour and be in Hot Standby in six hours. See OP 2-0030125, " Turbine Shutdown Full Load to Zero load," and OP 2-0110055,

" Surveillance Requirements for Shutdown Margin, Modes 1 and 2 (Critical).

6. With more than one CEA inoperable or misaligned from any other CEA in its group by 15 inches (indicated position) or more, be in Hot Standby within six hours.

5.2 ONE CEA MISALIGNED BY GREATER THAN 15 INCHES BUT NOT A DROPPED CEA 5.2.1 Immediate Automatic Action:

1. CEA motion inhibit.

5.2.2 Immediate Operator Action:

1. Place CEDMCS control panel in OFF.

2. Determine if any mismatch exists between reactor power and turbine power. If a mismatch exists, adjust turbine power to equal reactor power.

5.2.3 Subsequent Operator Actions:

1. Determine from symptoms and CEA position indications the cause of the inoperability or if the CEA is operable but misaligned, in accordance with Appendix "B". During the determination of the cause of the misaligned CEA, maintain reactor power at or below the level of step 5.2.2.2.

2. Ensure automatic functions have initiated.

3. Refer to Plant Curve Book and obtain the most recent F{value.

4 a) <1.5), restore Within the CEA (per 15 Appendix minutesA) (25 minutes if F[770 inches of all to within other CEAs in its group.

0,,R, b) Within one hour of misalignment, reduce power to

<70% of RATED THERMAL POWER.

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, ST. LUCIE UNIT 2 0FF-N0ttMAL OPERATING PROCEDURE NO. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT 9

5.0 INSTRUCTIONS (continued) 5.2 (continued) 5.2.3 (continued)

5. Within one hour, perform the following: .

a) Restore to operable status within its specified alf gnment requirements (within 7.0 inches of other CEA's in its group) per Appendix A.

3 b) Declare the CEA inoperable and assure the Shutdown Margin requirements of T.S. 3.1.1.1 are satisfied.

Operation in Modr.s 1 and 2 may continue pursuant to the requirements of T.S. 3.1.3.6.

1. Reduce power to f,70% of the TRERMAL POWER level prior to misalignment IF THE PRE-MISALIGNMENT ASI WAS MORE NEGATIVE THAN -0.15 (ASI g Units).

2. Align the remainder of the CEA's in the group to within 7.0 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown in T.S. Figure 3.1-2.

3. The Shutdown Margin requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I E c) Be in Hot Standby within six hours.

6. Upon ascertaining that plant conditions are normal, return to the desired operating power level in accordance with OP 2-0030123. The guidelines for ASI oscillation control should be implemented appropriately.

7. If excessive friction or mechanical interference prevents movement of the CEA, or the CEA is untrippable, ensure l

appropriate Shutdown Margin within one hour and be in Hot Standby in six hours. See OP 2-0030125, " Turbine Shutdown Full Load to Zero Load" and OP 2-0110055, Surveillance Requirements for Shutdown Margin Modes 1 and 2 (Cricical)".

8. With more than one CEA inoperable or misaligned from any other CEA in its group by 15 inches (indicated position) or more, be in Hot Standby within six hours.

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, ST. LUCIE UNIT 2

OFF-NORMAL OPERATING PROCEDURE NG. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT

5.0 INSTRUCTIONS

(continued) 5.3 DROPPED CEA RECOVERY 5.3.1 Immediate Automatic Action:

1. CEA motion inhibit.

5.3.2 Immediate Operator Action:

1. Immediately reduce turbine load to match the reactor power and to return the plant conditions to within LCO's.

5.3.3 Subsequent Operator Action:

1. Determine from symptoms and CEA position indications the cause of the inoperability or if the CEA is operable but aisaligned, in accordance with Appendix "B". During the determination of the cause of the dropped CEA, maintain reactor power at or below the level of step 5.3.2.1.

2. Enaure automatic functions have initiated.

3. Refer to Plant Curve Book and obtain the most recent FR value.

4 a. Within 15 minutes (25 minutes if FR <1.5), restore the CEA (per Appendix A) to within 770 inches of all other CEA's in its group, gR

. b. Within one hour of misalignment, reduce power to 170%

of RATED THERMAL POWER.

5. Within one hour, perform the following:

a. Restore to operable status within its specified alignment requirements (within 7.0 inches of other CEA's in its group) per Appendix A.

gR,

b. Declare the CEA inoperable and assure the Shutdown Margin requirements of T.S. 3.1.1.1 are satisfied.

Operation in Modes 1 and 2 may continue pursuant to the requirements of T.S. 3.1.3.6.

1. Reduce power to 170% of the THERMAL POWER level prior to misalignment IF THE PRE-MISALIGNMENT ASI WAS MORE NEGATIVE THAN -0.15 (ASIg Units). ,

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, ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT

5.0 INSTRUCTIONS

(continued) 5.3 (continued) 5.3.3 (continued)

5. (continued)

b. (continued) ,

2. Align the remainder of the CEA's in the group to within 7.0 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown in T.S. Figure 3.1-2.

3. The Shutdown Margin requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

9K c) Be in Hot Standby within six hours.

6. If excessive friction or mechanical interference prevents movement of the CEA, or the CEA is untrippable, ensure appropriate Shutdown Margin within one hour and be in Hot Standby in six hours. See OP 2-0030125, " Turbine Shutdown Full Load to Zero load" and OP 2-0110055,

" Surveillance Requirements for Shutdown Margin, Modes 1 and 2 (Critical)".

7. With more than one CEA inoperable or misaligned from any other CEA in its group by 15 inches (indicated position) or more, be in Hot Standby within six hours.

8. Upon ascertaining and correcting the cause for the dropped CEA, recovery of the CEA can be made as follows:

a. The CEA should be recovered by a slow, smooth withdrawal using small increments of movement.

Preferably, the movement increments should be three steps or less. The period of time for recovering the CEA should be approximately 10 minutes.

b. Reactor power should te maintained constant by boration while withdrawing the dropped CEA.

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/R3 i

Page 8 of 12

. ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT

5.0 INSTRUCTIONS

(continued) 5.3 (continued) 5.3.3 (continued)

8. (continued)

c. Following the return of the CEA to its group, operation should be maintained at the existing power level for at least one hour

in order to allow assessment ** of resultant power distributions and/or azimuthal tilts.

d. Upon ascertaining that a normal power distribution is present and that the plant conditions are normal, return to the desired operating power level in accordance with OP 2-0030123. The guidelines for ASI oscillation control should be implemented appropriately.

It may be necessary to operate at this reduced power level for as long as 24 to 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months in order to reduce the azimuthal oscillatien and the T

resultingvaluesofF[,T,Fresulting from a dropped OEA.g, and

- Notify the Reactor Engineering Supervisor.

6.0 REFERENCES

6.1 St. Lucie Unit 2 Technical Specifications 6.2 CEDMCS Tech Manual 6.3 St. Lucie Unit 2 Operating Procedure 2-0030123, " Reactor Operating Guidelines During Steady State and Scheduled Ioad Changes" 6.4 CE letter, L-CE-8859, dated June 20,1983, "New Issue of Core Operating Guidelines for St. Lucie 2" 6.5 St. Lucie Unit 2 Operating Procedure 2-0030125, " Turbine Shutdown Full Ioad to Zero Ioad" 6.6 St. Lucie Unit 2 Operating Procedure 2-0110055, " Surveillance Reqtfirements for Shutdown Margin, Modes 1 and 2 (Critical)"

7.0 RECORDS REOUIRED:

7.1 Normal log entries

/R3

l . .

P:g2 9 cf 12 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE No. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT APPENDIX A - CEA REALIGNMENT 1.0 Limits and Precautions:

1.1 This procedure is required for CEA off-normal operation and realignsment while in Modes 1 or 2.

1.2 Regulating CEAs should be withdrawn in sequence and overlap between groups shall not exceed 40 percent.

1.3 Do not exceed a sustained SUR of 1.4 DPM (alarm 1.3 DPM).

1.4 Criticality shall be anticipated any time CEAs are being withdrawn.

1.5 If deviation between CEAs in any group approaches 3 inches, stop group withdrawal and realign CEAs.

1.6 Individual CEA positions within the group shall be determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except when the CEA position deviation circuit is out of service, then verify CEA positions at least once every four hours.

1.7 CEAs shall be limited in physical insertion as shown by Technical Specification Figure 3.1-2 (insertion limit curves).

1.8 Any changes to this procedure shall be in accordance with QI 5-1.

2.0 Instructions

2.1 Alignment of a CEA which is below its group when in Mo,'e 2 (suberitical): g

1. Utilizing MANUAL SEQUENTIAL control, insert the misaligned group a minimum of 4 inches.

2. Utilizing MANAUAL INDIVIDUAL control, withdraw the low CEA to the group position.

3. Monitor the position of all CEAs in the group for proper alignment.

2.2 Alignment of a CEA which is above its group, prior to criticality:

1. Utilize MANUAL INDIVIDUAL control, and insert the high CEA to the group position.

2. Monitor the position of all CEAs in the group for proper alignment.

4

/R3

Page 10 of 12 ST. LUCIE UNIT 2 OFF-NORMAL OPERATING PROCEDURE NO. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT APPENDIX A - CEA REALIGNMENT (continued)

I 2.0 (continuad) 2.3 Alignment of an above or below CEA with the reactor critical

1. Utilize MANUAL INDIVIDUAL control to return the misaligred CEA to the group position.

2. If necessary, alternate between MANUAL INDIVIDUAL control of the misaligned CEA and MANUAL SEQUENTIAL control of its associated group to maintain the desired reactor power level.

