Text

Response to Request for Additional Information Related to Request to Extend the Third 10-Year ISI Interval for Reactor Vessel Weld Examination
	ML052870473
Person / Time
Site:	Palisades
Issue date:	10/11/2005
From:	Harden P; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML052870473 (219)
	v • d • e

NMC Committed to Nuclear Excellec Palisades Nuclear Plant Operated by Nuclear Management Company, LLC October 11, 2005 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Response to Request for Additional Information Related to Request to Extend the Third 10-Year ISI Interval for Reactor Vessel Weld Examination By letter dated March 31, 2005, Nuclear Management Company, LLC (NMC) requested Nuclear Regulatory Commission (NRC) approval, pursuant to 10 CFR 50.55a(a)(3)(i),

for the use of an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, paragraph IWB-2412, Inspection Program B, at the Palisades Nuclear Plant (PNP).

By letter dated August 23, 2005, the NRC issued a request for additional information (RAI) on the subject relief request. Enclosure 1 provides the NMC response for PNP.

Summary of Commitments contains no new commitments and no revisions to existing commitments.

Paul A. Harden Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure (1)

Attachments (4)

CC Administrator, Region ll, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC 0417 27780 Blue Star Memorial Highway . Covert, Michigan 49043-9530 Telephone: 269.764.2000

ENCLOSURE I RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PALISADES NUCLEAR PLANT NRC Request In its March 31, 2005, request for authorization to extend the third 10-year ISI interval for reactor vessel examinations, Nuclear Management Company (NMC) stated that the technical justification for its request is consistent with the guidance provided in a January 27, 2005, letter from the NRC to Westinghouse Electric Company (Summary of Teleconference with the Westinghouse Owners Group Regarding Potential One Cycle Relief of Reactor Pressure Vessel Shell Weld Inspections at Pressurized Water Reactors Related to WCAP-16168-NP, "Risk Informed Extension of Reactor Vessel In-Service Inspection Intervals'"). Item number six of this guidance says the following:

The licensee could then provide a discussion of how, based on its plant operational experience, fleet-wide operational experience and plant characteristics, the likelihood of an event (in particular, a significant pressurized thermal shock event) over the next operating cycle which could challenge the integrity of the reactorpressure vessel (RPV), if a flaw was present, is very low.

NMC's submittal includes general statements indicating that the likelihood of pressurized thermal shock (PTS) events is small, and briefly describes a Palisades operating procedure that provides guidance on the preferred water temperature in the safety injection refueling water tank (SIRWT). The guidance recommends that the water in the SIRWT be maintained above 80 degrees to reduce the likelihood of a severe PTS event.

The NRC staff is re-evaluating the risk from PTS events in a study done to develop a technical basis for revising Title 10 of the Code of Federal Regulations, (10 CFR) Part 50, Section 61. Although the NRC staff has not yet completed its evaluation, the current results indicate that the three types of accident sequences shown below cause the more severe PTS events and thereby dominate the risk. Please describe the characteristics of your plant (design and operating procedures) that assure that the likelihood of a severe PTS event over the next operating cycle, which could challenge the integrity of the RPV if a flaw was present, is very low for the following accident sequences:

Sequence 1 Any transient with reactor trip followed by one stuck-open pressurizer safety relief valve that re-closes after about 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Severe PTS events also require the failure to properly control high-head injection.

Sequence 2 Large loss of secondary steam from steam line break or stuck-open atmospheric dump valves. Severe PTS events also require the failure to properly control auxiliary feedwater flow rate and destination (e.g., away from affected steam generators), and failure to properly control high-pressure injection.

Page 1 of 4

Sequence 3 Four-to-nine-inch loss-of-coolant accidents. Severity of PTS event depends on break location (worst location appears to be in the pressurizer line) and primary injection systems flowrate and water temperature.

NMC Response The Palisades Nuclear Plant (PNP) has design characteristics that assure the likelihood of a severe PTS event over the next operating cycle, which would challenge the integrity of the RPV if a flaw is present, is very low for the following accident sequences. The PNP high pressure safety injection (HPSI) pump's design shutoff head is low, which limits the pressure challenge in the described sequences below. In addition, the PNP nominal pressurizer operating design value of 2060 psia is about 150 psi less than other operating pressurized water reactors (PWRs). Therefore, the likelihood of challenging a pressurizer safety relief valve (SRV) is less than that for other PWRs. Furthermore, the PNP pressure and temperature curves are based on Appendix G pressure and temperature limits and utilize a 200 degree subcooling limit. The 200 degree subcooling curve provides extra margin in regard to PTS.

The PNP has operating procedures that assure the likelihood of a severe PTS event over the next operating cycle, which would challenge the integrity of the RPV if a flaw is present, is very low for the following accident sequences. The PNP operator response to each of the listed sequences would be in accordance with the PNP Emergency Operating Procedures (EOPs). The EOPs are based on the Westinghouse Owners Group (WOG) CEN-1 52, "Emergency Procedure Guidelines," for Combustion Engineering (CE) nuclear steam supply system (NSSS) plants.

Sequence 1 This event is characterized as a vapor space loss-of-coolant accident (LOCA). Upon receipt of a reactor trip, the operators would implement EOP-1.0, "Standard Post Trip Actions," provided as Attachment 1, followed by entry into EOP-4.0, "Loss of Coolant Accident Recovery," provided as Attachment 2.

In order to minimize the risk for a PTS event, the operators control PCS temperature, and PCS pressure within the limits of EOP Supplement 1, "Pressure Temperature Limit Curves," provided as Attachment 4.

PCS temperature is controlled by steaming the steam generators in accordance with EOP-4.0, Step 22. This removes energy from the PCS that could potentially cause PCS pressure to raise leading to a PTS event.

Parameters are continuously monitored to determine if safety injection (SI) and charging pump flow can be throttled or stopped. EOP-4.0, Step 4.25 (a continuously applicable step) provides Si throttle criteria. Step 4.33 provides the instructions for throttling Si and controlling charging and letdown. If HPSI pumps and charging pumps were started by an SI actuation signal, then this step is used to reduce or stop HPSI or charging flow Page 2 of 4

to reduce the chances of over pressurizing the PCS and low temperature stressing of the reactor vessel.

Once the pressurizer SRV closes, and the SI throttle criteria is verified, EOP-4.0 provides several steps to control primary coolant system (PCS) inventory in order to prevent a PTS event.

Step 4.32 re-establishes letdown if it was isolated in order to control PCS inventory.

The control of letdown in a solid condition provides the operator a method to control PCS pressure within EOP Supplement 1 limits.

Step 4.34 (a continuously applicable step) provides contingency actions to address over-subcooling or pressurizer pressure greater than the limits of EOP Supplement 1 The concern for PTS is minimized by staying below the upper subcooled limits shown in EOP Supplement 1.

Step 4.70 provides contingency actions should the subsequent closing of the SRV result in water solid conditions in the PCS. The goal of this step is to maintain the PCS within the limits of EOP Supplement 1, by controlling PCS temperature and pressure with the steam generators, and by controlling HPSI, charging, and letdown flow.

Sequence 2 This event is characterized as an excess steam demand event (ESDE.) Upon receipt of a reactor trip, the operators would implement EOP-1.0, "Standard Post Trip Actions,"

followed by entry into EOP-6.0, "Excess Steam Demand Event," provided as .

During performance of the standard post trip actions (SPTA), PCS heat removal safety function acceptance criteria are evaluated in Step 4.8. Contingency action, Step 4.8.a.3, requires that, if a steam generator (SG) has an indication of an ESDE, feedwater flow to the affected SG be secured. This supports the strategy outlined in CEN-1 52, that the operator should not feed a suspected faulted steam generator. Upon entering EOP-6.0, identification and isolation of the affected SG is again addressed in steps 13, 14, and 15. Feedwater is isolated to the affected SG to limit the inventory available to boil off, thus limiting or stopping uncontrolled plant cooldown and stabilizing the plant.

The SI throttle criteria are verified in EOP-6.0, Step 4.17 (a continuously applicable step) and throttling is addressed in Step 4.18. If HPSI pumps and charging pumps were started by an SI actuation signal, then this step is used to limit or stop HPSI or charging flow to reduce the chances of over pressurizing the PCS and low temperature stressing the reactor vessel.

As outlined in Step 4.23 (a continuously applicable step) PCS pressure is maintained within the limits of EOP Supplement 1. The concern for PTS is minimized by staying below the upper subcooled limits shown in EOP Supplement 1. Contingency actions listed in Step 4.23.1, address over-subcooled conditions in the PCS. These include controlling HPSI, charging, and letdown flows, reducing PCS pressure, and controlling Page 3 of 4

PCS cooldown rate in order to restore PCS temperature and pressure within the limits of EOP Supplement 1, thereby minimizing PTS concerns.

Sequence 3 A LOCA is an accident which is caused by a break in the PCS pressure boundary. The break can be as large as a double ended guillotine break in the hot leg, or as small as a break which results in a loss of PCS fluid at a rate that is just in excess of the available charging capacity of the plant.

Small and large break LOCAs differ in their effect on the post-LOCA PCS heat removal process. For a large break LOCA, the only path necessary for PCS heat removal, in both the short and long term, is the break flow with core boil off. For small breaks, heat removal via the flow out the break is not sufficient to provide cooling and, therefore, SG heat removal is required. The emergency procedure guidelines take this into account with the decisions that must be made. Although distinct small and large break LOCA information is contained in the bases section of EOP-4.0, the action steps to be used during the actual emergency do not require the operator to distinguish between break sizes.

There are two paths initially available for PCS heat removal: heat transfer to the secondary side via the SGs, and heat transfer via the fluid flowing out the break. Large break LOCAs have sufficient fluid flowing out the break to provide adequate heat removal without relying on the SGs. Small break LOCAs do not have sufficient fluid flowing out of the break to provide adequate heat removal. Therefore, SG heat removal is required in addition to break flow for adequate heat removal. Because the LOCA EOP does not distinguish between large and small break LOCAs, SG heat removal capability is required at all times during a LOCA (EOP-4.0, Step 22.) Steaming the SGs removes energy from the PCS that could potentially cause PCS pressure to raise leading to a PTS event.

Parameters are continuously monitored to determine if SI and charging pump flow can be throttled or stopped. EOP-4.0, Step 4.25 (a continuously applicable step) provides SI throttle criteria. Step 4.33 provides the instructions for throttling SI and controlling charging and letdown. If HPSI pumps and charging pumps were started by an SI actuation signal, then this step is used to reduce or stop HPSI or charging flow to reduce the chances of over pressurizing the PCS and low temperature stressing of the reactor vessel.

Step 4.34 (a continuously applicable step) provides contingency actions to address over-subcooling or pressurizer pressure greater than the limits of EOP Supplement 1.

The concern for PTS is minimized by staying below the upper subcooled limits shown in EOP Supplement 1. Contingency actions listed in Step 4.34.1 address over-subcooled conditions in the PCS, including throttling SI flows.

A break location in the pressurizer surge line could impact the ability of the operator to determine if SI throttle criteria are met due to either the inability to refill the pressurizer or lack of PCS pressure indication. If SI throttle criteria cannot be verified, then the operator would continue to maintain full SI flow, while aggressively steaming the SGs to remove heat from the PCS (EOP-4.0, Step 22.)

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ATTACHMENT 1 EOP-1, "STANDARD POST TRIP ACTIONS" 25 Pages Follow (Procedure Attachments not included)

IALIBAREs PAL ISADES NUCLEAR PLANT Proc No EOP-1g0 S EMERDENC D OSPERATING Revision 12 uct'ire PROCEDURE Issued Date 2/11/02 STANDARD POST-TRIP ACTIONS 6f~rZ //_7~z q Procedure Sponsor Date GGPalIntsano / 1/2/02 Technical Reviewer Date GWSleerer I 1/1/01 User Reviewer Date

PALISADES ALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 IEOPE K osrs n NUCLEAR PLANT PROCEDU Page 1of 24 TITLE: STANDARD POST-TRIP ACTIONS USER ALERT CONTINUOUS USE PROCEDURE Read each step of the procedure prior to performing that step. When sign-offs are required, sign off each step as complete before proceeding to the next step.

1.0 PURPOSE This procedure provides the immediate actions which must be accomplished after a Reactor trip has occurred or should have occurred. These actions are necessary to ensure that the plant is placed in a stable, safe condition or that the plant is configured to respond to a continuing emergency.

End of Section 1.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 NUCLEAR PLANT PROCEDURE Page 2 of 24 TITLE: STANDARD POST-TRIP ACTIONS 2.0 ENTRY CONDITIONS Standard Post Trip Actions may be entered when ANY of the following symptom(s) of a Reactor Trip exist:

1. Reactor Trip alarm (EK-0972).

2. Control Rod bottom lights on.

3. Rapid reduction of Reactor power.

4. Red trip lights lit on Clutch Power Supplies 1 through 4.

5. RPS trip logic lights on.

6. RPS trip setpoint(s) exceeded.

7. Licensed operator evaluation indicates conditions warrant a Reactor trip.

End of Section 2.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0

@ EMERGENCY OPERATING Revision 12 NUCLEAR PLANT PROCEDURE Page 3 of 24 TITLE: STANDARD POST-TRIP ACTIONS 3.0 EXIT CONDITIONS SPTAs may be exited when ANY of the following conditions exist:

1. IE ALL safety function acceptance criteria are met, AND NO contingency actions were performed, THEN GO TO EOP-2.0 "Reactor Trip Recovery."

2. IF ANY safety function acceptance criteria are NOT met, OR ANY contingency action was taken, THEN GO TO Attachment 1, "Event Diagnostic Flow Chart" to diagnose the event.

End of Section 3.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 NUCLEARPLANT PROCEDURE Page 4 of 24 TITLE: STANDARD POST-TRIP ACTIONS 4.0 IMMEDIATE ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS Record Time of Reactor Trip

1. DETERMINE that Reactivity Control acceptance criteria met:

El a. VERIFY Reactor power U a.1. PERFORM ANY of the following:

lowering.

PUSH BOTH REACTOR TRIP pushbuttons on EC-02 and EC-06.

OPEN CRD Clutch Power Feeder Breakers 42-1 RPS and 42-2RPS.

PLACE ALL CRD clutch power toggle switches to CLUTCH OFF.

El b. VERIFY negative startup rate.

El c. VERIFY a maximum of one full U c.1. COMMENCE emergency boration.

length Control Rod NOT fully inserted.

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 IEOPS~elIn NUCLEARPLANT PROCEDURE rrxat Page 5 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

2. DETERMINE that Main Turbine-Generator acceptance criteria are met:

El a. VERIFY Main Turbine is E a.1. LF plant was operating at power tripped. AND the MSIVs are open, THEN PERFORM ANY of the following:

1) MANUALLY TRIP Main Turbine at Control Panel C-01 (preferred).

2) CLOSE BOTH MSIVs.

CV-051 0 ('A' S/G)

CV-0501 ('B' S/G)

U b. VERIFY that the Main o b.1. PERFORM ANY of the following:

Generator is disconnected from grid by ANY of the 1) OPEN Main Generator Output following: Breakers at Control Panel C-01.

Main Generator Output . 25F7 Breakers open.

25H9 o 25F7 2) CONNECT jumper between o 25H9 terminals 1 and 10 on Relay 487U (Y Phase) inside Panel C-04.

MOD 26H5 open.

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 i EMERGENCY OPERATING Revision 12 r

PLAN PROCEDURE Page 6 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

3. CONTROL the Feedwater System as follows:

U a. PLACE ALL operating Main Feed Pump Individual Speed Controllers to MAN.

S HIC-0526 S HIC-0529 U b. IF BOTH Main Feed Pumps U b.1. IE a Main Feed Pump's speed can are operating, NOT be lowered, THEN RAMP ONE Main Feed THEN TRIP the Main Feed Pump.

El Pump to minimum speed.

c. WHEN TAVE lowers towards U c.1. JE a Main Feed Pump's speed can 525*F (535 0 F preferred), NOT be lowered, THEN RAMP the remaining THEN TRIP the Main Feed Pump.

Main Feed Pump to minimum speed.

Q d. ENSURE CLOSED ALL Main E d.1. IF ALL Main Feed Regulating Valves Feed Regulating Valves and AND ALL Bypass Feed Regulating ALL Bypass Feed Regulating Valves can NOT be closed, Valves for BOTH S/Gs: THEN TRIP the operating Main Feed Pumps.

6 CV-0701 ('A' S/G) a CV-0735 ('A' S/G) a CV-0703 ('B' S/G) 6 CV-0734 ('B' S/G)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 U PLANPROCEDURE Page 7 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

4. DETERMINE that Vital Auxiliaries-Electric acceptance criteria are met:

a. VERIFY that station loads have transferred to offsite electrical power such that ALL of the following conditions exist:

la 1) Buses 1C and 1D energized. E 1.1) ENSURE D/G started for bus NOT energized.

1-1 D/G (Bus 1C)

1-2 D/G (Bus 1D) 0 1.2) ENSURE associated DIG output breaker closed (one attempt only)

Bus 1C (D/G 1-1): 152-107

Bus 1D (D/G 1-2): 152-213 El 2) IFSIAS is NOT actuated, THEN Bus 1E is energized.

El 3) Buses 1A and 1B are energized.

El 4) Y01 is energized.

(continue)

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4. (continued)

NOTE: The following indications can be used for status of DC power:

DC Bus - Indication -. -

D11A P-8A Control Power D11-1 CV-0510 MSIV Dl1-2 K-7A Trip Power D21A P-8C Control Power D21-1 CV-0501 MSIV D21-2 K-7B Trip Power I

5) ALL of the following DC Buses are energized:

0 Left Channel DC Buses 0 D11A 0 D11-1 0 DI1 -2

Right Channel DC Buses 0 D21A 0 D21-1 0 D21 -2 Q 6) At least 3 of 4 Preferred AC Buses are energized.

S Y10 S Y20 aS Y30 Y40

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 NUCLEAR PNT PROCEDURE Page 9 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

5. DETERMINE that PCS Inventory 0 5.1. IF PLCS does NOT respond, Control acceptance criteria are THEN RESTORE AND MAINTAIN met: PZR level between 42% and 57%:

U a. VERIFY BOTH of the following a. OPERATE PZR Level Control conditions exist: System (PLCS).

Pressurizer (PZR) level b. MANUALLY OPERATE Charging between 20% and 85% and Letdown.

PZR level trending to between 42% and 57%

NOTE: Determine PCS subcooling using TH with forced circulation and the Average of Qualified CETs with natural circulation.

0 b. VERIFY PCS at least 25 0 F subcooled.

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 N EMERGENCY OPERATING Revision 12 NUCLEAR PLANT PROCEDURE Page 10 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS Q 6. DETERMINE that PCS Pressure O 6.1. IF PPCS is NOT operating properly, Control acceptance criteria are THEN RESTORE AND MAINTAIN met by verifying that BOTH of the PZR pressure within the limits of following conditions exist: EOP Supplement 1:

PZR pressure between 1650 a. OPERATE PZR Pressure and 2185 psia Control System.

PZR pressure trending toward b. MANUALLY OPERATE PZR 2010 and 2100 psia heaters and PZR spray.

E 6.2. IE PZR pressure is less than 1605 psia, THEN PERFORM the following:

a. VERIFY SIAS initiated ("SAFETY INJ INITIATED" EK-1342 in alarm)

OR PUSH left and right INJECTION INITIATE pushbuttons on EC-13.

PB1-1

PB1-2

b. ENSURE ALL available HPSI and LPSI pumps operating with the associated loop isolation valves open.

0 6.3. IF PZR pressure is less than 1300 psia, THEN STOP PCPs as needed to establish one PCP operating in each loop.

El 6.4. IF PZR pressure is less than minimum PCP operation limits of EOP Supplement 1, THEN STOP ALL PCPs.

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7. DETERMINE that Core Heat Removal acceptance criteria are met:

Ek a. VERIFY at least one PCP is operating.

0k b. VERIFY Loop AT (TH-TC) is less than 100F.

NOTE: Determine PCS subcooling using TH with forced circulation and average of qualified CETs with natural circulation.

El c. VERIFY PCS at least 25 0 F subcooled.

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8. DETERMINE that PCS Heat Removal acceptance criteria are met:

E a. VERIFY at least one S/G has o a.1. For low level, ENSURE at least one BOTH of the following: S/G has feedwater flow of at least 165 gpm.

Level between 5% and 70%

O a.2. For high level, REDUCE feedwater

Feedwater available to flow to the affected S/G.

maintain S/G level E a.3. IF one S/G has indication of an ESDE or SGTR, THEN SECURE feedwater flow to the affected S/G.

E b. VERIFY that TAVE is between o b.1. IF TAVE is greater than 5400F, 5250F and 5400F. THEN RESTORE TAvE to between 5250 F and 5400F using ANY of the following:

Turbine Bypass Valve (preferred)

Atmospheric Steam Dump Valves (continue) (continue)

(continue) (conti flue)

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_NUCLEARPLANT PROCEDURE Page 13 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

8. (continued) (continued)

O b.2. IF TAVE is less than 5250 F, THEN PERFORM BOTH of the following:

1) ENSURE Feedwater flow is NOT excessive.

2) RESTORE TAVE to between 5250F and 5400F using ANY of the following:

Turbine Bypass Valve (preferred)

Atmospheric Steam Dump Valves El c. VERIFY BOTH S/G pressures o c.1. IF either S/G pressure is greater than are between 800 psia and 970 psia, 970 psia. THEN RESTORE S/G pressure to less than 970 psia using ANY of the following:

S Turbine Bypass Valve (preferred)

U Atmospheric Steam Dump Valves (continue) (continue)

(continue) (continue)

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8. (continued) (continued)

E c.2. IF either S/G pressure is less than 800 psia, THEN PERFORM ALL of the following:

1) ENSURE that the Turbine Bypass Valve is closed.

2) ENSURE that the Atmospheric Steam Dump Valves are closed.

3) CLOSE BOTH MSIVs.

CV-0510 ('A' S/G)

CV-0501 ('B' S/G) o c.3. IF either S/G pressure is less than 500 psia, THEN ENSURE CLOSED the following valves:

1) BOTH MSIVs.

CV-051 0 ('A' S/G)

CV-0501 ('B' S/G)

2) Main Feed Regulating Valve and Bypass Feed Regulating Valve on affected S/G only:

a CV-0701 ('A' S/G) e CV-0735 ('A' S/G) e CV-0703 ('B' S/G)

CV-0734 ('B' S/G)

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9. DETERMINE that Containment Isolation acceptance criteria are met:

El a. VERIFY containment pressure O a.1. IE Containment pressure is greater less than 0.85 psig. than or equal to 4.0 psig, THEN PERFORM ALL of the 6 PIA-1814 following:

6 PIA-1815

1) VERIFY Containment Isolation Signal initiated ("CIS INITIATED" EK-1 126 in alarm)

OR PUSH left and right HIGH RADIATION INITIATE pushbuttons on EC-13.

S CHRL-CS S CHRR-CS

2) ENSURE CLOSED the following:

BOTH MSIVs:

0 CV-051 0 ('A' S/G) 0 CV-0501 ('B' S/G)

Main Feed Reg Valves:

o CV-0701 ('A' S/G) o CV-0703 ('B' S/G)

Bypass Feed Reg Valves:

o CV-0735 ('A' S/G) o CV-0734 ('B' S/G)

(continue) (continue)

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9. (continued) (continued)

CCW Isolation Valves:

o CV-0910, (KEY: 337) o CV-091 1, (KEY: 338) o CV-0940, (KEY: 336)

3) ENSURE SIAS initiated by performing the following:

a. VERIFY "SAFETY INJ INITIATED" EK-1 342 alarmed OR PUSH left and right INJECTION INITIATE pushbuttons on EC-13.

S PB1-1 S

PB1-2

b. ENSURE ALL available HPSI and LPSI pumps operating with the associated loop isolation valves open.

(continue)

PALISADES PALISADES NUCLEAR PLANT ProcNo EOP-1.0 E EMERGENCY OPERATING Revision 12 LOPs~lpnes o NUCLEAR PLANT PROCEDURE Page 17 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

9. (continued)

Ek b. VERIFY Containment Area o b.1. IF Containment radiation level is Monitor alarms clear greater than 1 x 10' R/hr on ANY and NO unexplained rise. Containment Area Monitor, THEN PERFORM BOTH of the RIA-1 805 following:

RIA-1 806 0

RIA-1 807 1) VERIFY Containment Isolation RIA-1 808 Signal initiated ('CIS INITIATED EK-1126 in alarm)

OR PUSH left and right HIGH RADIATION INITIATE pushbuttons on EC-13.

CHRL-CS

CHRR-CS

2) CORROBORATE Containment Area Monitor readings by comparing to Containment High Range Monitor readings.

S RIA-2321 S

RIA-2322 0 c. VERIFY Condenser Off Gas Monitor RIA-0631 alarm clear and NO unexplained rise.

EI d. VERIFY Main Steam Line Monitor alarms clear and NO unexplained rise.

RIA-2323

RIA-2324

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10. DETERMINE that Containment O 10.1. ENSURE the Containment Air Atmosphere acceptance criteria Coolers are in operation as follows:

are met:

a. IF SIAS is NOT present, El a. VERIFY Containment THEN ENSURE OPERATING temperature less than 1250 F. ALL available Containment Air Cooler fans.

0 b. VERIFY Containment pressure less than 0.85 psig.

V-lAandV-lB

V-2A and V-2B 6 PIA-1814

V-3A and V-3B 6 PIA-1 815

V-4A and V-4B

b. OPEN Containment Air Cooler high capacity outlet valves as Service Water System capacity permits:

CV-0867

CV-0861

CV-0864

CV-0873 0 10.2. IF Containment pressure is greater than or equal to 4.0 psig, THEN PERFORM ALL of the following:

a. ENSURE OPERATING ALL available Containment Air Cooler 'A' fans.

V-1A

V-2A a V-3A

V-4A (continue) (continue)

CV-0869 VHX-4 Inlet Valve will be closed if a SIAS has occurred

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0

@ EMERGENCY OPERATING Revision 12 NUCLEARPLANT PROCEDURE Page 19 of 24 TITLE: STANDARD POST-TRIP ACTIONS Iia INSTRUCTIONS CONTINGENCY ACTIONS

10. (continued) (continued)

b. ENSURE OPEN ALL available Containment Spray Valves.

c. ENSURE ALL available Containment Spray Pumps are operating.

PPALISADES ALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 NUCLEAR PLANT PROCEDURE Page 20 of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

11. DETERMINE that Vital Auxiliaries-Water acceptance criteria met by performing ALL of the following:

El a. VERIFY at least two Service O a.1. START available Service Water Water Pumps operating. Pumps.

U b. VERIFY BOTH Critical SW U b.1. START available Service Water Headers in operation with Pumps.

pressures greater than 42 psig.

E b.2. IE SW Header pressure is less than 42 psig, AND SIAS is NOT present, THEN PERFORM BOTH of the following:

1) ENSURE CLOSED Containment Air Cooler high capacity valves as necessary to raise SW Header pressure greater than 42 psig.

CV-0867

CV-0861

CV-0864

CV-0873

2) IE SW Header pressure is less than 42 psig following the closing of containment Air Cooler high capacity valves, THEN ENSURE CLOSED Non-critical SW Isolation valve CV-1359.

U c. VERIFY OPERATING at least L c.1. START available CCW Pumps.

one CCW Pump.

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 NUCLEAR PLANT PROCEDURE Page 21of 24 TITLE: STANDARD POST-TRIP ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS o 12. DETERMINE that Vital o 12.1. START available Instrument Air Auxiliaries-Air acceptance criteria Compressors as necessary.

met by verifying Instrument Air pressure greater than 85 psig. o 12.2. IF Feedwater Purity Building Air supply is available, THEN OPEN FWP Air Cross-tie Valve, CV-1221 as necessary.

End of Section 4.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.0 3 EMERGENCY OPERATING Revision 12 PLANT PROCEDURE Page 22 of 24 TITLE: STANDARD POST-TRIP ACTIONS 5.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS WHEN SIRWT level is less than or equal to 25%,

THEN:

El a. Prior to RAS, PERFORM Pre-RAS actions. Refer to EOP Supplement 42.

LI b. IF RAS occurs, THEN PERFORM Post-RAS actions. Refer to EOP Supplement 42.

CAUTION Each D/G is limited to a 2500 KW continuous load rating and a 2750 KW two-hour load rating. Operation of VC-10 (VC-1 1) will draw approximately 44 KW.