. 3. Monitor the position of all CEAs in the group for proper alignment.

4. Utilize MANUAL GROUP control as required to readjust the group positions for proper automatic sequencing.

V 4

Page 11 of 12 0FF-NORMAL OPERATING PROCEDURE NO. 2-0110030, REVISION 3 CEA 0FF-NORMAL OPERATION AND REALIGNMENT APPENDIX B - DROPPED CEA INVESTIGATION 1.0 Determine that the dropped CEA is functional, select Manual Individual (MI) on the Mode Select switch, select the affected CEA on the Individual CEA Selection switches, and select the group of the af fected CEA on the Group Select switch. Momentarily press the Bypass Enable push button and press and hold the CMI Bypass push button. Withdraw the affected CEA until the Core Mimic DRC light and the Lower Electric Limit light both deenergize. Insert and withdraw the affected CEA and check for smooth operation and normal indications. Reactor power shall not be increased above the value present at the time the dropped CEA occurred. If the affected CEA is determined to be functional realign the CEA per the dropped CEA procedure.

I 2.0 Guidelines for Investigating Dropped CEAs:

Dropped CEAa have occurred from:

A. Tripped CEA Disconnect B. Loss of CEA Subgroup logic function Symptoms

\

A. 1. CEA Disconnect in OFF, red light of f, green light on.

2. CEA Disable lights red for affected CEA.

B. Timer Failure lights red for affected CEA.

Trouble Shooting A. Call I & C specialist in.

B. Connect visicorder to coil monitor of affected CEA.

C. Close/ check closed CEA disconnect of affected CEA and record trace of UG.

D. Check trace for proper SCR firing and proper coil current.

E. If D is not satisfactory, troubleshoot UG circuits.

F. If D is satisfactory, attempt to withdraw the CEA while recording Coil Monitor trace. Check traces for SCR firing, coil current, and timing. Troubleshoot as required.

Place Subgroup of affected CEA on maintenance bus prior to troubleshooting that af fects any of the other Subgroup CEAs.

A e

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Page 12 of 12 ,l ST. LUCIE UNIT 2 j

OFF-NORMAL OPERATING PROCEDURE NO. 2-0110030 REVISION 3 :

CEA OFF-NORMAL OPERATION AND REALIGNMENT 'g l

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-1 1

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2

OFF-NORMAL OPERATING PROCEDURE NO. 2-0120036

'l REVISION 1

.i

'j

1.0 TITLE: ,__,,,

d PRESSURIZER RELIEF /SAFETT VALVE - 0FF-NORMAL OPERATION 1 2.0 REVIEW AND APPROVAL: -

d

.$.. .. ......... .. Reviewed by Facility Review Group February 8 19 1

.......Appr_o.ved by C. M. Wethy Plant Manager February 11 1983

! Revision 1 ReviewN b FRG Sud I, k /7 19 8 g _,

. Approved by N /h hb Mr

/' Id2..

i i

3.0 PURPOSE AND DISCUSSION:

a FOR INFORMATTON OHLY

.t This document is not conTielleZYefore use,

3.1 Purpose

verify information with a controlled document.

E!

d This procedure provides operator actions to be performed in the event of:

t{g j 1. Pressurizer relief or safety valve leakage.

il i 2. Malfunction of a Pressurizer relief valve causing it to open j and remain open.

.J

_! 3. Malfunction of a Pressurizer safety valve causing it to open j and remafn open.

3.2 Discussions j A stuck open Pressurizer relief or safety valve could result.in :

f I

depressurization of the Reactor Coolant System and the formation.of.

voids in the system and possible formation of a steam bubble in the

.- reactor vessel. Such occurrences would require immediate actions as j described in ECP 2-0120042, " Loss of Reactor Cool. ant". -

I 4.0 SYMPTOMS:

J j 4.1 Any one or more of the following is indicative of a Pressurizer relief cr safety malfunction: -

4

! 4 1.1 An unexplained increase in temperature on:

TIA-1106: Pressurizer relief line temperature (V-1475) -

TIA-1107: Pressuriser safety valve V-1200 line temperatore- -

j TIA-1108: Pressurizer safety valve V-1201 Line temperature y TIA-1109: Pressurizer safety valve V-1202 line temperature-TIA-1110: Pressurizer relief line temperature (V-1474) - - /R1

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Page 2 of 5

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ST. LUCIE UNIT 2

.] 0FF-NORMAL OPEEATING PROCEDURE NO. 2-0120036, REVISION 1

.~.~ ;. . ..

PRESSURIZER RELIEF /SAFETT VALVE - 0FF-NORMAL OPERATION _... .... .. ....

1

'J 4

.] 4.0 STMPTOMS: (continued) _.

i

~

4.1 (continued) li

,] 4.1.2 Yali6 annunciation of:

~

Jj Pressurizer Relief Line High Temperature N Pressuriser Safety Relief Y-1200 High Discharge Temperature l Pressurizer Safety Ealief Y-1201 High Discharge Temperature 1 Pressurizer Safety Relief V-1202 High Discharge Temperature Safety / Relief Valve Open t

., 4.2 Any one or more of the following could be indicative of a Pressurizer relief or safety malfunction: -

., TIA-1116: Quench Tank temperature increase -

PIA-1116: Quench Tank pressure increase

[j LIA-1116: Quench Tank level increase .. - .

a f.' Quench Tank High Pressure. alarm -

A

~j Quench Tank High Temperature alarm .

Quench Tank High/ Low Level alarm

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. Page 3 of 5 t . ST. LUCIE UNIT 2

' 0FF-NORMAL OPERATING PROCEDURE No. 2-0120036, REVISION 1

'. PRESSURIZER RELIEF / SAFETY VALVE - 0FF-NORMAL OPERATION l 5.0 INSTRUCTIONS: _ _ , ,

T 4

5.1 Immediate Automatic Action:

i i None 1

l .l 5.2 Immediate Operator Action:

.I l .j 5.2.1 Safety valve Leakage:

1

,' 1. If a temparature increase is detected on TIA-1107,

"}* TIA-110P, or TIA-1109, leakage 14 from one of the respective safety valves. Refer to Off-Normal

! OP 2-0120031, " Excessive RCS Leakage".

A

2. If flow is indicated on the acoustic flow monitor, determine which safety valve and refer to Off-Normal OP 2-0120031, " Excessive RCS Leakage".

g 5.2.2 Relief Valve Leakage: _, ,, , _ , , , , ,

l

,j 1. Determine which relief valve is leaking.

' Ul

l. NOTE: One relief valve will normally be isolated during power operations.

! A. If a temperature increase is detected on TIA-1106 or

.l .

TIA-1110, identify leak as follows: -

TIA-1106: V-1475 TIA-1110: V-1474 1 B. Check acoustic flow monitor to determine which relief j valve is leaking.

I

, 2. If V-1474 is indicating flow, close MV-1476 and monitor

, TIA-1110. Ensure temperature starts to decrease. -

-j -

3. If V-1475 is indicating flow, close MV-1477 and monitor

, TIA-1106. Ensure temperature starts to decrease.

l

4. If the acoustic monitor is not indicating flow, perform the following:

f- A. If temperature increases on TIA-1106, close MV-1477.

} Verify temperature decrease.

i j B. If temperature increases on TIA-1110, close MV-1476.

-; Verify temperature decrease.

I

/R1

'4 4

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Page 4 of 5 ST. LUCIE UNIT 2 .

j OFF-NORMAL OPERATING PROCEDURE NO. 2-0120036 REVISION 1 PRESSURIZER RELIEF / SAFETY VALVE - 0FF-NORMAL OPERATION - . . ..

.2 5.0 INSTRUCTIONS: (continued) _ _ .

5.2 (Cont.)

'; 5.2.3 Safety valve opens: _ , , , _ ,_

1. Refer to E0P 2-0120042, " Loss of Reactor Coolant".

, 5.2.4 Relief Valve Opens and Fails to Close:

1. Observe the red / green indicating lights and acoustic flow

. monitors to determine which relief valve has opened.

} 2. Select relief valve control switch to OVERRIDE position. Verify valve closure by observing position indicating lights, discharge line temperature, Quench Tank parameters. Pressurizer pressure, and the acoustic .

1 flow monitor. -

i 3. If Pressuriser pressure continues to decrease below 2350 p'sia and/or Quench Tank parameters indicate that the valve has not closed as required, then immediately close respactive motor operated valve.

4

4. If it is not known which PORY is stuck open, immediately shut both relief isolation valves.

MV-1476 for V-1474 -

MV-1477 for V-1475 -

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Page 5 of 5 ST. LUCIE UNIT 2 -

7 0FF-NORMAL OPERATING PROCEDURE NO. 2-0120036, REVISION 1

. 3.. . ..