O 2. ENSURE CR HVAC is aligned for Emergency Mode Operation within 20 minutes of the time of the Reactor Trip by performing the following:

a. ENSURE at least one Air Filter Unit Fan associated with an operating train is ON:

V-26A

V-26B

b. ENSURE OFF the following fans:

V-94 Purge Fan

V-47 Switchgear Exhaust Fan

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-1.O

@ EMERGENCY OPERATING Revision 12 NUCLEARPLANT PROCEDURE Page 23 of 24 TITLE: STANDARD POST-TRIP ACTIONS 5.0 OPERATOR ACTIONS INSTRUCTIONS i CONTINGENCY ACTIONS

3. VERIFY BOTH of the following:

U a. At least one Condensate Pump U 3.1. CLOSE BOTH MSIVs.

operating.

CV-0510 U b. At least one Cooling Tower

CV-0501 Pump operating.

0 4. IF an SIAS has initiated, THEN PERFORM EOP Supplement 5 "Checklist for Safeguards Equipment Following SIAS."

o 5. IF a CHP or CHR has initiated, THEN PERFORM EOP Supplement 6 "Checklist for Containment Isolation and CCW Restoration to Containment."

o 6. COMMENCE Emergency Shutdown Checklist. Refer to GOP-1 0, "Balance of Plant Actions Following a Reactor Trip."

0 7. IF Reactor trip was due to Equipment Fire, THEN REFER TO ONP-25.1, "Fire Which Threatens Safety Related Equipment."

U 8. IF the MSIV AND MSIV bypass valves are closed, THEN ENSURE TRIPPED BOTH Main Feed Pumps.

PPALISADES ALISADES NUCLEAR PLANT Proc No EOP-1.0 EMERGENCY OPERATING Revision 12 T PROCEDURE Page 24 of 24 TITLE: STANDARD POST-TRIP ACTIONS 5.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS E 9. IF ALL of the following conditions exist:

ALL safety function acceptance criteria met

No contingency action was taken

Control Room is habitable, THEN GO TO EOP-2.0, "Reactor Trip Recovery."

0 10. IE ANY of the following conditions exist:

ANY safety function acceptance criteria NOT met

ANY contingency action was taken

Control Room is NOT habitable, THEN REFER TO Attachment 1, "Event Diagnostic Flow Chart" AND DIAGNOSE the event.

End of Section 5.0

I-ATTACHMENT 2 EOP-4, "LOSS OF COOLANT ACCIDENT RECOVERY" 110 Pages Follow (Procedure Attachments not included)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLPLANT PROCEDURE Issued Date 1/6/05 LOSS OF COOLANT ACCIDENT RECOVERY RLTucker / 1/5/05 Procedure Sponsor Date GGShaffer / 10/22/04 Technical Reviewer Date DCampbell / 10/26/04 User Reviewer Date

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 IPROCEDURE TL Page 1of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY USER ALERT CONTINUOUS USE PROCEDURE Read each step of the procedure prior to performing that step. When sign-offs are required, sign off each step as complete before proceeding to the next step.

1.0 PURPOSE This procedure provides operator actions which must be accomplished in the event of a Loss of Coolant Accident (LOCA) when the Shutdown Cooling System is NOT initially in service. These actions are necessary to ensure that the Plant is placed in a stable condition. The goals of this procedure are to mitigate the effects of a LOCA, isolate the break (if possible), and to establish long term cooling using the Safety Injection System or the Shutdown Cooling System. This procedure achieves these goals while maintaining adequate core cooling and minimizing radiological releases to the environment.

End of Section 1.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 LEAPLN PROCEDURE Page 2 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 2.0 ENTRY CONDITIONS

1. EOP-1.0, "Standard Post Trip Actions," has been performed.

The event initiated from a lower mode when the Shutdown Cooling System is NOT initially in service.

2. Plant conditions indicate that a LOCA has occurred as indicated by ANY of the following:

a. Abnormal Pressurizer level change (low or high)

b. Pressurizer pressure low for existing plant conditions

c. SIAS automatically activated

d. Standby Charging Pumps start

e. CHP or CHR alarms

f. Containment pressure, temperature or humidity high

g. Containment Sump level rising

h. Quench Tank level, temperature, or pressure high I. Volume Control Tank level dropping End of Section 2.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 3of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 3.0 EXIT CONDITIONS

1. The diagnosis of a LOCA is NOT confirmed.

OR

2. ANY of the Safety Function Status Check Sheet acceptance criteria are NOT satisfied AND corrective actions to restore the safety function are NOT effective.

3. The Loss of Coolant Accident Recovery procedure has accomplished its purpose by satisfying ALL of the following:

a. ALL Safety Function Status Check Sheet acceptance criteria are being satisfied

b. Shutdown Cooling entry conditions are satisfied QOB The break has been isolated The PCS is in long term cooling

c. An appropriate approved plant procedure can be implemented End of Section 3.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 X EMERGENCY OPERATING Revision 16 NEAR PROCEDURE Page 4 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 4.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS CAUTION During degraded Containment conditions, the operator should not rely on any single instrument indication due to large instrument errors. Alternate/additional instrumentation should be used to confirm trending of PCS conditions.

by performing ALL of the following:

EOP-1.0, "Standard Post Trip

a. VERIFY Attachment 1, "Safety Actions," Attachment 1, "Event Function Status Check Sheet" Diagnostic Flowchart' AND acceptance criteria: RE-DIAGNOSE the event.

1) Are satisfied at intervals of

For events initiated from a lower approximately fifteen mode, GO TO the EOP minutes. considered appropriate by the Shift Supervisor.

OR

EOP-9.0, "Functional Recovery Procedure."

2) Corrective actions to restore Attachment 1, "Safety Function Status Check Sheet," acceptance criteria are effective.

(continue) 0 =

= Hold Point Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 RPL PROCEDURE Page 5 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

1. (continued)

b. iF ALL of the following conditions exist:

Steam Generator Blowdown Monitor, RIA-0707, has NOT alarmed

SIAS has NOT occurred OB has been reset

CHP and CHR signals are NOT present, THEN SAMPLE S/Gs for activity and Lithium AND VERIFY sample results do NOT indicate a SGTR.

c. Observation of NO abnormal S/G level rise (NOT attributable to feed flow or swell).

3. OPEN the placekeeper AND RECORD the time of EOP entry.

4. IF PZR pressure is less than or 4.1. PUSH BOTH left and right equal to 1605 psia INJECTION INITIATE pushbuttons QB Containment pressure is on EC-13.

greater than or equal to 4.0 psig, THEN VERIFY 'SAFETY INJ

PB1-1 INITIATED" (EK-1342) is alarmed.

PB1-2 0 = Continuously applicable step fA= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 T PROCEDURE ,Page 6 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

5. IF SIAS is present, THEN PERFORM ALL of the following:

a. ENSURE available safeguards equipment operated or operating. Refer to EOP Supplement 5.

b. VERIFY at least minimum Si b.1. IF Si flow is NOT within the limits of flow. Refer to EOP Supplement EOP Supplement 4,

4. THEN PERFORM ANY of the following to restore SI flow:

1) ENSURE electrical power available to Si pumps and valves.

2) ENSURE correct SI valve lineup.

3) ENSURE adequate Si pump seal cooling.

4) START additional Si pumps as needed until SI flow is within the limits of EOP Supplement 4.

c. IF Letdown Orifice Stop Valves are closed, THEN PLACE handswitches in the CLOSE position:

0 HS-2003 0

HS-2004 0

HS-2005 O= Continuously applicable step Hold

= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 T PROCEDURE Page 7 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: P-50A and P-50B shall not be operated simultaneously when Tc is less than 300 0F.

6. IF PZR pressure lowers to less than 1300 psia AND SIAS is initiated, THEN PERFORM BOTH of the following:

a. ENSURE one PCP is stopped in each loop.

b. IF PCS is less than 25 0 F subcooled, THEN ENSURE ALL PCPs stopped.

7. WHEN PCS temperature lowers, THEN ENSURE PCPs configured as follows:

- -7.I-,- 1 IMAXIMUM '

-:-PCS T6: -. -OPERATING PCPs

<450'F 3

. 300'F 2

8. IF PCPs are operating, 8.1. STOP PCPs which do NOT satisfy THEN VERIFY PCP operating PCP operating limits.

limits are satisfied. Refer to EOP Supplement 1.

(D = Continuously applicable step t,= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NE PLANT PROCEDURE Page 8 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

9. IF open, THEN CLOSE CWRTs Vent Valves:

S CV-1 064 0 CV-1 065

10. ISOLATE the LOCA by performing ALL of the following:

a. IF PZR pressure is less than a.1. CLOSE the PORV block valves:

2100 psia, THEN VERIFY BOTH PORVs

MO-1 042A are closed.

MO-1 043A

b. ENSURE CLOSED Letdown Stop Valves:

S CV-2001 0 CV-2009

c. ENSURE CLOSED PCS Sample Isolation Valves:

S CV-1 910 S CV-1911

d. ENSURE CLOSED Reactor Vessel and PZR Vent Valves on C-11A:

PRV-1067

PRV-1068

PRV-1069

PRV-1070 (continue) 0 = Continuously applicable step t,= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 9 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

10. (continued)

e. VERIFY BOTH of the following e.1. IF PCS to CCW leak is evident, conditions exist: THEN PERFORM ALL of the following:

0 CCW Radiation Monitor, RIA-0915, alarm clear 1) LOCATE the leak. Refer to ONP-23.1, "Primary Coolant a "COMPONENT CLG Leak."

SURGE TANK T-3 HI-LO LEVEL" (EK-1 172) is clear 2) ISOLATE the leak. Refer to ONP-23.1, "Primary Coolant Leak.'

3) IF CCW was isolated to any operating PCP, THEN SECURE the affected PCP(s).

f. VERIFY PZR Relief Valve(s) f.1. REDUCE PCS pressure to less NOT lifting by the following: than 1800 psia.

Observation of Acoustic Monitor Panel indications on C-11A

PZR Relief Valve Discharge Temperature indicators on C-12

Observation of Quench Tank temperature, pressure and level D-l i cabl esteD

_- -Cn-ti u_aul- aDplicable C) = Continuouslv s eI.. .fS= Hold o Point Poi nt

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 INUCLEARPLANT PROCEDURE Page 10 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

11. IF LOCA is outside of containment as indicated by ANY of the following:

Abnormal rise in Auxiliary Building Area Monitors.

Abnormal rise in East or West ESS Room Sump levels.

Abnormal rise in Dirty Waste Drain Tanks level THEN PERFORM ALL of the following:

a. LOCATE AND ISOLATE the leak.

b. ENSURE applicable areas of the Auxiliary Building are isolated by performing the following:

1) IF any of the following alarms have annunciated,

EK-1364, Gaseous Waste Monitoring Hi Radiation

EK-1 366, Plant Area Monitoring Hi Radiation (continue)

O= Continuously applicable step fA'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 T PROCEDURE Page 11 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

11. (continued)

THEN REFER TO ARP-8, "Safeguards Safety Injection and Isolation Scheme EK-13 (EC-13)" AND PERFORM Corrective Actions for any alarming monitors listed.

2) NOTIFY plant personnel to stay clear of the affected areas of the Auxiliary Building.

c. INITIATE actions to makeup to the SIRWT. Refer to one of the following:

SOP-2A, "Chemical &

Volume Control System Charging & Letdown"

SOP-1 7A, "Clean Radioactive Waste System"

d. MANUALLY INITIATE CIS by pushing left or right HIGH RADIATION INITIATE pushbuttons on EC-13 AND PERFORM EOP Supplement 6.

CHRL-CS

CHRR-CS

e. NOTIFY the TSC.

0 = Continuously applicable step t,= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEAPLA PROCEDURE 1 Page 12 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

12. PLACE at least one Hydrogen Monitor in operation, ensuring the appropriate Key Switch in the

'ACCI' position. Refer to SOP-38, "Gaseous Process Monitoring System."

13. IE ANY of the following conditions exist:

Containment pressure is greater than or equal to 4.0 psig

Any operable Containment Radiation Monitor rises to 1 x 10' R/hr, THEN PERFORM ALL of the following:

a. VERIFY "CIS INITIATED" a.1. MANUALLY INITIATE CIS by (EK-1 126) is alarmed. pushing left or right HIGH RADIATION INITIATE pushbutton on EC-13.

CHRL-CS

CHRR-CS

b. VERIFY Containment Isolation. b.1. CLOSE valves that failed to Refer to EOP Supplement 6. automatically operate.

C = Continuously applicable step) f5= Hold

(= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT ProcNo EOP-4.0 EMERGENCY OPERATING Revision 16 LSLAUN PROCEDURE IPage 13 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

14. IF Containment pressure is greater than or equal to 4.0 psig, THEN PERFORM ALL of the following:

a. VERIFY Containment Spray a.1. OPEN available Containment Spray alignment valves to obtain required AND at least minimal configuration and at least minimum acceptable spray flow per flow.

following table:

CV-3001 NUMBER :

CV-3002

. OF NUMBER OF CS FLOW.

RUNNING -- OPEN CS. MUST BE AT,` AND CSPUMPS !.VALVES -'LEAST: -.

START available Containment

.RAS NOT Present', .-

Spray pumps 1 at least 1 2185 gpm total 0 P-54A 2 or3 l 2 2939 gpm total 0 P-54B RAS Present 0 P-54C 1 l 1 I 1525 gpm 2 or 3 2 l 3100 gpm total

b. ENSURE at least one Containment Air Cooler Accident Fan operating.

V-1A

V-2A

V-3A

V-4A 0 = Continuouslvyappicable step 15= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 X EMERGENCY OPERATING Revision 16

_; PROCEDURE Page 14 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Operation of PCPs should be minimized when seal cooling is NOT present or controlled bleedoff is isolated.

15. IF PCP seal cooling is unavailable, THEN PERFORM ALL of the following:

a. CLOSE PCP Controlled Bleedoff valves:

0 CV-2083 0 CV-2099

b. CLOSE PCP Controlled Bleedoff Relief Stop, CV-2191.

c. RESTORE PCP seal cooling.

Refer to ONP-6.2, "Loss of Component Cooling."

C) == Continuously applicable

= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 E09PE PROCEDURE Page 15 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Continued operation of the sprays after pressure has been reduced to an acceptable level increases the possibility of wetting electrical connectors (which may result in electrical grounds, shorts and other malfunctions) and containment sump screen clogging.

Parameter- Condition Containment less than 3 psig pressure NOT required for CTMT ambient cooling NOT required for HPSI subcooling NOTE: These conditions must be met prior to securing the last Containment Spray pump.

Containment NOT needed for iodine removal Spray as determined by Chemistry operation OR ALL of the following:

Containment high range Gamma monitors read less than 1800 R/lHr

Containment isolated per EOP Supplement 6

less than one hour has elapsed since reactor trip (Continue)

O=

= Continuously applicable stepstep 0= Hold Point

(=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 l EMERGENCY OPERATING Revision 16 PROCEDURE Page 16 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

16. (Continued)

THEN STOP spray pumps one at a time, waiting to see the effect of reduced spray flow as follows:

a. IF three Containment Spray a.1. IF Containment Pressure rises to Pumps are operating, 3 to 4 psig THEN STOP one Containment AND two Containment Spray Spray Pump as directed by the Pumps operating, CRS. THEN START Containment Spray Pump.

b. IF Containment pressure is less b.1. IF Containment Pressure rises to 3 than 3 psig, to 4 psig AND two Containment Spray AND one Containment Spray Pump Pumps are operating, operating, THEN PERFORM the following THEN as directed by the CRS:

1) START Containment Spray

1) CLOSE one Containment Pump.

Spray Valve as follows:

2) OPEN Containment Spray a) PLACE one CHP Bypass Valve.

Switch to BYPASS:

HS-3001C, CV-3001 (Key: 397)

HS-3002C, CV-3002 (Key: 396) b) ENSURE CLOSED associated Containment Spray Valve:

0 CV-3001 0

CV-3002 (Continue)

C)=

('= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16

-PROCEDURE [ Page 17 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

16. (Continued)

2) STOP one Containment Spray Pump.

c. IF Containment pressure is less c.1. IF Containment Pressure rises to 3 than 3 psig AND one to 4 psig AND no Containment Containment Spray Pump is Spray Pump operating, THEN operating, THEN STOP the Containment 1) Ensure one Containment Spray Pump as directed by the Spray Valve open.

CRS.

2) START Containment Spray Pump.

d. WHEN ALL Containment Spray Pumps have been stopped, THEN ENSURE CLOSED BOTH Containment Spray Valves.

1) ENSURE BOTH CHP Bypass Switches in BYPASS:

HS-3001C, CV-3001 Bypass (Key: 397)

HS-3002C, CV-3002 Bypass (Key: 396)

2) ENSURE CLOSED BOTH Conatinment Spray Valves:

0 CV-3001 CV-3002 0 == Continuously applicable step

= Hold Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 EON PROCEDURE Page 18 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

17. WHEN all Containment Spray Pumps have been stopped, THEN PERFORM ALL of the following:

a. IE MFW or Condensate pumps are operating AND feedwater from these sources is NOT desired, THEN PLACE ALL of the following controllers in MANUAL AND CLOSE:

1) Feedwater Regulating Valves

LIC-0701 ('A' S/G)

LIC-0703 ('B' S/G)

2) Feedwater Regulating Bypass Valves 0 LIC-0735 ('A' S/G) 0 LIC-0734 ('B' S/G)

b. IF CCW to containment has NOT been restored, THEN PLACE the following CCW valve keyswitches to CLOSE:

Valve Keyswitch' Key CV-0910 HS-0910 337 CV-0911 HS-0911 338 iCV-0940 HS-0940 336 (Continue)

C)

©== Continuously applicable step A~= Hold Point

¶= Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 LSLAUN PROCEDURE [Page 19 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

17. (Continued)

NOTE: Automatic reinitiation of spray will not occur until after SIAS has been reset.

c. RESET CHP circuits by pushing left and right HIGH PRESSURE RESET pushbuttons on C-13 0 CHPL - Reset 0

CHPR - Reset

d. WHEN CHP has been reset, THEN ENSURE both Containment Spray Valve CHP Bypass Keyswitches are in NORMAL:

a HS-3001 C 0

HS-3002C C)= Continuously applicable step 'f= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 N PROCEDURE [Page 20 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

18. VERIFY BOTH of the following: 18.1. ENSURE CLOSED BOTH MSIVs:

At least one Cooling Tower

CV-0510 ('A' S/G)

Pump operating

CV-0501 ('B' S/G) 0 P-39A 18.2. ENSURE CLOSED from the Control 0 P-39B Room BOTH MSIV Bypass valves:

At least one Condensate Pump

MO-0510 ('A' S/G) operating

MO-0501 ('B' S/G) 0 P-2A a. IF ANY MSIV Bypass valves 0 P-2B were open when power/position indication was lost, THEN LOCALLY CLOSE ANY open MSIV Bypass valve.

b. ENSURE CLOSED ALL S/G Blowdown Valves:

-'. I

-'A' AS/G,; .- 'B SJ--

CV-0739 CV-0738 CV-0771 CV-0770 CV-0767 CV-0768

19. IF the LOCA is isolated, THEN GO TO Step 64.

©= Continuously applicable step ft= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 PROCEDURE Page 21 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Each D/G is limited to a 2500 KW continuous load rating and a 2750 KW two-hour load rating. Operation of VC-10 (VC-1 1) will draw approximately 44 KW.

20. ENSURE at least one train of CR HVAC in Emergency Mode. Refer to SOP-24, "Ventilation and Air Conditioning System.'

NOTE: IF emergency boration is in progress, THEN cooldown may commence/continue while the required shutdown margin value is calculated.

C 21. VERIFY PCS boron concentration 21.1. IF PCS boron concentration is less greater than or equal to required than required boron concentration, boron concentration as verified by THEN PERFORM BOTH of the sample or hand calculation. Refer following:

to EOP Supplement 35.

a. ENSURE emergency boration is

a. IF Emergency boration is in in progress.

progress AND PCS boron concentration b. WHEN required boron is greater than or equal to concentration is reached, required boron concentration, THEN SECURE emergency THEN SECURE emergency boration. Refer to EOP boration. Refer to EOP Supplement 40.

Supplement 40.

0 =

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEARPLANT PROCEDURE Page 22 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION A maximum PZR cooldown rate of 2000F/Hr and a maximum PZR Spray AT (PZR vapor temp - spray temp) of 3500 F should be observed to prevent damage to the PZR or Spray Nozzle.

NOTE: PZR level indication decalibration will occur during cooldown. Correction curves in EOP Supplement 9, "Pressurizer Level Corrections Hot Calibrated" or EOP Supplement 10, "Pressurizer Level Corrections Cold Calibrated" should be used.

NOTE: S/G level indication decalibration will occur during cooldown. Correction curves in EOP Supplement 11, "S/G Level Correction" should be used.

NOTE: Steam flow through two of the four Atmospheric Steam Dump Valves should be adequate to establish an initial cooldown rate of 75 0F/hr.

NOTE: P-50A and P-50B shall not be operated simultaneously when Tc is less than 3000F.

(continue)

©= Continuously applicable step A~= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 RPLANT PROCEDURE [Page 23 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

22. (continued)

22. COMMENCE steaming S/Gs as follows:

a. REFER TO the following:

EOP Supplement 1, Pressure and Temperature Limit Curves

EOP Supplement 33, PCS Heatup/Cooldown Rate Data

b. IF safety injection flow is b.1. OPERATE Atmospheric Steam causing a cooldown in excess Dump Valves.

of required limits, THEN OPERATE the Turbine Bypass 1) IF desired to enhance Valve to maintain all of the temperature control, THEN following as applicable: ISOLATE two Atmospheric Steam Dump Valves. Refer to

S/Gs within 50 psi of Psat Table 22-1.

for Average of Qualified CETs

As required to establish or support natural circulation

As required to establish or support two phase natural circulation (Continue)

C)= Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

@1 EMERGENCY OPERATING Revision 16 PROCEDURE Page 24 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

22. (Continued)

c. WHEN PCS cooldown rate can c.1. OPERATE Atmospheric Steam be controlled within required Dump Valves.

limits, THEN OPERATE the Turbine Bypass Valve to 1) IF desired to enhance cooldown at the maximum temperature control, THEN allowed rate. ISOLATE two Atmospheric Steam Dump Valves. Refer to Table 22-1.

Table 22-1

'A' S/G MV-MS101, ASDV CV-0782 Inlet MV-CA782, A/S to CV-0782 MV-MS103, ASDV CV-0781 Inlet OB MV-CA781, A/S to CV-0781

'B' S/G MV-MS102, ASDV CV-0779 Inlet OB MV-CA779, A/S to CV-0779 MV-MS104, ASDV CV-0780 Inlet CB MV-CA780, A/S to CV-0780 CAUTION Operating P-50A and P-50B simultaneously when Tc is less than 300°F is prohibited by Techncial Specifications.

d. ENSURE not more than two PCPs operating (preferably one in each loop.)

©= Continuously applicable step t,= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 I

T PROCEDURE Page 25 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

23. IF BOTH of the following conditions exist for each SIG:

At least three of four S/G pressure sigmas indicate between 510 and 550 psia (indicators between alarm flags)

A controlled cooldown is in progress THEN BLOCK MSIS for the S/G meeting the above conditions by performing ALL the following:

a. BLOCK MSIV closure signal for the applicable S/G by pushing the appropriate pushbutton on Control Panel C-01:

HS/LPE-50A ('A' S/G)

HS/LPE-50B ('B' S/G)

b. VERIFY "STEAM GEN VALVES ISOLATION LOCKOUT" (EK-0970) is alarmed.

c. ENSURE CLOSED BOTH Main Feed Reg Valves:

CV-0701 ('A' S/G)

CV-0703 ('B' SIG)

d. ENSURE CLOSED BOTH Bypass Feed Reg Valves:

CV-0735 ('A' S/G)

CV-0734 ('B' SIG) 0 = Continuously applicable step fo= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 EOP. PROCEDURE Page 26 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Use the following instruments to determine spray nozzle AT:

PZR Vapor Phase Temperature, TI-0101

Spray line temperature, TIA-01 03 or TIA-01 04 (use the lowest temperature if using main sprays)

Charging line temperature, TI-0212 (if using Auxiliary Spray)

C = Continuously applicable step 0= Hold Point

PALISADES PALISADES NUCLEAR PLANT ProcNo EOP-4.0 E EMERGENCY OPERATING Revision 16 PSPROCEDURE TE Page 27 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Use ANY of the following to determine Average of Qualified CETs:

PPC point "KCETA" (Average of Qualified CETs)

PPC Incore Qualified CET Map (PPC page 313)

Manual calculation. Refer to SOP-34, mPlant Process Computer (PPC) System."

© 25. VERIFY Si Pump throttling criteria 25.1. IF ANY of the SI Pump throttling are satisfied by ALL of the criteria can NOT be maintained, following: THEN RAISE HPSI flow AND START HPSI Pumps as necessary.

a. Based on the Average of Qualified CETs, PCS I VALVE subcooling meets ONE of the PUMP I NUMBER I'- -- DESCRIPTIONa following: ___-______Train 1

At least 250 F subcooled for 1 MO-3009 f HPSI Train 1 to Loop 1B non-degraded Containment P-66B MO-3011 HPSI Train 1 to Loop 2A conditions lMO-3007 HPSI Train I to Loop 1A MO-3013 HPSI Train 1 to Loop 2B

Greater than the minimum subcooling curve on EOP MO-3066 HPSI Train 2 to Loop 1B Supplement 1 for degraded P-66A MO-3064 HPSITrain 2 to Loop 2A Containment conditions MO-3068 HPSI Train 2 to Loop 1A

b. Corrected PZR level is greater . MO-3062 HPSI Train 2 to Loon 2B than 20% (40% for degraded Containment) and controlled.

REFER TO EOP Supplements 9 and 10.

(continue)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE [Page 28 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

25. (continued)

c. At least one S/G is available for PCS heat removal with corrected level being maintained or being restored to between 60% and 70%.

REFER TO EOP Supplement 11.

d. Operable RVLMS channels indicate greater than 102 inches above the bottom of fuel alignment plate (621' 8").

NOTE: Reactor Vessel Upper Head voiding resulting from controlled PCS pressure reductions is not expected to result in safety functions being jeopardized.

a. OPERATE PZR heaters and Main or Auxiliary PZR sprays.

b. IF SI Pump throttling criteria are met, THEN PERFORM ANY of the following:

1) CONTROL Charging and Letdown.

2) THROTTLE HPSI flow.

C) = Continuously applicable step) Irf= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 NUCLEAR A PROCEDURE Page 29 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

27. IF ALL of the following conditions exist:

PZR pressure is less than 1687 psia

SIAS is NOT actuated or blocked

'Safety Injection Signal Block Permit" (EK-1369) is alarmed

A controlled cooldown and/or controlled depressurization is in progress, THEN BLOCK SIAS by performing ALL of the following:

a. PLACE AND HOLD SIAS block handswitch PB3-1 to BLOCK.

1) VERIFY the following annunciator in alarm:

NSAFETY INJ BLOCK RELAY SI-1 " (EK-1 337)

2) RELEASE SIAS block handswitch PB3-1.

(continue)

--- =rr-Continuously applicable step fS=

(=HlHold Point on

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_UCLEPLANT PROCEDURE 1 Page 30 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

27. (continued)

b. PLACE AND HOLD SIAS block handswitch PB3-2 to BLOCK.

1) VERIFY the following annunciators in alarm:

"SAFETY INJ BLOCK RELAY SI-2" (EK-1338)

"SAFETY INJ BLOCKED" (EK-1339)

2) RELEASE SIAS block handswitch PB3-2.

28. IF HPSI Pumps are operating AND SI Pump throttling criteria are satisfied, THEN THROTTLE HPSI flow OR STOP one HPSI Pump at a time.