PRESSURIZER RELIEF /SAFETT VALVE - 0FF-NORMAL OPEEATION .... ... ... ... ..

q b 5.0 INSTRUCTIONS: (continued) .,_,,,,,

-)

.i 6 5.3 Subsequent Operator Action:

"} 5.3.1 Safety Valve Malfunction:

..)

'i

1. Is Modes 1, 2, and 3 with one Pressurizer code safety inoperable, either restore to operable in 15 minutes or 1 he in at least Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in

[i-) Hot Shutdown within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . /R1 d 2. In Mode 4, and 5 with no Pressurizar code safe.y 1] operable, immediately suspend all operations uvolving 7(j positive reactivity changes and place an operable

. Shutdown Cooling Loop into operation.

j 5.3.2 Relief Valve Malfunction: _. . . . . . .

p 1.

j)

Investigate and correct cause of malfunction. .

,i, .

6.0 REFERENCES

=

?,

.l . 6,1 CE P&ID E-13172-310-108 and 109 -

.- /R1

, .l

'.) 6.2 St. Lucie Unit 2 FSAR, Section 5.2.4.4.C and 5.5.3.2

]j. 6.3 St. Lucie Unit 2 Technical Specifications 3.4.2, 3.4.2.1 and 3.4.4 /R1

.il

.a 7.0 RECORDS REQUIRED: . _ . .

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FLORID & POWER & LIGHT COMPANY ST. LUCIE UNIT 2

{'

OFF-NORMAL OPERATING PROCEDURE No. 2-0530030 REVISION 1

1.0 TITLE

' ~ " ~

~

WASTE GAS SYSTEN - 0FF NORMAL OPERATION

?.0 REVIEW AND APPROVAL: , =,_,,,_,,,,,,

l ... . ............. Reviewed by Facility Review Group December 28 19 1 1

_ ...........Approv_ed by J. H. Barrow (for) Plant Manager December 28 1982 _ _ , , , , _ _ .

Revision 1 Ravi d by FRG hs I g k- /7 19 g _

. ,_,,.,__,,,_,Aggroved by v

d -

b b t Manager M _ / 7 1,9 M ___

v 3.0 PURPOSE AND DISCUSSION: __ ,_

i 3.1 This procedure provides instructions and guidelines for actions to .

be taken when abnormal Wasta Gas System conditions exist. - . .

3.2 Releases of gas due to large system leaks or uncontrolled releases through the plant vent are covered in Off-Normal OP 2-0530031,

" Uncontrolled Release of Radioactive Gas".

4.0 SYMPTOMS

A number of abnormal conditions with different symptoms and operator actions are covered in this procedure and will be described in Section 5.0, Instructions, under the respective aberrmal condition - ' -

heading.

4.1 Excessive use of Nitrogen . :- .

T 4.2 High Oxygen in the Syst=

FOR I;;pgRMATl0N ONLY 4.3 Ioss of both Waste Gas Compressors s doeurnent ;* "'I confrolled' Be '

4.4 High Gas Surge Tank Pressure [*rlfy informe%n 4 * **"I'*II*d dm

l

! 4.5 Waste Gas Compressor Diaphragm Leak . .

l l 4.6 Weste Gas Decay Tank Isolation Valve Imak -

l l

Prga 2 cf 7 ST. LUCIE UNIT 2

, OFF-NORMAL OPERATING PROCEDURE NO. 2-0530030, REVISION 1 WASTE GAS SYST1!M - 0FF NORMAL OPERATION __

5.0 INSTRUCTIONS

5.1 Excessive Use of Nitrogen 5.1.1 Normal Gas Decay Tank Fill Rate

1. Symptoms:

NOTE: The below symptoms are indicative of a leak from the system.

A. low Nitrogen Manifold Supply Pressure alarm, (later) psig.

B. Abnormal decrease in nitrogen inventory.

. C. Increasing radiation level on Plant Vent Monitor.

2. Ismediate Operator Actions - None -

3. Subsequent Actions:

A. If the local Radiation Monitor or Plant Vent Monitor alarms on high level, refer to Off-Normal OP 2-0530031, " Uncontrolled Release of Radioactive Gas".

B. Review any operation being performed or recently performed for proper line-up.

NOTE: In the following step, caution must be used when isolating components with respect to any operations that may be in progress.

C. Conduct a systematic check of the Vent Gas Surge System by isolating components from the Nitrogen System and the Vent Gas Surge Header one at a time.

D. If leaks are suspected around a Waste Gan Compressor, l stop the operating compressor and start the standby i compressor before isolating.

l t

I l

l

Pega 3 of 7 ST. LUCIE UNIT 2

, OFF-NORMAL OPERATING FROCEDURE NO. 2-0530030, REVISION 1 WASTE GAS SYSTEN - OFF NORMAL OPERATION ~

1

5.0 INSTRUCTIONS

(Cont.) _,

5.1 (Cont.)

5.1.2 Abnormal Gas Decay Tank Fill Rate

, 1. Symptoms:

A. Low Nitrogen Manifold Supply Pressure alarm, (later) psig.

B. Abnormal decrease in nitrogen inventory.

C. Gas Surge Tank High Pressure alarm (15 psig).

D- Gas Decay Tank High Pressure alarm (175 psig).

E. Auto start of standby Wasta Cast Compressor.

2. Immediate Operator Actions - None

3. Subsequent Actions:

A. Review any operation being performed or recently performed for proper valve lineup.

NOTE: In the following step, caution must be used when isolating components suspected of having in-leakage to the vent gas surge header with respect to any operations that may be in progress.

B. Conduct a systematic check of the vent gas surge system by isolating components from the Nitrogen System and the vent gas surge header one at a time.

C. If nitrogen pressure is decreasing at an abnormal rate, readjust the nitrogen supply header pressure -

regulator to approximately 20 psig until the leak is located to prevent exhausting the nitrogen supply.

D. Check closed A0V-6300 (Reactor Drain Tank vent valve), A0V-6208 (Nitrogen stop to flash tank), and A0V-1400 (Quench Tank vent valve). If any of these valves are open, a continuous bleed of nitrogen from the Nitrogen System to the vent gas system will occur. /R1

Peg 3 4 cf 7 i

ST. LUCIE UNIT 2

, OFF-NORMAL OPERATING FROCEDURE NO. 2-0530030 REVISION 1 WASTE GAS SYSTEM - 0FF NORMAL OPERATION _, , ,, ,

5.0 INSTRUCTIONS

(Cont.) __ _ ,

f 5.2 High Oxygen in the System

5.2.1 Symptoms

1. Increasing reading or high oxygen alarm on the Gas Analyzer.

5.2.2 Immediate Operator Action

1. With the concentration of oxygen in the on-service Gas Decay Tank >4% by volume and the hydrogen concentration

>2% by volume, immediately suspend all additions of waste gases to the system and immediately commence reduction of the concentration of oxygen to 12% by volume.

5.2.3 Subsequent Actions:

1. Check the Gas Analyzer for proper operation. Refer to OP 2-1720020, " Gas Analyzer Operation".

2. Purge the affected tank with nitrogen by readjusting the -

nitrogen supply regulator to a higher pressure and -

venting the tank to the vent gas collection header.

3. Determine the cause of oxygen in-leakage. -

NOTE: If all Gas Analyzer sample points indicate high oxygen, it is probable that the analyzer is malfunctioning and the Chemistry Department should --

be notified to conduct local sampling.

. 4. With the concentration of oxygen in the on-service Gas Decay Tank >2% by volume but 142 by voltane, reduce the . :.-

o-ygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

5.3 Loss of Both Waste Gas Compressors -

5.3.1 Symptoms

1. High pressure in Gas Surge Tank (15 psig).

2. Increased pressure in the Flash Tank. -

5.3.2 Immediate Operator Actions - None

Paga 5 of 7 ST. LUCIE UNIT 2 i

OFF-NORMAL OPERATING PROCEDURE No. 2-0530030, REVISION 1 l

, WASTE GAS SYSTEM - 0FF NORMAL OPERATION _, ,_

5.0 INSTRUCTIONS

(Cont.) , , , _ _

5.3 (Cont.)

5.3.3 , Subsequent Actions:

1. If Flash Tank pressure exceeds 10 psig, place the control switch for A0V-6307 (Flash Tank divert) in the HOLDUP -

TANK position and bypass letdown directly to the Holdup Tank.

2. Determine the cause and correct problem. Refer to OP 2-0530020, "Wasta Gas System Operation".

3. If the Boric Acid Concentrators are in service and the Wasta Gas Compressors cannot be restarted immediately, proceed to shut down the concentrators as per -

OP 2-0540021, " Boric Mid concentrator Operation". .-

5.4 High Gas Surge Tank Pressure -

5.4.1 Symptoms

1. High Gas Surge Tank Pressure alarm (15 psig). -

5.4.2 Immediate Operator Actions - None 5.4.3 Subsequent Actions:

1. Check Weste Gas Compressors for proper operation. The - -

backup compressor should be running. Refer to .. .

OP 2-0530020, " Waste Gas System Operation". -

2. Check Gas Surge Tank nitrogen supply pressure regulator. . _ .

for proper operation and setpoint (approximately -

1 psig). Readjust if necessary. ~

5.5 Waste Gas Compressor Diaphragm Leak .

5.5.1 Symptoms

1. Waste Gas Compressor Diaphragm Leak Detector High Pressure alarm. -

5.5.2 Immediate Operator Actions - None .

l Pcg2 6 cf 7

)

ST. LUCIE UNIT 2 l

', OFF-NORMAL OPERATING PROCEDURE NO. 2-0530030, REVISION 1 I

, WASTE CAS SYSTEM - 0FF NORMAL OPERATION _,,,

5.0 INSTRUCTIONS

(Cont.) ,_ ,,

5.3 (Cont.)

5.5.3 Subsequent Actions:

1. If leak is on running compressor, place backup compressor in netvice per OP 2-0530020 and shutdown and remove the leaking compressor from service for repair.

2. If leak is on idle compressor, remove from service for repair.

5.6 Waste Gas Decay Tank Isolation Valve Leak

5.6.1 Symptoms

1. Unexpected or abnormal drop or rise in pressure in Gas Decay Tank, usually resulting from equaling out effect . ~

between two tanks during a gas release.

5.6.2 Immediate Operator Action:

1. Isolste gas release if in progress. .

5.6.3 Subsequent Actions:

1. Notify Chemistry Department so both tanks can be sampled and released for repair work, with the following special ..

conditions:

A. Approved release permit for both tanks.

I B. Release flow rate based on highest activity tank. .. - .

l C. Total equivalent X -133 Curie content of both tanks lessthanTechnicaISpecificationrequirementsfor one tank.

l l

1 l

- , , , - _- - - - - , - - - - - , . - . - - - - - --- , .-- w- , . , , , ,

Pega 7 of 7 ST. LUCIE UNIT 2 .

, OFF-NORMAL OPERATING PROCEDURE No. 2-0530030, REVISION 1 WASTE GAS SYSTEM - CFF NORMAL OPERATION ,,,, ,, .,

6.0 REFERENCES

6.1 OP 2-0530031, " Uncontrolled Release of Radioactive Gas" 6.2 OP ,2-0530020, "Wasta Gas Systen Operation"

, 6.3 00 2-0540021, " Boric Acid Concentrator Operation" 6.4 OP 2-1720020, " Gas Analy::er Operation" 6.5 OP 2-0230020, " Nitrogen System Operation" 6.6 St. Lucie Unit 2 Technical Specifications 3.11.2.5 /R1 7.0 RECORDS REQUIRE'{: ,, _ __,,,,,,,

7.1 Normal log entries .

~

DOCUMENT REVISION DISTRIBUTION SHEET - UNIT II- ,

OPF NORMAL fr EMERGENCY OPI2. PROCEDURE "D$^;hr a TITLE f e hMAWMt.#$1vssem f6A-%s /d) oPhmting) G

_ -la ,.w DOCbENT FILE NUZGER ~OY7O&YO J DOCUMENT REVISION NUMBER O _

1- - --

DISTRIBUTED ON 3/ /[ .3 *- S

. . ... .- . . t DOCUMENT SENT T6T' ~~ ~

' 6 COFT TRANSMITTAL COPT TRANSMITTAL 1

30. DOCUMENT HOLDER RETURNED NO. noct.NENI Hofm . _ RirL x.ua

.Q,l M5 UNCONTROLLED COPIES 1 D. A. Sager ~ -

2 3 NRC-Region II 4 Actus EPPS Branch ChJef 5 N. G. Roos H. Paduaco - GO 6 TJC A. W. Bailey .

, 7

, 8 o

9 10 Control Room II i 11 G. Regal l 3

12 . --

Ug'elow, A. - Backfit j

s r 13 ECI a* gg 15 Training J.'Spodick '

T. Vogan.- CO G. J. Boissy R. R. Jennings H. M. Mercer R. J. huesca %

AeWT!!nnt NRC NRC - IE: HQ

. .. Attn: Chief, Nuclea r Response

. - .u

[ 3 C. Burns - CE - PSL z -

5.

)b ,

s PROCESSED BY:

/ ,

DATE ~ ' "

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. -. . - - 2 ; L. .. .a.-- a.:a.=.:.:L:~h :. 3 X ..;. ..:..e: a ;..;;;_,.. .s _ ,.. ._ , . _

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 0FF-NORMAL PROCEDORE No. 2-0970030 REVISION O __

1. . TITLE: 1207 INSTRUMENT AC SYSTEM (CLASS 1E) 0FF-NORMAL OPERATION

~ _ - . . . ._2. . PREP. _A. RED BY: M. Alternatt August 3 1983

3. SUBCOMMITTEE REVICW BY: (including content list)

C. Marple. K. Thomas for FP&L PNE August 15 1983 e

.. -..-.4. -.REVI.EWED BY FRG ON: e u. 2d. 19 ]

4--.-

. . . - .5 . . APPROVED BY: MMl//A Plant Manager P- 2 7-' 19 7 3 .. .__. .

[ .

..._...6.. .~ REVI.SION REVIEWED BY FRG ON: .

19 _ j _,

1 Plant Manager

.._.. .. ..7... . APPRO.VED BY: 19 .._ ,

i J

i 1

f.

! I h

ocumen

) **tify infor. men, **nt'o!!ed. cefor, ,,,, ,

controllod g,,,,,n,,

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. .:.w.. .

,. Page 1 of 11 i

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 0FF-NORMAL PROCEDURE NO. 2-0970030 REVISION 0

1.0 TITLE

1207 Instrument AC System (Class 13) Off-Normal Operation .

2.0 REVIEWANDAPPROVAk.:

,, , Reviewed by Facility Review Group u.au s 19M

_ . . , . ._._.... Approved by MM/d Plant Manager b '2 9 - 19 ,5

. _ . _ _ . . . . . . _ . Revi_sion Reviewed by FRG 6 19

. Approved by Plant Manager 19

3.0 PURPOSE AND DISCUSSION: ' _ . . . . _ _ _ _ _ . .

3.1 Purposu

~

+

3.1.1 This procedure provides instructions and guidance for restoration of power to the MA, MA-1, MB, MB-1, MC, MC-1, MD and MD-1 instrument biases on loss of normal inverter power. It also provides instructions for verifying or restoring power to PP-266 and PP-267 on loss of the

, 2A and 2B Inverters to the Oualified Safety Parameter Display System (QSPDS).

3.2 Discussion 3.2.1 Four pairs of redundant 1207 AC single" phase ungrounded

. instrument buses (2MA, 2MA':1', 2MB , 2MB-1,' 2MC, 2MC-1, . -

2MD, 2MD-1) provide uninterruptible power to the Reactor Protective System (RPS) and Engineered Safety Features Actuation System (ESFAS). Each bus is supplied separately.

, from an inverter connected to one of the two safety related 125V DC buses.'

To permit maintenance and backup power without disabling the instrument bus, maintenance transformers are provided for each inverter system. The system is arranged so that any single failure does not prevent the RPS and ESFAS from performing their safety functions.

-33 .n.raaq Y J t!;.--.+G..? :s.... sav.s J nmlc ny y This document is not centrolled. Before use, verify Information with a controlled document.

)

I 1

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, Page 2 of 11

, ST. LUCIE UNIT 2 A,

0FF-NORMAL PROCEDURE NO. 2-0970030 RZYISION O r i 1207 INSTRUMENT AC SYSTEM (CLASS 1E) 0FF-NORMAL OPERATION

, , 3.0 PURPOSE AND DISCUSSION: (continued) ,

3.2 (continued) i 3.2.2 In addition, two redundant 1207 AC single phase ungrounded buses (PP-266 and PP-267) provide uninterruptible power to

, the QSPDS and ESFAS instrumentation. Each Los is supplied

! separately from an invertar connected to one of the two

safety related 125V DC buses.

To permit maintenance and backup power without disabling the

, QSPDS, each inverter has its own bypass systen, consisting of

! one power line conditioner (PIE).

i The inverters include an internal static switch which transfers the load to the bypass input line on detection of j ] internal faults. A manual "aske before break" bypass switch I is provided for each inverter to allow transfer from normal l d to bypass power supply during inverter outage without 1

interruption to the AC output.

11

.] ,

4.0 STMPTOMS

I

.5

.j 4.1 Ioss of instrument bus inverter or instrument bus breaker trip.

sf

'l 4.1.1 "120V AC Instr Bus Inverter Trouble" annunciator j (A-43, B-43, A-53, B-53).

.1 i 4.1.2 Loss of power to RPS channel cabinet with automatic trip of

.{ four reactor trip breakers.

\

l 4.1.3 Loss of power to ESFAS channel cabinet.

t s '

4.1.4 1 less of reactor protection safety instrumentation.

4.2 Loss of QSPDS inverter and/or power l$ce conditioner.

.'i -

.J q 4.2.1 "1207 AC Instr Bus Inverter Trouble" annunciator n (A-43, B-43). ' ' ~ ~ - - - -

~~

i

'8 4.2.2 Imss of QSPDS video display.

i

. 4.2.3 Loss of ESFAS instrumentatioc.

e .1 i

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l i

. Page 3 of 11

, ST. LUCIE UNIT 2 OFF-NORMAL PROCEDURE NO. 2-0970030, REVISION O 120V INSTRUMENT AC SYSTEM (CLASS 1E) 0FF-NORMAL OPERATION ._

i, .