(- ,- V-ALVE 1- ---

PUMP -NUMBER l -DESCRIPTION

_ _-: ___ Train 1 MO-3009 HPSI Train 1 to Loop I B P-66B MO-3011 HPSI Train 1 to Loop 2A MO-3007 HPSBTrain I to Loop IA MO-3013 HPSI Train 1 to Loop 21A

-_--_ A- Train 2 MO-3066 HPSI Train 2 to Loop 1B P-66A MO-3064 HPSI Train 2 to Loop 2A

[MO-3068 HPSI Train 2 to Loop 1A MO-3062 I HPSI Train 2 to Loop 2B C)= Continuously applicable step) 0= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 X EMERGENCY OPERATING Revision 16 NUCLEAR PROCEDURE Page 31 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

29. IF LPSI Pumps are operating AND PZR pressure is being controlled greater than 200 psia, THEN PERFORM BOTH of the following:

a. STOP the operating LPSI Pumps:

P-67A

P-67B

b. CLOSE the LPSI injection valves:

MO-3008 LPSI Loop 1A

MO-3010 LPSI Loop 1B

MO-3012 LPSI Loop 2A

MO-3014 LPSI Loop 2B

30. IE PZR pressure lowers to less than 200 psia AND LPSI pumps have been stopped, THEN PERFORM BOTH of the following:

a. ENSURE OPERATING ALL available LPSI pumps:

P-67A

P-67B

b. ENSURE OPEN LPSI injection valves:

MO-3008 LPSI Loop 1A

MO-3010 LPSI Loop 1B

MO-3012 LPSI Loop 2A

MO-3014 LPSI Loop 2B 0 = Continuously applicable step Hold Point fV= Hold Point

Continuously applicable step t'

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 NUCLEARPLANT PROCEDURE Page 32 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

a. Post-RAS injection from Spent Fuel Pool. Refer to EOP Supplement 44.

b. Refill of SIRW Post-RAS. Refer to EOP Supplement 43.

32. IF Letdown is isolated AND BOTH of the following conditions exist:

SI Pump throttling criteria are met

Letdown is needed or desired, THEN RESTORE Letdown. Refer to EOP Supplement 27.

C = Continuously applicable step A=

f Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 I PROCEDURE [Page 33 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: PZR level instrument de-calibration occurs due to PCS pressure and containment temperature changes. Level correction is per EOP Supplements 9 and 10.

NOTE: IF the PCS is in a water solid condition for PCS Pressure Control, THEN the PZR level limit of 85% may be exceeded.

NOTE: PZR level should be maintained greater than 36% (40% for degraded Containment) to have continued availability of PZR Heaters.

33. IF Si Pump throttling criteria are met, THEN MAINTAIN corrected PZR level between 20% and 85% (42%

to 57% preferred) by performing ANY of the following:

a. THROTTLE HPSI flow.

b. CONTROL Charging and Letdown.

(continue)

C)= Continuously applicable step) t-= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 NUCLEARTPL PROCEDURE Page 34 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

33. (continued)

NOTE: IF an interruption in boration via Charging Pump to HPSI Train 2 occurs, THEN a different Si cold leg injection nozzle should be used when restoring flow.

1) ENSURE normal charging 1.1) IF the normal charging path is NOT path aligned as follows: available AND HPSI Train 2 is available, a) OPEN Charging Line THEN CHARGE to the PCS via the Stop Valve, CV-21 11. HPSI header by performing ALL of the following:

b) OPEN at least one Charging Stop Valve: 1) STOP ALL Charging Pumps.

0 CV-2 113 2) CLOSE Charging Line Stop 0

CV-2 115 Valve, CV-211 1.

c) IF BOTH Charging Stop 3) CLOSE Letdown Orifice Stop Valves fail to open THEN Valves:

ENSURE greater than 33 gpm flow through

CV-2003 CK-CVC21 12.

CV-2004

CV-2005

4) CLOSE Letdown Containment Isolation Valve CV-2009.

5) ENSURE CLOSED HPSI Pump B Discharge to Train 2, CV-3018.

(continue) (continue)

C = Continuously applicable step '&= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 NUCLEAR A PROCEDURE J Page 35 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

33. (continued) (continued)

6) OPEN ONE HPSI Train 2 Injection Valve:

S MO-3062 0 MO-3064 0

MO-3066 0

MO-3068

7) PLACE SIT Pressure Indicating Controller associated with valve opened above to MANUAL AND CLOSE:

0 PIC-0338, MO-3062 0

PIC-0347, MO-3064 0

PIC-0346, MO-3066 PIC-0342, MO-3068

8) OPEN Charging Pump Discharge to Train 2, MO-3072.

9) START Charging pumps as necessary to control PZR level.

©= Continuously applicable step t= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLELN PROCEDURE Page 36 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS C 34. MAINTAIN PCS pressure within the 34.1. IF the PCS is oversubcooled limits of EOP Supplement 1 by QO PZR pressure is greater than performing ANY of the following: the maximum limits of EOP Supplement 1,

a. CONTROL the following: THEN PERFORM ANY of the following to restore subcooling or 0 PZR heaters PCS pressure to within the 0

Main Spray appropriate limit:

S Auxiliary Spray (Supplement 37) a. OPERATE available S/G(s) to stop the cooldown

b. IE SI Pump throttling criteria are AND STABILIZE Qualified CET met, temperatures and Loop Tcs.

THEN CONTROL HPSI, Charging, and Letdown flows. b. OPERATE the following to lower PZR pressure within allowable limits:

Main Spray

Auxiliary Spray (Supplement 37)

c. IF SI Pump throttling criteria are met, THEN CONTROL HPSI, Charging, and Letdown flows.

34.2. IE PCS cooldown rate exceeds Technical Specification limits, THEN PERFORM ANY of the following to restore the cooldown rate to within Technical Specification limits:

a. OPERATE available S/G(s) to stop the cooldown AND STABILIZE Qualified CET temperatures and Loop Tcs.

(continue) (continue)

C = Continuously applicable step > = Hold Point -_

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

@ EMERGENCY OPERATING Revision 16 NUCLEAR PROCEDURE Page 37 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

34. (continued) (continued)

b. OPERATE the following to maintain PZR pressure within limits of EOP Supplement 1:

PZR heaters

Main Spray

Auxiliary Spray (Supplement 37)

Letdown

c. As directed by the Shift Supervisor, CONTINUE the PCS cooldown at less than or equal to Technical Specification limits. Refer to EOP Supplement 33.

C 35. ENSURE at least one S/G has corrected level being maintained or being restored to between 60% and 70%. Refer to EOP Supplement 11.

C = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 e EMERGENCY OPERATING Revision 16 NUCLEAR A PROCEDURE JPage 38 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

a. CALCULATE minimum PCS cooldown rate. Refer to EOP Supplement 2.

b. VERIFY BOTH of the following: b.1. LF additional sources of inventory which allow the requirements to be

The calculated cooldown met are NOT available, rate does NOT exceed THEN GO TO EOP-9.0, Technical Specification "Functional Recovery Procedure."

limits.

The calculated cooldown rate is achievable with the existing PCS heat removal path.

C)= Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 6 EMERGENCY OPERATING Revision 16 T PROCEDURE Page 39 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

Indicated Charging and Letdown flows do NOT correspond to PZR level trend.

PZR level rising significantly faster than trend expected from Auxiliary Spray flow.

Core AT (Average of Qualified CETs - Tc) or Loop AT (TH - Tc) rising for same secondary steaming and Auxiliary Feed rates.

Any operable PCS temperature indication is less than 250 F subcooled.

Operable RVLMS indicates voiding in the Reactor Vessel.

38. IE PCS voiding is indicated AND ANY of the following exist:

PCS pressure reduction is inhibited

PCS heat removal is inhibited

The Shift Supervisor directs void elimination, THEN PERFORM void elimination actions. Refer to EOP Supplement 26.

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEAR PLANT PROCEDURE Page 40 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

39. IF ANY of the following AC or DC 39.1. IF Bus 1D and Bus IE are NOT buses are NOT energized, energized, THEN RESTORE power to the IHEN as resources permit, affected buses. Refer to the PROVIDE power to PZR Heaters following applicable procedure: from Bus 1C. Refer to ONP-2.1, "Loss of AC Power," Attachment 1.

'BUS - PROCEDURE 1Cor 1D EOP Supplement 29 1E with No SIAS EOP Supplement 29 1E with SIAS SOP-30 Y10 ONP-24.1, "Loss of Preferred AC Bus Y10" Y20 ONP-24.2, "Loss of Preferred AC Bus Y20" Y30 ONP-24.3, "Loss of Preferred AC Bus Y30" Y40 ONP-24.4, 'Loss of Preferred AC Bus Y40" Y01 ONP-24.5, 'Loss of Instrument AC Bus Y0 Any DC Bus ONP-2.3, "Loss of DC Power"

©= Continuously applicable step t,= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 LEAPLN PROCEDURE Page 41 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

40. IF offsite power was lost AND offsite power is available, THEN RESTORE power to plant equipment by performing ALL of the following:

a. IF NONE of the following are energized:

'R' Bus

'F' Bus

Cook 1 Line, THEN INITIATE actions to restore power to 'F' or 'R' Bus, as available. Refer to EOP Supplement 21.

b. WHEN ANY of the following are energized:

'R' Bus

'F' Bus

Cook 1 Line, THEN INITIATE actions to restore Plant power. Refer to EOP Supplement 29.

(continue)

C = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEAR PLA PROCEDURE Page 42 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

40. (continued)

c. RESTORE power to the affected bus(es). Refer to the following applicable procedure:

l .- BUS : --. . PROCEDURE ;l (without SIS) EOP Supplement 29 (i1 E SOP-30 or 1B ONP-2.1, "Loss of l~orlBAC Power

d. RESTART plant equipment as desired.

0) =

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 43 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Each D/G is limited to the following load rating:

2500 KW continuous

2750 KW two hours per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

41. WHEN 2400V Bus 1C or Bus 1D is 41.1. IF equipment needed to maintain energized, Safety Functions is available from THEN as resources permit, a de-energized 2400V Vital Bus ENERGIZE Plant buses by AND a power supply is available, performing ALL of the following: THEN ENERGIZE the bus AND RESTORE the needed equipment.

a. IF Bus 1C is energized, THEN PERFORM ALL of the following:

1) ENSURE CLOSED the following breakers:

152-115(BuslCto Transformers 11 and 19)

152-108 (Bus 1C to Transformer 13)

(continue)

C)== Continuously aDplicable

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 NUCLER PROCEDURE Page 44 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

41. (continued)

2) ENSURE 480V MCCs are energized as appropriate:

MCC1: 52-1906 (Bus 19)

MCC 3: 52-1301 (Bus 13)

MCC 7: 52-1103 (Bus 11)

b. IE Bus 1D is energized, THEN PERFORM the following:

1) ENSURE CLOSED 152-201 (Bus 1D to Transformers 12 and 20)

2) ENSURE 480V MCCs energized as appropriate:

MCC 2: 52-2006 (Bus 20)

MCC 8: 52-1201 (Bus 12)

(continue)

= Continuously 0 = applicable step step 'f= Hold 15= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 p EMERGENCY OPERATING Revision 16 PROCEDURE Page 45 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

41. (continued)

NOTE: IF only one MCC is available (MCC 1 or MCC 2),

THEN BOTH vital DC Buses should be powered from the two Battery Chargers supplied by the same energized MCC.

c. ENSURE CLOSED Battery Charger Feeder Breakers from available MCCs:

1) MCC 1 Charger No 1 Feeder 52-146

Charger No 4 Feeder 52-1 86

2) MCC 2

Charger No 2 Feeder 52-225

Charger No 3 Feeder 52-285

d. VERIFY 125V DC Buses D10 d.1. PLACE Battery Chargers in and D20 are powered by a operation. Refer to SOP-30, Battery Charger. "Station Power."

C = Continuously applicable step f-= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLERPLA PROCEDURE Page 46 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

42. IF ALL PCPs are stopped, 42.1. ENSURE proper control of S/G THEN VERIFY natural circulation feeding and steaming rates.

flow in at least one PCS loop by ALL of the following:

Core AT less than 500 F (Average of Qualified CETs minus Tc)

Loop THS and Loop Tcs constant or lowering

Average of Qualified CETs at least 250 F subcooled

Difference between Loop TH and Average of Qualified CETs is less than or equal to 150 F

43. IF ALL PCPs are stopped, AND natural circulation criteria are NOT satisfied, THEN ENSURE ALL of the following conditions exist:

All available Charging pumps are operating

Si flow is within the limits of EOP Supplement 4

At least one S/G is available for removing heat from PCS with level being maintained or restored to between 60%

and 70%

Average of Qualified CETs is less than superheated C) = Continuously applicable step t0= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEA-LA PROCEDURE Page 47 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

44. WHEN BOTH of the following conditions exist:

PZR Pressure within limits of EOP Supplement 1

PCS Cooldown rate is within required limits THEN PLACE LTOP in service as follows:

a. ENSURE OPEN PORV Isolation Valves. Refer to SOP-1 B, "Primary Coolant System -

Cooldown," Attachment 6.

b. PLACE BOTH of the following PORV LTOP enable keyswitches to ENABLE:

HS-0105A (Key: 1)

HS-0105B (Key: 4)

c. PLACE BOTH of the following PORV Handswitches to AUTO:

HS-1042B

HS-1 043B

d. MAINTAIN PZR pressure within limits of EOP Supplement 1.

45. WHEN PCP restart is desired, THEN RESTART desired PCPs.

Refer to EOP Supplement 3.

C)= Continuously applicable step

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR PROCEDURE Page 48 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

46. WHEN required shutdown boron concentration has been established (approximately 30 to 45 minutes using all charging pumps),

THEN ALIGN Charging Pump suction to SIRWT. Refer to EOP Supplement 40.

C 47. VERIFY the containment sump 47.1. IF Containment Sump level is NOT level is rising as the SIRWT level is rising as SIRWT level lowers, lowering. THEN PERFORM ALL of the following:

a. CONFIRM the LOCA is outside containment.

b. INITIATE actions to makeup to the SIRWT. Refer to one of the following:

SOP-2A, "Chemical &

Volume Control System Charging & Letdown"

SOP-1 7A, "Clean Radioactive Waste System"

c. IF "CIS INITIATED" (EK-1 126) is clear, THEN MANUALLY INITIATE CIS by pushing left or right HIGH RADIATION INITIATE pushbuttons on EC-13 AND PERFORM EOP Supplement 6.

0 CHRL-CS 0 CHRR-CS

d. NOTIFY the TSC.

0 = Continuously applicable step Point G'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 49 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

48. WHEN SIRWT level less than or equal to 25%,

THEN prior to RAS, PERFORM Pre-RAS Actions. Refer to EOP Supplement 42.

CAUTION Each D/G is limited to a 2500 KW continuous load rating and a 2750 KW two-hour load rating. Operation of VC-10 (VC-11) will draw approximately 44 KW.