5.0 INSTRUCTIONS

l 5.1 Immediate Automatic Action 5.1.1 Four TCB's open on loss of power to one instrument bus.

5.1.2 Automatic transfer of PP-266, PF-267 power on loss of 3

inverter to power line conditioner (PLC).

5.2 Immediate Operator Action 5.2.1 If a reactor trip occurs, carry out Off-Normal OP 2-0030130,

" Reactor Trip / Turbine Trip."

5.3 Subsequent Operator Action 5.3.1 Instrument Bus Inverters j 5.3.1.1 Refer to Table 1 for listing of instrumentation lost. Use redundant in,truments or monitor parameters indirectly using available non-affected instrumentation.

, 5.3.1.2 Restore pcwer to affected instrument bus by placing bypass switch to the ALTERNATE SOURCE TO LOAD

. position.

I 5.3.1.3 Verify with Control Room instrument power is restored.

5.3.1.4 If power is not restored, verify " Alternate Source AC Input" breaker on static inverter cabinet is closed and the alternate source breaker from the 480V vital MCC associated with the affected inverter is closed.

Refer to Technical Specification 3.8.3.1.

Static Inverter 2A: MCC 2AS, Breaker 2-41207 Static Inverter 25: MCC 235, Breaker 2-42050 Static Inverter 2C: MCC 2AS, Breaker 2-41212 Static Inverter 2D: MCC 2BS, Bresker 2-42016 5.3.1.5 Notify Electrical Department to investigate cause for loss of inverter.

i 5.3.1.6 Restore inverter m service per OP 2-0970020,

" Operation of the 120V Instrument AC System (Class 1E)" when inverter is operational.

p i , -. .y-%.m. g ,. - - - - . . , , - , - , - , . - , - - , , - , , , - . , - , . . - - - ,

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, Page 4 of 11

. ST. LUCIE UNIT 2 0FP-NORMAL PROCEDURE NO. 2-C970030, REVISION 0 1207 INSTRUMENT AC SYSTEM (CLf.SS 1E) OFP-NORMAL OPERATION ,, p

5.0 INSTRUCTIONS

(continued) 5.3 (continued) 5.3.2 QSPDS Inverters

5.3.2.1 Refer to Table 2 for listing of instrumentation los t. Use redundant instruments or monitor parsmaters indirectly using available non-affected instruientation.

5.3.2.2 Verify power line conditioner (PLC) supplying power by illumination of " reverse transfer" LED (red light) located on control panel of affected in rter.

5.3.2.3 If PLC has a fault, ensure QSPDS is being supplied by inverter by illumination of " forward transfer" LED (green light) located on control panel of affected inverter.

5.3.2.4 Verify QSPDS display and ECCS instrumentation energized with Control Room.

i 5.3.2.5 If power is not restored, verify PLC input breaker located on PLC is closed and the PLC 480V vital MCC breaker is closed.

Power Line Conditioner 2A: MCC 2A6, Breaker 2-41355 Power Li t Conditioner 2B: MCC 2B6, Breaker 2-42112 5.3.2.6 Restore power by placing Manual Bypass Switch located on inverter to the ITPASS position.

5.3.2.7 Notify Electrical Department to investigate cause of inverter or PI4 failure.

5.3.2.8 Restore inverter to service per OP 2-0970022,

" Operation of the QSPDS' inverter," when inverter is operational.

6.0 REFERENCES

6.1 St. Lucie Unit 2 PSAR, Section 8.3, "Onsite Power System,"

Subsection 8.3.1.1.le, Instrument Power Supply System" 6.2 Off-Normal OP 2-0030131, " Plant Anrunciator Summary" 6.3 Instruction Manual, " Single Phase, Class IE Static Inverter,"

Elgar Corporation, Ebasco ID, 2998-15906 6.4 Instruction Manual, " Power Line Conditioner," Elgar Corporation, Ebasco ID, 2998-15907 I

I

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Page 5 of 11

, ST. LUCIE UNIT 2 0FP-NORMAL PROCEDURE NO. 2-0970030, REVISION 0 ',.

1207 INSTRUMENT AC SYSTEM (CLASS 1E) 0FF-NORMAL OPERATION _

s

6.0 RDERENCES

(continued) 6.5 St. Lucie Plant Unit 2 Power Distribution and Motor Data, Ebasco ID, 2998-B-335 i

6.6 St. Lucie Plant Unit 2 Control Wiring Diagram, Ebasco ID, 2998-B-327 6.7 St. Lucie Plant Unit 2 Technical Specifications, Electrical Power Systems, 3/4.8.3 Onsite Power Distribution, Operating,

Section 3.8.3.1 s 6.8 OP 2-0960020, "125V DC Class IE Power Systen Normal Operation" 6.0 OP 2-0970020 " Operation of the 1207 Instrument AC System -

(Class IE)"

7.0 RECORDS REQUIRED: ,,__

1 7.1 Entry of reactor trip to the Reactor Trip Leg, if a trip occurs.

,j 7.2 Normal'1og entries 1

9 6

t b

9

g..

E

.....-.....q...,-.- < -

a~ n .

+w..y ge- e _- , -_-,,% . , _ . - , , . . , , , , , . , , . , . . , , , _ = , , _ . , , , ,y-.,_.,,,. , . , ,,y_w,, mm,,,,.y ,,__,.,._,,.,,._,.,_--,.yp, ,y,,a. , , , , , , , - . _ -

--_._..._.._ . . _ . . _ . _ . , _ . _ , _ _ _ _ , , , , , .m _ , , _ _

Prge 6 cf 11 ST. LUCIE UNIT 2 OFF-NORMAL PROCEDURE No. 2-0970030, REVISION 0

, 1207 INSTRUMENT AC SYS N (CLASS 1E) 0FF-NORMAL OPERATION TABLE 1

.; Instrument Bua 2MA

1. RIM-26-3, Containment Radiation Monitor

2. RC-26-3, Containment Radiatio'n Monitor

3. 1R-26-3, Containment Radiation Recorder

4. JI-001A, Wide Range Power Level

5. JR-001A, Wide Range Power Recorder

6. JKI-001A, SUR Instrument

7. Reactor Protection Cabinet A l 8. PIA-1102ALL, Pressurizer Pressure

9. Engineered Safeguards Cabinet MA, (Primary Power) SA i 10. Auxiliary Feedwater Actuation Cabinet MA

11. LIC-9013A, Steam Generator Level 2A

12. LIC-9023A, Steam Generator Level 2B

13. PI-09-9A, Feedwater Header Pressure 2A

14. PI-09-10A, Feedwater Header Pressure 2B i

15. PIS-07-2A, Containment pressure,

16. LIS-07-2A, RWI Level j 17. PI-8013A, Steam Cenerator Pressure 2A

18. PI-8023A, Steam Generator Pressure 2B

19. FIS-14-15A, CCW froe RCP's

20. RIS-26-3-2, Containment Radiation

21. PI-1102A, Pressurizar Pressure

22. TI-1102A, Icop Temperature

23. PDI-1101A, RCS Flow

24. JI-001A-1, Wide Range Power (HSCB)

25. TE-1122HA, Loop 2B Hot Leg Temp (SAS, QSPDS Inpat)

26. TE-1122CA, Ioop 2B1 Cold Leg Temp (SAS, QSPDS Input)

!! 27. TE-1112HA, Loop 2A Hot Leg Temp (SAS, QSPDS Input)

28. TE-1112CA, Imop 2A2 Cold Leg Temp (SAS, QSPDS Input)

29. HS-1102A, Loop Temp Pushbutton Selector

30. HS-1101A, Core Flow Pushbutton Selector

- - - - - - - ,w---m,,----...,y----.s. -

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b .... . . . . _:. _ . . .- _ . .: . _ .. ..e _ _ :;_c a. w ._ u . . . . . .. ..- ..

i l

Pzg3 7 cf 11

ST. LUCIR UNIT 2 0FF-NORMAL PROCEDURE NO. 2-0970030, REVISION O

.- 1207 InstRUMElfr AC SYSTEM (CLASS 1E) CFF-NORMAL OPERATION -

a .

TABLE 1 q

i , (continued) g s l Instrument Bus 2MB _,_ . _

g 1. RIM-26-4, containment Radiation Monitor

.] 2. RC-26-4, Containment Radiation honitor

-} 3. 1R-26-4, Containment Radiation Recorder

4. JI-001B, Wide Range Power Level -

5. JR-001B, Wide Range Potver Recorder

] 6. JKI-001B, SUR Instrument

.g

7. Reactor Protection Cabinet B j ! 8. PIA-1102BLL p Pressuriser Pressure d 9. Engineered Safeguards Cabinet MB, (Primary Power) SB

10. Auxiliary Feedveter Actuation Cabinet MB

.]