49. IE Control Room HVAC Compressor VC-1 0 or VC-1 1 tripped on high temperature due to low SW flow, THEN RESET AND START VC-10 or VC-1 1.

C) = step 0= Hold Point t=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

~ EMERGENCY OPERATING Revision 16 NUCPLAN PROCEDURE Page 50 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Subsequent to the actions in Step 50, the TSC must approve closure of ANY of the failed open valves.

50. WHEN Containment water level approaches the level specified below, THEN ENSURE OPEN the following valves AND OPEN associated breakers:

Cntmt ;. Valve.

Water Lev Number Bkr -Description,.

MCC No. 1 MO-3008 52-141 LPSI Loop 1A 595919 MO-3010 52-147 LPSI Loop IB MO CNo. 2 MO-3012 52-2471 LPSI Loop2A MO-3014 52-2511 LPSI Loop 2B

_____ .MCCNo.1 -

MO-3009 52-1971 HPSI Train 1 to Loop 1B MO-3011152-157 HPSI Train 1 to Loop 2A MO-3007 52-137 HPSI Train 1 to Loop 1A MO-3013 52-151 HPSI Train 1 to Loop 2B 596'4' - .-

__ MOOCC No.2 MO-3066 52-257 HPSI Train 2 to Loop 1B MO-3064 52-237 HPSI Train 2 to Loop 2A MO-3068 52-261 HPSI Train 2 to Loop 1A MO-3062 52-241 HPSI Train 2 to Loop 2B 0 = Continuously applicable step) lA= Hold Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLA PROCEDURE Page 51 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Premature initiation of RAS can lead to insufficient Containment Sump inventory for SI Pump operation. Minimum Containment Water level of 594' 1" is necessary for adequate ESS pump NPSH.

51. WHEN BOTH of the following conditions exist:

LOCA inside Containment

SIRWT level lowers to less than 2%

THEN REFER TO EOP Supplement 42 AND PERFORM the following:

a. Post-RAS actions

b. MONITOR for indications of sump screen clogging.

52. IF Containment Water level is less than 594' 1" following a RAS, THEN CONSULT with TSC for additional guidance.

C)-= Continuously applicable step

'=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16

_ PROCEDURE [Page 52 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

53. IF RAS is initiated, THEN PERFORM the following:

a. IE BOTH HPSI Pumps are a.1. IF total HPSI Pump flow less than operating, 100 gpm, THEN VERIFY total HPSI Pump THEN PERFORM ALL of the flow greater than 100 gpm. following:

1) STOP ALL Charging Pumps.

Refer to EOP Supplement 39, "Alternate Methods of Reducing PCS Pressure," as needed to control PZR pressure.

2) IE total HPSI Pump still has flow less than 100 gpm, THEN STOP one HPSI Pump.

b. IE one HPSI Pump is operating, b.1. IE the operating HPSI Pump has THEN VERIFY the operating flow less than 50 gpm, HPSI Pump has flow greater THEN PERFORM ALL of the than 50 gpm. following:

1) STOP ALL Charging Pumps.

Refer to EOP Supplement 39, "Alternate Methods of Reducing PCS Pressure," as needed to control PZR pressure.

2) IF the operating HPSI Pump still has flow less than 50 gpm, THEN STOP the HPSI Pump.

3) CONSULT with the TSC for further guidance.

C) = Continuously applicable step G'= Hold Point

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a. IF 3 Containment Spray Pumps are operating, THEN STOP one Containment Spray Pump (P-54B or P-54C preferred.)

b. THROTTLE HPSI flow to b.1. IF HPSI loop isolation valves are achieve 200 to 250 gpm flow to de-energized, each operating train using THEN PERFORM the following:

either Option 1 or Option 2:

1) STOP one HPSI pump.

2) ENERGIZE and CLOSE two HPSI loop isolation valves associated with the operating HPSI pump (Refer to Option 1 or 2).

(Continue) (Continue)

C)= Continuously applicable step fS= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEAR PLA PROCEDURE Page 54 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

54. (Continued) (Continued)

OPTION 1 - OPTION 1. - -

POSITION NUMBER --'DESCRIPTION BKR '-NUMBER,' ]_--`DESCRIPTION

' . _ . Train 1 (P-66B) ' ' '

Closed MO-3009 HPSI Trn 1 to Loop 1B -. Trainn 1 (P-66B) '..----. .,: .'

Closed MO-3013 HPSI Trn 1 to Loop 2B 52-197 MO-3009 HPSI Trn 1 to Loop 1B Throttled MO-3011 HPSI Trn 1 to Loop 2A 52-151 MO-3013 HPSI Trn 1 to Loop 2B Throttled MO-3007 HPSI Trn 1 to Loop 1A '.',:.Train 2 (P-66A) -

,....-. -.Train 2 (P-66A)'52-237 MO-3064 HPSI Trn 2 to Loop 2 Closed MO-3064 HPSI Trn 2 to Loop 2A Closed MO-3068 HPSI Trn 2 to Loop 1A 52-261 MO-3068 HPSI Trn 2 to Loop 1A Throttled MO-3066 HPSI Trn 2 to Loop 1B Throttled MO-3062 HPSI Trn 2 to Loop 2B OPTION 2-BKR - NUMBER DESCRIPTION:

OPTION 2 -

-Train 1 (P-66B) -

POSITION NUMBER: DESCRIPTION

'._______ . ;'Train 1.(P-66B) -,52-157 MO-3011 HPSI Trn to Loop 2A Closed MO-3011 HPSI Trn 1 to Loop 2A 52-137 MO-3007 HPSI Trn 1 to Loop 1A Closed MO-3007 HPSI Trn 1 to Loop 1A - - Train 2 (P-66A)

Throttled MO-3009 HPSI Trn 1 to Loop 1B 52-257 MO-3066 HPSI Trn 2 to Loop 1B Throttled MO-3013 HPSI Trn 1 to Loop 2B 52-241 MO-3062 HPSI Trn 2 to Loop 26

. -: ,--.-,.'Train 2 (P-66A-Closed MO-3066 HPSI Trn 2 to Loop 1B Closed MO-3062 HPSI Trn 2 to Loop 2B Throttled MO-3064 HPSI Trn 2 to Loop 2A Throttled MO-3068 HPSI Trn 2 to Loop 1A (Continue)

C == Continuously

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 55 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

54. (Continued)

c. STOP remaining operating Containment Spray Pumps as follows:

1) IF containment pressure greater than 4 psig OR CHP NOT reset, THEN CLOSE one containment spray valve.

a) PLACE one CHP Bypass Switch to BYPASS:

HS-3001C, CV-3001 (Key: 397)

HS-3002C, CV-3002 (Key: 396) b) ENSURE CLOSED associated Containment Spray Valve:

CV-3001

CV-3002

2) STOP all Containment Spray Pumps.

0 P-54A 0

P-54B P-54C (Continue)

C)=

= Hold Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

~ EMERGENCY OPERATING Revision 16 PROCEDURE Page 56 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

54. (Continued)

3) ENSURE BOTH CHP Bypass Switches in BYPASS.

HS-3001C, CV-3001 (Key: 397)

HS-3002C, CV-3002 (Key: 396)

4) ENSURE CLOSED BOTH Containment Spray Valves:

CV-3001

CV-3002

d. MONITOR HPSI pump for d.1. IF HPSI pump performance does improved or stable NOQT improve, performance. THEN PERFORM the following:

1) IF HPSI loop isolation valves are energized, THEN THROTTLE HPSI flow to 50 to 100 gpm on each operating train (low in the band preferred.)

2) IF HPSI pump performance is NOT improved, THEN STOP HPSI pump.

3) iE HPSI pump performance improves, THEN RAISE flow to a point where stable pump performance can be (Continue) maintained.

C)= Continuously applicable step fA= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 PROCEDURE Page 57 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

54. (Continued)

e. NOTIFY TSC to begin monitoring for SAMG entry conditions.

f. GO TO EOP-9.0

55. PLACE the following ESS Room Sump Pump handswitches in OFF AND CAUTION TAG "Do Not Use -

LOCA in Progress":

0 East P-72A (42-165ASS) 0 East P-72B (42-165BSS) 0 West P-73A (42-155ASS) 0 West P-73B (42-155BSS)

56. IE Charging Pump suction is aligned to the SIRWT AND RAS has initiated, THEN PERFORM ALL of the following:

a. STOP ALL Charging Pumps:

P-55A S

P-55B S

P-55C

b. RACK OUT ALL Charging Pump breakers:

-CHARGING :. ; BREAKER

- PUMP -.. _.- . ...

P-55A 52-1205 P-55B ;52-1308

. P-55B 52-1120 t P-55C 1 52-1105 (continue)

X)== Continuously applicable step)

'=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 LS2^iT PROCEDURE Page 58 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

56. (continued)

c. PLACE a Caution Tag on their handswitches that reads "Do NOT Use - No suction source available'

52-1205CS

52-1206CS

52-1105CS

57. IF ALL operable Containment Area Radiation Monitors indicate less than 1 x 101 R/hr AND Containment pressure is less than 3.0 psig, THEN RESET CHR by pushing the following:

The RESET pushbutton on each Containment Area Radiation Monitor.

BOTH left and right HIGH RADIATION RESET pushbuttons on C-13.

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUOCLERLAT PROCEDURE Page 59of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Failure of Instrument Air to containment will prevent venting the SITs.

58. IF PZR pressure is between 58.1. IF ANY SIT could NOT be isolated, 350 psia and 300 psia as read on THEN VENT the unisolated SIT P1-0104 (NR) or PR-0125 and using ONE of the following:

controlled AND a controlled cooldown is in a. VENT to containment as progress, follows:

THEN ISOLATE SITs as follows:

1) ENSURE CLOSED CWRT

a. UNLOCK AND CLOSE the Vent Isolation Valves:

following breakers:

CV-1 064 BREAKER

-OUTLET VALVET -sr

CV-1 065

..-i-;,V A LV E --.

52-2129 MO-3041 T-82A 2) VENT each unisolated SIT 52-2329 MO-3045 T-82B one tank at a time by 52-2229 MO-3049 T-82C opening the Vent Valve and 52-2429 MO-3052 T-82D closing when tank is vented.

S

-sr -VENTVALVE -

KEY: 190 I T-82A CV-3067

b. CLOSE the following SIT Outlet T-82B CV-3065 Valves: T-82C CV-3063 J T-82D CV-3051

.BREAKER OUTLET. l KEY- KVEALVE EY-52-2129 MO-3041 98 52-2329 MO-3045 99 52-2229 MO-3049 100 52-2429 MO-3052 101 (continue) (continue)

G) = Continuously applicable step t0= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR - PROCEDURE IPage 60 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

58. (continued) (continued)

3) WHEN ALL the following conditions are met:

Unisolated SITs are vented and their associated vent valve closed

Plant conditions allow venting containment THEN OPEN CWRT Vent Isolation Valves:

CV-1 064

CV-1065

b. VENT unisolated SITs via Clean Waste Receiver Tank Header per SOP-3, "Safety Injection and Shutdown Cooling System."

C)=

=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 NU}CLEAR PL PROCEDURE Page 61 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

59. 1F the elapsed time from event 59.1. IF hot leg injection can NOT be initiation (EOP Entry) is 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months established via the normal path, AND Shutdown Cooling will NOT THEN INITIATE hot leg injection be in service prior to 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after via HPSI flow through the PZR.

event initiation (EOP Entry) Refer to EOP Supplement 20.

AND ANY of the following conditions are satisfied:

Based on the Average of Qualified CETs, PCS subcooling meets ONE of the following:

o Less than 25 0 F subcooled for non-degraded Containment conditions o Less than the minimum subcooling curve on EOP Supplement 1 for degraded Containment conditions

Corrected PZR level is less than 20% (40% for degraded Containment) (Refer to EOP Supplements 9 and 10)

Operable RVLMS channels indicate less than 102 inches above the bottom of fuel alignment plate, THEN ESTABLISH simultaneous hot and cold leg injection by performing ALL of the following in the order listed:

(continue)

C)= Continuously applicable step G'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 LS2\UiJ PROCEDURE FPage 62 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

59. (continued)

a. CLOSE HPSI Train 2 to Cold Leg Valve, MO-3080.

(KEY: 117)

b. OPEN HPSI Train 2 to Hot Leg Valve, MO-3082.

(KEY: 118)

c. CLOSE HPSI Train 1 to Cold Leg Valve, MO-3081.

(KEY:1 15)

d. OPEN HPSI Train 1 to Hot Leg Valve, MO-3083.

(KEY: 116)

e. IF HPSI Train 2 is in operation, THEN VERIFY HPSI flow to Loop 1 hot leg on Fl-0316A.

f. IF HPSI Train 1 is in operation, THEN VERIFY HPSI flow to Loop 1 hot leg on Fl-0317A.

g. OBSERVE HPSI flow to PCS cold legs on the following indicators:

0 FI-0308A 0

FI-031 OA S

FI-0312A S FI-0313A (continue) 0 == Continuously applicable step

t'= Hold Point

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59. (continued)

h. VERIFY total HPSI flow to Loop 1 hot leg is approximately equal to total HPSI flow to cold legs.

FI-031 6A 0 FI-031 7A

i. VERIFY the following:

Total HPSI flow is within acceptable limits. Refer to EOP Supplement 4.

Containment spray flow is within acceptable limits.

Refer to SFSC, Table CA.

Q=

'=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PLANT PROCEDURE JPage 64 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

60. IF measured Containment hydrogen concentration is between 1%and 3%,

THEN PERFORM ALL the following:

CAUTION Each D/G is limited to a 2500 KW continuous load rating and a 2750 KW two-hour load rating. A hydrogen recombiner will draw a maximum of 75 KW.

a. PLACE at least one Hydrogen Recombiner in service. Refer to SOP-5, "Containment Air Cooling and Hydrogen Recombining System."

b. OPEN MCC 9 Feeder Breaker, 52-1304.

LOCATION: On Bus 13

61. IF Si Pump Throttling criteria are satisfied, THEN RESET SIAS. Refer to SOP-3, "Safety Injection and Shutdown Cooling System,"

Attachment 4.