.] 11. LIC-9013B, Steam Generator Level 2A ~-

] 12. LIC-9023B, Steam Generator Level 2B l 13. PI-09-95, Feedwater Header Pressure 2A - -

1 Jj .

14. PI-09-105, Feedwater Bender Pressure 2B

15. PIS-07-2B, Containment pressure

.}

. 16. LIS-07-2B, RWT Level - -

.~. 17. PI-8013B, Steam Generator Pressure 2A -

i i

18. FI-80238, Steam Generator Pressure 2B

19. FIS-14-155, CCW from RCP's

! - 20. 215-26-4-2, Containment Radiation - - -

21. PI-1102B, Pressuriser Pressure ---

}

i 22. TI-1102B, Imop Temperature -~-

s

. .i 23. PDI-1101B, RCS Flow -

24. JI-0013-1, Vide Range Power (HSCB)

25. TE-1122HB, Loop 2A Hot log Temp (SAS, QSPDS Input)

26. TE-1122CE, Imop 2A1 Cold Leg Temp (SAS, QSPDS Input) -

27. TE-1112HB, Loop 2B Hot Leg Temp (SAS, QSPDS Input) ~

j 28. TE-1112CB, Imop 232 Cold Leg Temp (SAS, QSPDS Input) - -

29. HS-1102B, Loop Temp Pushbutton Selector -

l,

30. ES-1101B, Core Flow Pushbutton Selector -

t i

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., . _ . , . . . . . . . . . , . . . . . . . . _ m .

. <. s

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t P;g) 8 cf 11 ST. LUCIE UNIT 2 i 0FF-NORMAL PROCEDURE NO. 2-0970030, REVISION O

,_, ,, _ , 1207 INSTEDMENT AC SYSTEM (CLASS 1E) 0FF-NORMAL OPERATION -

... y,

\m TABLE 1

{ (continued)

J

,' Instrument Bus 2MC

1. RIM-26-5, Containment Radiation Monitor

2. RC-26-5, Containment Radiation Monitor

-j

, 3. RR-26-5, Containment Radiation Recorder

! 4. JI-001C, Wide Range Power Level

5. JR-001C, Wide Range Power Recorder a

'; 6. JKI-001C, SUR Instrument

, 7. Reactor Protection Cabinet C

,j , 8. PIA-1102CLL, Pressuriser Pressure

. , 9. Engineered Safeguards Cabinet MC, (Backup Power) SA q 10. Auxiliary Feedwater Actuation Cabinet MC

}o 11. LIC-9013C, Stema Generator Level 2A

12. LIC-9023C, Steam Generator Level 2B I 13. PI-09-9C, Feedwater Header Pressure 2A J

14. PI-09-10C, Feedwater Header Pressure 2B j 15. PIS-07-2C, Contait: ment Pressure jj 16. LIS-07-2C, F.WT Level

% 17. PI-8013C, Steam Generator Pressure 2A i 18. PI-8023C, Steam Generator Pressure 25

{ 19. FIS-14-15C, CCW from RCP's

20. RIS-26-5-2, Containment Radiation

], 21. PI-1102C, Precsurizer Pressure

22. TI-1102C, Imop Temperature -

23. PDI-1101C, RCS Flow l

24. HS-1102C, Imop Temp Pushbutton Selector

25. HS-1101C, Core Flow Pushbutton Selector I 1

.i i

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' \ 31

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.h

.1 mer 3

6

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Pcg:2 9 cf 11

~

ST. LUCIE UNIT 2 OFF-NORMAL PROCEDURE NO. 2-0970030, REVISION O 120F INSTRUMENT AC SYSTEM (CLASS 1E) 0FF-NORMAL OPERATION A '

TABLE 1 1 (continued)

'! ~

'i

--i Instruasnt Bus 2MD ____ . - ..

. 1. RIM-26-6, containment Radiation Monitor

2. RC-26-6, Containment Radiation Monitor

3. 11-26-6, containment Radiation Recorder

4. JI-001D, Wide Range Power Level

5. JR-001D, wide Range Power Recorder

., 6. JKI-001D, SUR Instrument

7. Easctor Protection Cabinet D

-3 8. PIA-11020LL, Pressuriser Pressure

-; 9. Engineered Safeguards Cabinet MD, (Backup Power) SB

10. Aamittary Feedwater Actuation Cabinet MD 3

11. LIC-9013D, Steam Generator I4 vel 2A

-l

- 12. LIC-9023D, Steam Generator Level 2B

13. PI-09-9D, Feedwater Header Pressure 2A

14. PI-09-10D, Feedwater Header Pressure 2B

15. PIS-07-2D, Containment pressure

', 16. LIS-07-2D, RWT Level

17. PI-8013D, Steam Generator Pressure 2A

18. PI-8023D, Steam Generator Pressure 2B

. 19. FIS-14-15D, CCW from RCP's

20. 115-26-6-2, Containment Radiation

! 21. PI-1102D, Pressuriser Pressure

22. TI-1102D, Imop Temperature

23. PDI-1101D, RCS Flow -

24. HS-1102D, Imop Temp Pushbutton Selector ' -

25. HS-1101D, Core Flow Pushbutton Selector l

.i

=1 i

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-1 i

1 I

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

- ; ._ .. a. . . ; _L. J. s. . c L .e. ,. :. .. ~ . . _ .. . . :.c. . . .. ~ .: .. ._ _ - _:2 :.. a .gn.. t a ; ,;. . .

P,:g3 10 cf 11

, ST. LUCIE UNIT 2

, 0FF-NORMAL F10CEDURE NO. 2-0970030, REVISION O 1207 INSTRUMENT AC SYSTEM (CLASS 1E) 0FF-NORMAL OPERATION _ _

TABLE 2 Ji

.i Inverter 2B, Pr-267 (SB)

1. Closure Control of 41607 Swgr. 2B3 (2-20411) Incoming Feeder from 2B2 Swgr.

., 2. PIA-2212, Charging Pressure

3. FI-3325 HPSI to Rot I4g 2B Flow i 4. PI-3309, HPSI 2B Disch Edr Press

,' 5. FI-3342, LPSI Header Flow

6. FI-3341, HPSI Header Flow

i. -

7. FI-3332, LPSI Header Flow

. 8. FI-3331, HPSI Header Flow l 9. TI-3303Y, a

j 10. PI-3304, LPSI Pump 25 Disch Press j 11. PI-1107-1, Pressuriser Pressure (Wide Range)

12. LI-1110Y, Pressuriser Level

13. PI-1105D, Pressurizar Pressure (Digital) i 14 PI-1105/1106, Pressuriser Pressure (0-750 PSIA)

15. TI-1125, 251 Cold Leg Temperature I 16. PIS-21-88, Intake Header B Pressure

,' 17. ICC Control Cabinet (SB), QSPDS Moden and Display Power Supply j 18. FR-3301, Shutdown Cooling Bypass Flow -

,' 19. PR-3301, LPSI Header 2A Press

20. F1-3313/3323, HPSI Loop 2A2/2A1 Flow .

21. TR-3352, 2A SDC Temp from RCS/to RCS

22. PR-3305, HPSI 2A Header Pressure i

23. TR-3303W, SDEI 2A Outlet Temperature Recorder

24. FR-3317 HPSI to Hot Leg 2A Flow

25. TR-1112CB/1112HB, 'fC/TH (Wide Range)

I 9

=

t .

t \

._.y . . . . . _ _ ...

l- , , ,

_ _ _ _ - - - _ - _ _ _ . - _ _ . _ . - - - - - _ _ - - - _ _ _ - . - . - - - . - - - -- - I

.- _' . . .u .....:... :.. : . . - - u . :u . :. a.: .. w .; _ a .. , . : - :. , .

. - - .. _ a :.L 4 4 l

1 l

.i- Pcge 11 cf 11 ST. LUCIE UNIT 2 -

. *

OFF-NORMAL PROCEDURE NO. 2-0970030, REVISION O 1_ 1207 INSTRUMElff AC SYSTEM (CLASS 1E) OPF-NORMAL OPERATION

. ~

TABLE 2 i (continued)

1 1

'l Inverter 2A, PP-266 (SA) i

. 1. Closure Control of 41607 Swgr. 2A3 (2-20209) Incoming Feeder from 2A2 j 41607 Segr. .

o

2. FIA-2212, Charging Flow i

3. Ioss of Auto and Manual Makeup to VCT, cannot start Boric Acid Pumps 2A, 2B

, 4. ' PIA-3308, HPSI 2A Aux Header Discharge Pressure

5. FI-3315, HPSI to Hot Iag 2A Flow

6. FI-3312, LPSI Header Flow l 7. FI-3311 HPSI Header Flow

8. FI-3322, LPSI Header Flow -

f

! 3. FI-3321, HPSI Header Flow

10. TI-3303I, SDHI 2A outlet Temperature -

.I 11. PI-3307, LPSI Pump 2A Discharge Pressure -

~l i 12. PIi1108-1, Pressurizar Pressure (Wide Range) -

13. LI-1110X, Pressurizar I4 vel -

' ~

14. PI-1103D, Pressuriser Pressure (Digital)

15. PI-1103/1104, Pressurizer Pressure (0-750 PSIA) -

j 16. TI-1115, 2A1 Cold Leg Temperature -

'j 17. PIS-21-8A, Intake Header A Pressure -

l 18. ICC Cabinet (SA), QSPDS Modem and Display Power Supply l 19. FR-3333/3343, HPSI I4op 2B1/232 Plow -

j 20. FR-3306, Shutdown Cooling Bypass Flow -

) 21. FR-3327, HPSI to Hot Leg 2B Flow

'} 22. TR-3303Z, 23 SDHI Outlet Temperature .