C)== Continuously applicable step

(= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR srPROCEDURE Page 65 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

62. WHEN ALL of the following Shutdown Cooling System entry conditions are met:

PCS parameters are acceptable for existing Containment conditions:

Containment

'Containment Greater Than or Less Than EqualTo 175 0 F

-1750 FAND 'D Greater

,.LessThan; Than or Equal

, 3 psig at all

' To 3 psig at any times during the time during the Parameter - event event PCs Pressure Less Than REFER TO EOP 270 psia Supplement 1 PZR Level Greater than 36% Greater than 40%

and controlled and controlled Avg of Qualified Greaterthan REFER TO EOP CETs Subcooling 25 0F Supplement 1 vg of Qualified Less than 300'F REFER TO EOP ETs and Loop Supplement 1

.s TemDerature

TSC has determined that PCS activity is acceptable for circulation outside Containment.

Containment Spray Pumps are NOT in use for Containment Atmosphere safety function.

Shutdown Cooling System monitoring equipment power is available from Y01.

( n (Continue)

C)=

'&= Hold

= Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 LA2T PROCEDURE I Page 66 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

62. (Continued)

Alternate measures for loss of Y01 are established. REFER TO ONP-17, "Loss of Shutdown Cooling."

LTOP operable.

Power to the following Shutdown Cooling Return Valves is available:

0 MO-3015 (MCC-1) 0 MO-3016 (MCC-2)

OR Access to Containment is acceptable for manual valve operation.

THEN PERFORM the following:

(continue)

Q)= Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEARPLANT PROCEDURE Page 67 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

62. (continued)

a. IE hot leg injection is in use, THEN SECURE hot leg injection as follows:

1) CLOSE HPSI Train 2 to Hot Leg Valve, MO-3082.

(KEY: 118)

2) OPEN HPSI Train 2 to Cold Leg Valve, MO-3080.

(KEY: 117)

3) CLOSE HPSI Train 1 to Hot Leg Valve, MO-3083.

(KEY: 116)

4) OPEN HPSI Train 1 to Cold Leg Valve, MO-3081.

(KEY: 115)

b. STOP operating HPSI and LPSI Pumps.

c. ENSURE SIAS is reset. Refer to SOP-3, "Safety Injection and Shutdown Cooling System,"

Attachment 4.

d. GO TO GOP-9, "Mode 3 2 525 OF to Mode 4 or Mode 5" or TSC/PRC approved procedure.

63. IFSDC entry conditions can NOT be established, THEN MAINTAIN long-term cooling.

0 =© ContinuousIv Cotnuul

~ ~= armlicable ster) f==Hl

.Dlcbese Hold Point on

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 LPLA PROCEDURE Page 68 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

64. IF the LOCA is isolated, THEN PERFORM Steps 65 through 96.

NOTE: Use ANY of the following to determine Average of Qualified CETs:

PPC point "KCETA" (Average of Qualified CETs)

PPC Incore Qualified CET Map (PPC page 313)

Manual calculation. Refer to SOP-34, "Plant Process Computer (PPC) System."

© 65. VERIFY SI Pump throttling criteria 65.1. IF ANY of the SI Pump throttling are satisfied by ALL of the criteria can NOT be maintained, following: THEN RAISE HPSI flow AND START HPSI Pumps as necessary.

a. Based on the Average of Qualified CETs, PCS UM . =.VALVED subcooling meets ONE of the UNUMBER DESCRIPTION following: - Train1 .

MO-3009 HPSI Train 1 to Loop 1B

At least 250 F subcooled for non-degraded Containment I MO-3011 P-66B MO-P HPSI Train 1 to Loop 2A n

conditions MO-3007 HPSI Train I to Loop 1A jMO-3013 HPSI Train 1ito Loop 2B

Greater than the minimum Train2 -

subcooling curve on EOP MO-3066 HPSI Train 2 to Loop 1B Supplement 1 for degraded P-66A MO-3064 HPSI Train 2 to Loop 2A Containment conditions MO-3068 HPSI Train 2 to Loop 1A MO-3062 HPSI Train 2 to Loop 2A (continue)

O = Continuously applicable step tS= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 69 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

65. (continued)

b. Corrected PZR level is greater than 20% (40% for degraded Containment) and controlled.

REFER TO EOP Supplements 9 and 10.

c. At least one S/G is available for PCS heat removal with corrected level being maintained or being restored to between 60% and 70%.

REFER TO EOP Supplement 11.

d. Operable RVLMS channels indicate greater than 102 inches above the bottom of fuel alignment plate (621' 8").

C)= Continuously applicable step 'Py= Hold Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCPLANT PROCEDURE Page 70 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

66. IF HPSI Pumps are operating AND Si Pump throttling criteria are satisfied, THEN THROTTLE HPSI flow OB STOP one HPSI Pump at a time.

___UMP__

- -_l_NUMBERl:

VALVE DESCRIPTION,-

-_-_-_-Train 1 MO-3009 HPSI Train 1 to Loop 1B P-66B MO-3011 HPSI Train 1 to Loop 2A MO-3007 HPSI Train 1 to Loop 1A MO-3013 HPSI Train I to Loop 2B

.__-- Train2 ---

MO-3066 HPSI Train 2 to Loop I B MO-3064 HPSI Train 2 to Loop 2A P-66A MO-3068 HPSI Train 2 to Loop 1A

____MO-3062 IHPSI Train 2 to Loop 2B C) = ContinuousIV applicable step A~= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 1 EMERGENCY OPERATING Revision 16 1 PROCEDURE Page 71 of 1.09 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

67. IF LPSI Pumps are operating AND PZR pressure is being controlled greater than 200 psia, THEN PERFORM BOTH of the following:

a. STOP the operating LPSI Pumps:

P-67A

P-67B

b. CLOSE the LPSI injection valves:

MO-3008 LPSI Loop 1A

MO-3010 LPSI Loop 1B

MO-3012 LPSI Loop 2A

MO-3014 LPSI Loop 2B

68. IE PZR pressure lowers to less than 200 psia AND LPSI pumps have been stopped, THEN PERFORM BOTH of the following:

a. ENSURE OPERATING ALL available LPSI pumps:

P-67A

P-67B

b. ENSURE OPEN LPSI injection valves:

MO-3008 LPSI Loop 1A

MO-3010 LPSI Loop 1B

MO-3012 LPSI Loop 2A

MO-3014 LPSI Loop 2B 0 = Continuously applicable step 'ef= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 72 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

69. IF Letdown is isolated AND BOTH of the following conditions exist:

Si Pump throttling criteria are met

Letdown is needed or desired, THEN RESTORE Letdown. Refer to EOP Supplement 27.

C 70. VERIFY the PCS is NOT in a water 70.1. IF water solid PCS condition is solid condition as indicated by indicated, BOTH of the following: THEN MAINTAIN the PCS within the limits of EOP Supplement 1 by

a. No exaggerated or severe ANY of the following:

pressure response to PCS inventory or temperature a. OPERATE available S/G(s) to changes. control the cooldown AND STABILIZE Qualified CET

b. ANY of the following: temperatures and Loop Tcs.

Corrected PZR level is less b. IF Si Pump throttling criteria are than 100%. REFER TO met, EOP Supplements 9 and 10 THEN CONTROL HPSI, Charging, and Letdown flows.

RVLMS indicates voiding a = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 t EMERGENCY OPERATING Revision 16 pLANT PROCEDURE Page 73 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

71. IF it is desired to draw a bubble in the PZR, THEN PERFORM ALL of the following:

a. ENSURE ENERGIZED ALL available PZR heaters.

b. IF ANY of the following conditions exist:

Both S/G pressures can be maintained below the existing PCS pressure

At least one PCP is operating THEN PERFORM ALL of the following to reduce PCS pressure:

1) IF SI Pump throttling criteria are met, THEN CONTROL Charging, Letdown, and HPSI flow.

2) INITIATE PCS cooldown within Technical Specification limits.

3) MONITOR the PCS cooldown rate using PPC.

Refer to EOP Supplement 33.

(continue)

C)= Continuously applicable step '&= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEARPROCEDURE Page 74 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

71. (continued)

4) MAINTAIN PCS temperature and pressure within the limits of EOP Supplement 1.

5) MAINTAIN 250 F subcooling.

c. IE a bubble forms in the Reactor Vessel Upper Head region, THEN PERFORM BOTH of the following:

1) CONTROL Charging, Letdown, and HPSI flow to maintain PCS level greater than the 102 inches above the bottom of fuel alignment plate (621' 8").

2) CONTINUE efforts to draw a bubble in the PZR.

72. IF Si Pump throttling criteria are met, THEN MAINTAIN corrected PZR level between 20% and 85% (42%

to 57% preferred) by performing ANY of the following (Refer to EOP Supplements 9 and 10):

a. CONTROL Charging and Letdown.

b. THROTTLE HPSI flow.

C)= Continuously applicable step fS= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 UCE PROCEDURE Page 75 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS C) 73. MAINTAIN PCS pressure within the 73.1. IE the PCS is oversubcooled limits of EOP Supplement 1 by QB PZR pressure is greater than performing ANY of the following: the maximum limits of EOP Supplement 1,

a. CONTROL the following: THEN PERFORM ANY of the following to restore subcooling or 0 PZR heaters PCS pressure to within the S

Main Spray appropriate limit:

S Auxiliary Spray (Supplement 37) a. OPERATE available S/G(s) to stop the cooldown

b. IF SI Pump throttling criteria are AND STABILIZE Qualified CET met, temperatures and Loop Tcs.

THEN CONTROL HPSI, Charging, and Letdown flows. b. OPERATE the following to lower PZR pressure within allowable limits:

Main Spray

Auxiliary Spray (Supplement 37)

c. IF SI Pump throttling criteria are met, THEN CONTROL HPSI, Charging, and Letdown flows.

73.2. IF PCS cooldown rate exceeds Technical Specification limits, THEN PERFORM ANY of the following to restore the cooldown rate to within Technical Specification limits:

a. OPERATE available S/G(s) to stop the cooldown AND STABILIZE Qualified CET temperatures and Loop Tcs.

(continue) (continue)

C)= Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCEAORPLANT PROCEDURE Page 76 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

73. (continued) (continued)

b. OPERATE the following to maintain PZR pressure within limits of EOP Supplement 1:

PZR heaters

Main Spray

Auxiliary Spray (Supplement 37)

Letdown

c. As directed by the Shift Supervisor, CONTINUE the PCS cooldown at less than or equal to Technica! Specification limits. Refer to EOP Supplement 33.

0 = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR PROCEDURE Page 77 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS C 75. PERFORM ALL of the following:

a. CALCULATE minimum PCS cooldown rate. Refer to EOP Supplement 2.

b. Verify BOTH of the following: b.1. IF additional sources of inventory which allow the requirements to be

The calculated cooldown met are NOT available, rate does NOT exceed THEN GO TO EOP-9.0, Technical Specification "Functional Recovery Procedure.'

limits.

The calculated cooldown rate is achievable with the existing PCS heat removal path.

76. EVALUATE the need for a plant cooldown based on ALL of the following:

Technical Specifications require plant cooldown

Plant equipment repair requires plant cooldown

Availability of Auxiliary systems

Available Feedwater reserve inventory

The Shift Supervisor deems plant cooldown is necessary

77. IE a plant cooldown is NOT required, THEN GO TO Step 87.

C)= Continuously applicable step fP= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 L£2LAJ PROCEDURE [Page 78 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: IF emergency boration is in progress, THEN cooldown may commence/continue while the required shutdown margin value is calculated.

C 78. VERIFY PCS boron concentration 78.1. IF PCS boron concentration is less greater than or equal to required than required boron concentration, boron concentration as verified by THEN PERFORM BOTH of the sample or hand calculation. Refer following:

to EOP Supplement 35.

a. ENSURE emergency boration is

a. IF Emergency boration is in in progress.

progress AND PCS boron concentration b. WHEN required boron is greater than or equal to concentration is reached, required boron concentration, THEN SECURE emergency THEN SECURE emergency boration. Refer to EOP boration. Refer to EOP Supplement 40.

Supplement 40.

0 = Continuously applicable step '(= Hold Point

PALISADES PALISADES NUCLEAR PLANT ProcNo EOP-4.0 EMERGENCY OPERATING Revision 16 IEOCj PROCEDURE Page 79 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION A maximum PZR cooldown rate of 2000F/Hr and a maximum PZR Spray AT (PZR vapor temp - spray temp) of 350TF should be observed to prevent damage to the PZR or Spray Nozzle.

NOTE: PZR level indication decalibration will occur during cooldown. Correction curves in EOP Supplement 9, "Pressurizer Level Corrections Hot Calibrated" or EOP Supplement 10, "Pressurizer Level Corrections Cold Calibrated" should be used.

NOTE: S/G level indication decalibration will occur during cooldown. Correction curves in EOP Supplement 11, "S/G Level Correction" should be used.

NOTE: Steam flow through two of the four Atmospheric Steam Dump Valves should be adequate to establish an initial cooldown rate of 750F/hr.

(continue) 0 =

= Hold Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 L) R2AT PROCEDURE [Page 80 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

79. (continued)

a. REFER TO the following:

EOP Supplement 1, Pressure and Temperature Limit Curves

EOP Supplement 33, PCS Heatup/Cooldown Rate Data

b. IF safety injection flow is b.1. OPERATE Atmospheric Steam causing a cooldown in excess Dump Valves.

of required limits, THEN OPERATE the Turbine Bypass 1) IF desired to enhance Valve to maintain all of the temperature control, THEN following as applicable: ISOLATE two Atmospheric Steam Dump Valves. Refer

S/Gs within 50 psi of Psat to Table 79-1.

for Average of Qualified CETs

As required to establish or support natural circulation

As required to establish or support two phase natural circulation (Continue) 0 = Continuously applicable step) t,= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

@ EMERGENCY OPERATING Revision 16 NUCLEAR PROCEDURE Page 81 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

79. (Continued)

c. WHEN PCS cooldown rate can c.1. OPERATE Atmospheric Steam be controlled within required Dump Valves.

limits, THEN OPERATE the Turbine Bypass Valve to 1) IF desired to enhance cooldown at the maximum temperature control, THEN allowed rate. ISOLATE two Atmospheric Steam Dump Valves. Refer to Table 79-1.

Table 79-1

'A' S/G MV-MS101, ASDV CV-0782 Inlet MV-CA782, A/S to CV-0782 MV-MS1 03, ASDV CV-0781 Inlet M

MV-CA781, A/S to CV-0781

'B' S/G MV-MS102, ASDV CV-0779 Inlet QB MV-CA779, A/S to CV-0779 MV-MS104, ASDV CV-0780 Inlet MV-CA780, A/S to CV-0780 CAUTION Operating P-50A and P-50B simultaneously when Tc is less than 300°F is prohibited by Techncial Specifications.

d. ENSURE not more than two PCPs operating (preferably one in each loop.)