I g 23. TR-3351, 2B SDC Temperature from RCS/to RCS -

! 24. PT-3302, LPSI Header 2B Pressure -

! 25. TR-k112CA/1112HA, Cold Iag 2A2/ Hot Leg 2A Temperature 1

l 26. Recorder 1110X/1108, Pressurizer Level / Pressure t

-I 1

1 i

I l

I i

t \

}

.i

m. . . - -

UNIT II DOCU1GNT REVISION DISTRIBUTION SHEET

OFF No10fAL & EMERGENCY OPE

R. PROCEDURE

bCCUMENT TITLE DSS Of M48A/88 M/ O 3 C. DOCUMENT FILE NUMBER "" /d[d 3b ,

/ DOCUMENT REVISION NUMBER *

[ ,

jl DOCUMENT DISTRIBUTED ON b/DATE -

DOCUMENT SENT TO:

COPY -m TRANSMITTAL COPY TRAt.'5MITTAL NO. DOCUMENT HOLDER RETURNED NO. DOCUMENT HOLDER RETWNED

(. . MASTER UNCONTROLLED COPIES 1 D. A. Sager 2

,3 NRC - Region II 4

Attn: EPPS Branch (hief 5 N. G. Roos H. Paduano - GO 6 TSC A. W. Bailey I

c.,mp mu - m

YO $

9 NroW T.3.Oeftestry 10 11

<* W/M:II G. Regal

(, 12 -

Uselow, AL -Backfit y 4E0 ' Training 7-

'-t --

M 14 15 Training p(b (

J. Spodick T. Vogan - GO G. J. Boissy R. R. J=nnings H. M. Mercer

. ! sri R. J. Frechette n..W_t NRC

( iC MiiQ C. Burns - CE C -

PROCESSED BY: DATE i si

. i Paga 1 of 4 FLORIDA POWER & LIGHT CCMPANY ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE No. 2-1010030 s REVISION 1 1,o urtz.

FOR INFORMATION ONLY '

LOSS OF INSTRUMENT AIR This document is not controlled. Before use, 2.0 REVIEW AND APPRO M : dmd

__ .....___._... _.. Reviewed by Facility Review Group January 21 1982

._....Approv_ed by C. M. Wethy Plant Manager January 27 1982 Revision 1 Revie d by FRG LM /, d /7 19g d /h 4 W'b t Maneger

__. . . .. . . . ._. . hP.grov,ed by y i 7AIS v

/ 7 1983 3.0 PURPOSE AND DISCUSSION:

3.1 This procedura provides instructions to be followed in the event of loss of Instrument Air.

3.2 If Instrument Air is lost completely, air-operated valves (such as CVCS Letdown Control Valves, etc.) will lose remote operating capability. Also, air-operated instrumentation will be lost. Under

, these conditions air-opere.ted valves must be operated on manual or backup syctems. /R1

4.0 SYMPTOMS

4.1 Any of the fallowing conditions are symptoms of decreased Instrument Air System reserve capacity:

1. Both Instrument Air Compressors running continuously.

2. Reduced Instrument Air pressure.

3. Instrument Air Low Pressure Alarm. '

/R1

4. Failure of normal or str.ndby Instrument Air Compressor to load e - ---

or start on signal.

i

5. Air supply line failure.

, 6. Unit I/II Instrument Air cross ties open.

7. Instrument Air Compressor Auto-Start Alarm.

8. Miscellaneoue air-operated valves failing open or closed.

9. Instrument Air Compressor Hi Temp / Overload Trip Alarm. /R1

Paga 2 cf 4

' ST. LUCIE UNIT 2

', 0FF-NORMAL OPERATING PROCEDURE No. 2-1010030, REVISION 1 LOSS OF INSTRUMENT AIR

5.0 INSTRUCTIONS

5.1 Immediate Automatic Actions:

5.1.1 Backup Instrument Air Compressor starts (85 peig decreasing).

5.1.2 Unit I/II Instrument Air cross ties open at decreasing pressure of 80 psig and close at either increasing pressure of 80 psig or continued pressure decrease to 70 psig. /R1 5.2 Immediate Operator Actions:

5.2.1 When Instrument Air pressere decreased below 85 psig., start the backup Instrument Air Compressor (if not already rimaning).

. 5.2.2 If Instrument Air pressure continues to decrease, line up the Service Air header to supply the Instrument Air supply headsr, and start the Service Air Compressor.

NOTE: Minimize the time that the Instrument and Service Air Systems are cross-connected.

5.3 Subsequent Actions 5.3.1 Check the pressure drop across the Bailey Filter.

5.3.2 If Instrument Air pressure can be stabilized:

1. Investigate the Instrument Air System for leaks, regulator or compressor failures, or malfunctions.

2. Verify that the dryers are properly aligned and the filters are correctly in service.

3. Correct any abnormal conditions.

5.3.3 If the decrease in Instrument Air pressure is caused by a loss of electrical power to an Instrument Air Compressor motor due to overload trip of the 480V MCC breaker 2-41331 or 2-42192: /R1

1. Determine that malfunction of the motor or breaker was not the reason for the trip. /R1

2. Rastore power at the appropriate MCC.

3. Start the Instrument Air Compressor.

s

Paga 3 cf 4 ST. LUCIE UNIT 2 -

, OFF-NORMAL OPERATING PROCEDURE No. 2-1010030, REVISION 1 LOSS OF INSTRUMENT AIR

5.0 INSTRUCTIONS

(cont.)

, 5.3 (cont.)

l 5.3.4 If Instrument Air press'ure decreases to less than 75 peig: ,

1. Prepare to shut down the unit in accordance with GP 2-0030125, " Turbine Shutdown - Full Load to Zero Load," or OF 2-0030130, " Reactor Trip / Turbine Trip." /R1

2. Proceed to Cold Shutdown in accordance with OP 2-0030127, " Reactor Plant Cooldown Hot Standby to Cold Shutdown". /R1 NOTE: Air-operated valves may have to be operated manually.

% a

~

9 i

. *e

)

Pcg3 4 cf 4

' , . ST. LUCIE UNIT 2 .

, 0FF-NORMAL OPERATING PROCEDURE No. 2-1010030, REVISION 1 -

LOSS OF INSTRUMENT AIR

6.0 REFERENCES

6.1 Ebasco P&ID 2998-G-085, Service and Instrument Air 6.2 FP & L Annunciator list 6.3 FSAR, Section 9.3.1 7.0 RECORDS REQUIRED:

7.1 Normal Log Entries 1

3 4

7%,

s 6

\

h s N

UNIT II DOCUMENT REVISION DISTRI4UTIQN SEEET

OFF NORMAL & EMERGENCY OPE

R. PROCEDURE

.- bWdb/4Ay W QQas/7Kdf 4,Wfe Vgf4y)pa

., DOCU1ENT TITLE M/4Abef. d#

C N N RILE NoMsER 2-/9dodSd 1 ~y. _ _ DOCUMENT b ISION NUMBER h

I DOCUMENT DISTRI3UTED OM "/'

.---- DATE .

DOCCMENT SENT E ,.: '

COPY - . . .

TRANSMITTAL COPY NO3- TRANSMITTAL l _.

DOCUMENT. HOLDER RETURNED NO, DOCUMENT HOLDER REPURNED

/.

Q,, . .. MASTER UNCONTROLLED COPIES 1 D. A. Sager 2

-~3 NRC - Region II 4' -

~v' " Atta: EPPS Branch (hief 5 H. Paduano - GO N. G. Roos A. W. Bailey

~6, _ T.SC " ' ;' '-- - ~

T *^

8 g[

_ '9 .

10 Ceeerh/femm II T'..T. C a Af* }

l 11 C. Regal Ugelow, Al' -Backfit it - .

g. ..

Training 7---- "" -IV 14 15 Training J. Spodick T. Vogan - GO G. J. Boissy R. R. Jenings H. M. Mercer

. R. J. Frechette

.. gC-IE:

NR wenn m&

Q, ( Q tn: Chief, Nuclmar Response HQ

' -- h C. Burns - CE PROCESSED BY: / DATE i i

Paga 1 cf 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE No. 2-1900030 REVISION 2

1.0 TITLE

AUXILIARY BUILDING AND CONTROL ROOM VENTILATION OFF-NORMAL OPERATION 2.0 REVIEW AND APPROVAL:

. . . . . . _ . . . ... R.eviewe_d by Facility Review Group November 25 1981 l

_,,,, , , , Approv_ed by J. H. Barrow (for) Plant Manager December 4 1981

, , _ , , , .. Revision 2 ReviewedpFRC 7*4 I, /Im /7 19 B3

! .______ .__..__ Approved by d '

fj e k ant Manager M V/ ~7 19 3 l cf i

3.0 PURPOSE

3.1 This procedure provides instructions to be followed when Auxiliary Building and Control Room Ventilation capacity is lost or restricted or when one of the following off-normal conditions exist:

a) Containment Isolation b) Safety Injection c) Control Room Radiation Monitor high alara 3.2 Discussion The Auxiliary Building and Control Room Ventilation Systems are designed to perform or provide the following:

a) Provide outside filtered air.

I b) Provide cooling air to equipment and personnel in certain areas.

c) To filter exhaust air for certain radioactive nuclides.

d) To provide a self-contained atmosphere in the Control Room when an off-normal condition of Contain;aent Isolation or a Control Room Radiation Monitor high alarm exists.

e) To provide an additional filtered exhaust system from the ECCS and Penetration Rooms when a Safety Injection condition exists.

F0R =lNFORMATION ONLY This document is not controlled. Before use, verify information with a controlled document.

Pega,,2 cf 6 ST. LUCIE UNIT 2 "

'. ,- 0FF-NDEMAL OPERATING PROCEDURE No. 2-1900030, REVISION 2

__ , AUZILIARY BUILDING AND CONTROL ROG( VENTILATION OFP-NORMAL OPERATION ,

4.0 SYMPTOMS

4.1 Safety Injection Actuation Signal alarm (R-6) . i 4.2 Containment Isolation Actuation Signal alarm (P-3) ~

l t

e . . . . .,

j 4.3. Control room air cor.ditioning, 2HVA-3A, 2HVA-3B, or 2HVA-3C fan / compressor SS isolated (V-12, W-7, W-8) g"""'""/1(Z '""

4.4 Reactor Aux Bldg. Emerg. Exhaust 2HVE-9A or 2HVE-95 Low Flow, SIAS override, motor overload (W-10, W-11) 4.5 Esactor Aux Bldg. Supply 2HVS-4A or 2HYS-4B Low Flow, SIAS override, motor overload (W-16, W-17) 4.6 Reactor Aux Bldg. Main Exhaust 2HVE-10A or 2HVE-10B Low Flow, motor overload, alarm trip (W-4, W-5) 4.7 EAR Main Exhaust HEPA Filter Hi D/P (W-23) 4.8 Emergency safeguard pump room 2A/2B Hi Temp (W-21)

. - - 4.9 Electrical equipment room A or B Hi Temperature (I-12, X-24) 4.10 RAB 2HVE-SA and/or B HEPA Filter Hi D/P (W-9) /R2 4.11 Control Room Emergency HEPA Filter Hi D/P (W-2) /R2 4.12 Control Room A/C compressor 3A, 3B, or 3C failure (V-24, W-19, W-20) /R2

P ga 3 cf 6 ST. LUCIE UNIT 2 OYF-NORMAL OPERATING PROCEDURE NO. 2-1900030, REVISION 2 C

. , _ , , , _ , _ , , , AUXILIARY BUILDING AND CONTROL ROOM VENTILATION OFF-NORMAL OPERATION

5.0 INSTRUCTIONS

5.1 Safety Injection Actuation Signal Alarm (R-6) 5.1.1 Immediate Automatic Actions

1. 2HYS-4A and/or 2HYS-4B starts.

2. 2HVE-9A and 2HVE-9B start.

3. Daupers D-1, 2, 3, 4, 13, 14, 15, 16, open.

4. Dampers D-SA and B, 6A and B, 7A and B, 8A and B, -

9A and B. 12A and B close. /R2 5.1.2 Immediate Operatdr Actions

1. Verify immediate automatic actions have occurred.

5.1.3 Subsequent Actions

1. Stop either 2HVE-9A or 2HVE-98.

2. Stop either 2HYS-4A or 2HIS-4B.

5.2 Containment Isolation Actuation Signal Alarm (P-3) 5.2.1 Immediate Automatic Action

1. 2HVE-13A and 2IIVE-13B start.

2. FCV-25-14, 15, 16, 17, 18, 19, 24, and 25 close. ,

3. Dampers D-17A and B, 18 and 19 open. /R2 5.2.2 Immediate Operator Actions

1. Verify immediate automatic actions have occurred.

2. Stop 2HVE-14 and 2HVE-33. /R2 5.2.3 Subsequent Actions

1. Stop either 2HVE-13A or 2HVE-13B.

-' - 2. Slowly open either FCV-25-15 and 17 or FCV-25-14 and 16 to let outside makeup air enter the Control Room.

Pressurize the Control Room to a minimum pressure of

.0.125 inches water but do not exceed a maximum of

' O.140 inches water.

NOTE: Testing has indicated that less than 450 cfm makeup is required to maintain a pressure of 0.140 inches water

Paga 4 cf 6 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-1900030, REVISION 2

. _ . . . . . . ..__ .. AUKILIARY BUILDING AND CONTROL ROOM YENTIIATION OFF-NORMAL OPERATION

5.0 INSTRUCTIONS

(Cont.)

5.3 control Room Air Conditioning Fan / Compressor Motor Overload (V-12~, W-7, W-8) 5.3.1 Immediate Automatic Action None 5.3.2 Immediate Operator Actions

1. Start the idle unit.

5.3.3 Subsequent Actions

1. Notify Electrical Department /R2 5.4 RAB Supply 2HYS-4A and 4B Low Flow, Motor Overload (W-16, W-17) 5.4.1 Immediate Automatic Action None 5.4.2 Immediate Operator Actions

1. Start the idle unit.

2. Stop running unit.

.5.5 RAB Main Exhaust 2HVE-10A and B Low Flow, Motor Overload Alarm Trip (W-4, W-5) 5.5.1 Immediate Automatic Action l None 5.5.2 Immediate Operator Actions i

1. Start the idle unit.

l

2. Stop running unit.

5.6 Engineering Safeguard Pump Room 2A/2B Hi Temperature (W-21) 5.6.1 Immediate Automatic Action None 5.6.2 Immediate Operator Action

1. Check the area to verify conditions.

2. Check Area Radiation Monitoring system for alarms.

3. Check 2HVE-10A or 2HVE-10B running.

d Paga 5 cf 6 ST. LUCIE UNIT 2 0FF-NORMAL OPERATING PROCEDURE NO. 2-1900030, REVISION 2

....... .__. ..... AUXILIARY BUILDING AND CONTROL ROOM VElfrILATION OFF-NORMAL OPERATION 5.0 INSTRUCf!ONS: (Cont.)

5.7 Electrical Equipment Room Hi Temperature (I-12' I-24) ,

5.7. 1 Immediate Automatic Action None 5.7.2 Immediate Operator Action

1. Check the area to verify conditions.

2. Check fire alarm panel.

3. Check exhaust fan running (HVE-11 or 12).

5.8 HEPA Filters Hi D/P (W-2, W-9, W-23) 5.8.1 Immediate Automatic Action None 5.8.2 Immediate Operator Action

1. Verify alarm by local D/P gages.

5.8.3 Subsequent Actions

1. Notify Health Physics and Maintenance Department.

2. Reduce flow while changing filters.

5.9 Control Room A/C Compressor 3A, 3B or 3C Failure (V-24, W-19, W-20) 5.9.1 Immediate Automatic Actions l

! None 5.9.2 Immediate Operator Actions

1. Start the idle unit. /R2

. , .__..____ ....,_.,......_.. ._.,_ ,_ .... _____ ____, ,_____ _...._ -..,._-. , r, - , -. _ , , . . , . - - _ , , . - - -

Pcg3 6 cf 6 ST. LUCIE UNIT 2

, . , , , . OFF-N0ltMAL OPERATING 1ROCEDURE NO. 2-1900330, REVISION 2

',_,,,, AUXILIARY BUILDING AND CONTROL ROOM VElfrILATION OFF-NORMAL OPERATION

6.0 REFERENCES

6.1 FSAR Chapter 9.4 6.2 Ebasco P&ID 2998-C-879, HVAC Control Diagram 6.3 Ebasco P&ID 2998-G-873, General Arrangment 6.4 'Ebasco P&ID 2998-G-868, Reactor Building

) 6.5 Ebasco P&ID 2998-C-869 6.6 Ebasco P&ID 2998-G-870, General Arrangement 7.0 RECORDS REQUIRED:

7.1 Normal log entries 7.2 The Nuclear Plant Supervisor should ensure that necessary data is collected to submit a Licensee Event Report, if required.

.- _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ .

ML20080P384

Text

1.0 TITLE

4.0 SYMPTOMS

4.0 STMPTOMS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

1.0 TITLE

3.1 Purpose

3.2 Discussion

4.0 3YMProMS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

6.0 REFERENCES

2.0 Instructions

R. PROCEDURE

3.1 Purpose

6.0 REFERENCES

1.0 TITLE

4.0 SYMPTOMS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

5.2.1 Symptoms

5.3.1 Symptoms

5.0 INSTRUCTIONS

5.4.1 Symptoms

5.5.1 Symptoms

5.0 INSTRUCTIONS

5.6.1 Symptoms

6.0 REFERENCES

1.0 TITLE

4.0 STMPTOMS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

6.0 REFERENCES

6.0 RDERENCES

R. PROCEDURE

4.0 SYMPTOMS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

6.0 REFERENCES

R. PROCEDURE

1.0 TITLE

3.0 PURPOSE

4.0 SYMPTOMS

5.0 INSTRUCTIONS

5.0 INSTRUCTIONS

6.0 REFERENCES

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