0 == Continuously applicable step)

'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 82 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

80. WHEN BOTH of the following conditions exist:

PZR Pressure within limits of EOP Supplement 1

PCS Cooldown rate is within required limits THEN PLACE LTOP in service as follows:

a. ENSURE OPEN PORV Isolation Valves. Refer to SOP-1 B,

'Primary Coolant System -

Cooldown," Attachment 6.

b. PLACE BOTH of the following PORV LTOP enable keyswitches to ENABLE:

HS-0105A (Key: 1)

HS-0105B (Key: 4)

c. PLACE BOTH of the following PORV Handswitches to AUTO:

HS-1 042B

HS-1 043B

d. MAINTAIN PZR pressure within limits of EOP Supplement 1.

0 = Continuously applicable step) f-= Hold Point

(= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

@ EMERGENCY OPERATING Revision 16 NUCLEAR NTPROCEDURE Page 83 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Use the following instruments to determine spray nozzle AT:

PZR Vapor Phase Temperature, TI-0101

Spray line temperature, TIA-0103 or TIA-0104 (use the lowest temperature if using main sprays)

Charging line temperature, TI-0212 (if using Auxiliary Spray)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR I PROCEDURE Page 84 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Reactor Vessel Upper Head voiding resulting from controlled PCS pressure reductions is not expected to result in safety functions being jeopardized.

C 82. COMMENCE depressurization of the PCS to 270 psia by performing ANY of the following:

a. OPERATE PZR heaters and Main or Auxiliary PZR sprays.

b. IE SI Pump throttling criteria are met, THEN PERFORM ANY of the following:

1) CONTROL Charging and Letdown.

2) THROTTLE HPSI flow.

C)= Continuously applicable step ft= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLAR PROCEDURE JPage 85 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

83. IF BOTH of the following conditions exist for each S/G:

At least three of four S/G pressure sigmas indicate between 510 and 550 psia (indicators between alarm flags)

A controlled cooldown is in progress THEN BLOCK MSIS for the S/G meeting the above conditions by performing ALL the following:

a. BLOCK MSIV closure signal for the applicable S/G by pushing the appropriate pushbutton on Control Panel C-01:

HS/LPE-50A ('A' S/G)

HS/LPE-50B ('B' S/G)

b. VERIFY "STEAM GEN VALVES ISOLATION LOCKOUT" (EK-0970) is alarmed.

c. ENSURE CLOSED BOTH Main Feed Reg Valves:

CV-0701 ('A' S/G)

CV-0703 ('B' S/G)

d. ENSURE CLOSED BOTH Bypass Feed Reg Valves:

CV-0735 ('A' S/G)

CV-0734 ('B' S/G)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 PROCEDURE JPage 86 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

84. IF ALL of the following conditions exist:

PZR pressure is less than 1687 psia

SIAS is NOT actuated or blocked

"Safety Injection Signal Block Permit" (EK-1369) is alarmed

A controlled cooldown and/or controlled depressurization is in progress, THEN BLOCK SIAS by performing ALL of the following:

a. PLACE AND HOLD SIAS block handswitch PB3-1 to BLOCK.

1) VERIFY the following annunciator in alarm:

"SAFETY INJ BLOCK RELAY SI-1" (EK-1 337)

2) RELEASE SIAS block handswitch PB3-1.

(continue) 0 = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 p

U PROCEDURE Page 87 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

84. (continued)

b. PLACE AND HOLD SIAS block handswitch PB3-2 to BLOCK.

1) VERIFY the following annunciators in alarm:

"SAFETY INJ BLOCK RELAY SI-2" (EK-1338)

"SAFETYINJ BLOCKED" (EK-1339)

2) RELEASE SIAS block handswitch PB3-2.

'=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 w EMERGENCY OPERATING Revision 16 PROCEDURE Page 88 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS C 85. MONITOR for formation of PCS voiding as indicated by ANY of the following:

Indicated Charging and Letdown flows do NOT correspond to PZR level trend.

PZR level rising significantly faster than trend expected from Auxiliary Spray flow.

Core AT (Average of Qualified CETs - Tc) or Loop AT (TH - Tc) rising for same secondary steaming and Auxiliary Feed rates.

Any operable PCS temperature indication is less than 25 0 F subcooled.

Operable RVLMS indicates voiding in the Reactor Vessel.

86. IE PCS voiding is indicated AND ANY of the following exist:

PCS pressure reduction is inhibited

PCS heat removal is inhibited

The Shift Supervisor directs void elimination, THEN PERFORM void elimination actions. Refer to EOP Supplement 26.

C)= Continuously applicable step) fA= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 X EMERGENCY OPERATING Revision 16 N N PROCEDURE JPage 89 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

87. IF ANY of the following AC or DC 87.1. IF Bus 1D and Bus 1E are NOT buses are NOT energized, energized, THEN RESTORE power to the THEN as resources permit, affected buses. Refer to the PROVIDE power to PZR Heaters following applicable procedure: from Bus 1C. Refer to ONP-2.1,

'Loss of AC Power," Attachment 1.

.- BUS -:-PROCEDURE--'

1Cor 1D EOP Supplement 29 1E with No SIAS EOP Supplement 29 1E with SIAS SOP-30 Y10 ONP-24.1, "Loss of Preferred AC Bus Y1 O" Y20 ONP-24.2, "Loss of Preferred AC Bus Y20" Y30 ONP-24.3, "Loss of Preferred AC Bus Y30" Y40 ONP-24.4, 'Loss of Preferred AC Bus Y40" Y01 ONP-24.5, floss of Instrument AC Bus Y01" Any DC Bus ONP-2.3, tLoss of

._ DC Power" O == Continuously applicable

= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 RPLAHT PROCEDURE Page 90 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

88. LF offsite power was lost AND offsite power is available, THEN RESTORE power to plant equipment by performing ALL of the following:

a. IF NONE of the following are energized:

'R' Bus

'F' Bus

Cook 1 Line, THEN INITIATE actions to restore power to 'F' or 'R' Bus, as available. Refer to EOP Supplement 21.

b. WHEN ANY of the following are energized:

'R' Bus

'F' Bus

Cook 1 Line, THEN INITIATE actions to restore Plant power. Refer to EOP Supplement 29.

(continue)

C)= Continuously applicable step Y>5=

I'= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 3 EMERGENCY OPERATING Revision 16 PROCEDURE Page 91 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

88. (continued)

c. RESTORE power to the affected bus(es). Refer to the following applicable procedure:

-'--BUS -_-l---PROCEDURE'-,

(Without SIS) EOP Supplement 29 (with SIS)

.1Aor ONP-2.1, "Loss of l~ Il AC Power"

d. RESTART plant equipment as desired.

0 == Continuously applicable

'= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

&EMERGENCY OPERATING Revision 16

_ PROCEDURE [Page 92 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Each D/G is limited to the following load rating:

2500 KW continuous

2750 KW two hours per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

89. WHEN 2400V Bus 1C or Bus 1D is 89.1. IF equipment needed to maintain energized, Safety Functions is available from IHEN as resources permit, a de-energized 2400V Vital Bus ENERGIZE Plant buses by AND a power supply is available, performing ALL of the following: THEN ENERGIZE the bus AND RESTORE the needed equipment.

a. IF Bus 1C is energized, THEN PERFORM ALL of the following:

1) ENSURE CLOSED the following breakers:

152-115 (Bus 1C to Transformers 11 and 19)

152-108(BuslCto Transformer 13)

(continue)

C) =

Continuously aDDlicable step) 't,

¶1'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR NAM PROCEDURE Page 93 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

89. (continued)

2) ENSURE 480V MCCs are energized as appropriate:

MCC 1: 52-1906 (Bus 19)

MCC3: 52-1301 (Bus 13)

MCC7: 52-1103 (Bus 11)

b. IF Bus 1D is energized, THEN PERFORM the following:

1) ENSURE CLOSED 152-201 (Bus 1D to Transformers 12 and 20)

2) ENSURE 480V MCCs energized as appropriate:

MCC 2: 52-2006 (Bus 20)

MCC8: 52-1201 (Bus 12)

(continue)

C) Continuously applicable

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 N PLN PROCEDURE IPage 94 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

89. (continued)

NOTE: IF only one MCC is available (MCC 1 or MCC 2),

THEN BOTH vital DC Buses should be powered from the two Battery Chargers supplied by the same energized MCC.

c. ENSURE CLOSED Battery Charger Feeder Breakers from available MCCs:

1) MCC 1

Charger No 1 Feeder 52-146

Charger No 4 Feeder 52-186

2) MCC 2

Charger No 2 Feeder 52-225

Charger No 3 Feeder 52-285

d. VERIFY 125V DC Buses D10 d.1. PLACE Battery Chargers in and D20 are powered by a operation. Refer to SOP-30, Battery Charger. 'Station Power."

C) = Continuously applicable step f>= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 N LANT PROCEDURE Page 95 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

90. IF ALL PCPs are stopped, 90.1. ENSURE proper control of S/G THEN VERIFY natural circulation feeding and steaming rates.

flow in at least one PCS loop by ALL of the following:

Core AT less than 500 F (Average of Qualified CETs minus Tc)

Loop THs and Loop Tcs constant or lowering

Average of Qualified CETs at least 250 F subcooled

Difference between Loop TH and Average of Qualified CETs is less than or equal to 150 F

91. WHEN PCP restart is desired, THEN RESTART desired PCPs.

Refer to EOP Supplement 3.

92. IF a plant cooldown is NOT in progress, THEN GO TO a TSC approved procedure.

C)= Continuously applicable step t,=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR PROCEDURE Page 96 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Failure of Instrument Air to containment will prevent venting the SITs.

93. JE PZR pressure is between 93.1. IF ANY SIT could NOT be isolated, 350 psia and 300 psia as read on THEN VENT the unisolated SIT PI-0104 (NR) or PR-0125 and using ONE of the following:

controlled AND a controlled cooldown is in a. VENT to containment as progress, follows:

THEN ISOLATE SITs as follows:

1) ENSURE CLOSED CWRT

a. UNLOCK AND CLOSE the Vent Isolation Valves:

following breakers:

CV-1 064 I

1BREAKER

- ---OUTLET-OUTLET

>

CV-1065

________ VALVE,"f 52-2129 MO.3041 T-82A 2) VENT each unisolated SIT 52-2329 MO-3045 T-82B one tank at a time by 52-2229 MO-3049 T-82C opening the Vent Valve and 52-2429 MO-3052 T-82D closing when tank is vented.

t-- -SIT l VENT.VALVE -l KEY: 190 I T-82A CV-3067

b. CLOSE the following SIT Outlet T-82B CV-3065 Valves: T-82C CV-3063

. T-82D CV-3051 BREAKER -OUTLET KEY

___-___ --- VALVE __-- _.

52-2129 MO-3041 98 52-2329 MO-3045 99 52-2229 MO-3049 100 52-2429 MO-3052 101 (continue) (continue)

C)= Continuously applicable step A~= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NULA LAN PROCEDURE JPage 97 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

93. (continued) (continued)

3) WHEN ALL the following conditions are met:

Unisolated SITs are vented and their associated vent valve closed

Plant conditions allow venting containment THEN OPEN CWRT Vent Isolation Valves:

0 CV-1 064 0 CV-1 065

b. VENT unisolated SITs Via Clean Waste Receiver Tank Header per SOP-3, "Safety Injection and Shutdown Cooling System."

©= Continuously applicable step ft= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 ICPJ PROCEDURE Page 98 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

94. IF a SIAS or CHR signal is actuated AND is no longer needed, THEN RESET the signal as follows:

a. IF SI Pump throttling criteria are satisfied AND Containment pressure is less than 3.0 psig, THEN RESET SIAS. Refer to SOP-3, "Safety Injection and Shutdown Cooling System,"

Attachment 4.

b. IE ALL operable Containment Area Radiation Monitors indicate less than 1 x 101 R/hr THEN RESET CHR by pushing BOTH left and right HIGH RADIATION RESET pushbuttons on C-13.

C)= Continuously applicable step) f5= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 PROCEDURE Page 99 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

95. IF ALL of the following conditions are met:

Tc is below 3250 F AND prior to Tcs less than 300° F

SI Pump throttling criteria are met

HPSI pumps are NOT required for inventory control

A cooldown is in progress, THEN DISABLE BOTH HPSI pumps by removing Control Power fuses and fuse holders from the following breakers:

152-207, HP Safety Injection Pump P-66A LOCATION: 'D' Bus

152-113, HP Safety Injection Pump P-66B LOCATION: 'C' Bus Q = Continuously applicable step) t,= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 PROCEDURE IPage 100 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

96. WHEN ALL of the following Shutdown Cooling System entry conditions are met:

PCS parameters are acceptable for existing Containment conditions:

Containmet -:Containment -

Containment

-- Greater Than or Less Than Equal To 1750 F

1750 FAQA . Greater' Less Than Than or Equal 3 psig at all To 3 psig at any times during time during-the Parameter e event event.

PCS Pressure Less Than REFER TO EOP 270 psia Supplement 1 PZR Level Greater Than Greater than (corrected) 36% and 40% and controlled controlled Avg of Qualified GreaterThan REFER TO EOP CETS 250 F Supplement 1 Subcooling Avg of Qualified Less Than REFER TO EOP ETsand Loop 3000 F Supplement I THs Temperature

TSC has determined that PCS activity is acceptable for circulation outside Containment.

Containment Spray Pumps are not in use for Containment Atmosphere safety function.

(continue)

(= Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 i EMERGENCY OPERATING Revision 16

_UCLEAR PROCEDURE Page 101 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

96. (continued)

Shutdown Cooling System monitoring equipment power is available from Y01 OR Alternate measures for loss of Y01 are established per ONP-17, "Loss of Shutdown Cooling."

LTOP is operable.

Power to the following Shutdown Cooling Return Valves is available:

0 MO-3015 (MCC-1) 0 MO-3016 (MCC-2)

OR Access to Containment is acceptable for manual valve operation, THEN GO TO GOP-9, 'Mode 32 525OF To Mode 4 or Mode 5" or TSC/PRC approved procedure.

End Of Section 4.0 0 == Continuously applicable step

= Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16

_UCLEAR u PROCEDURE Page 102 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEKEEPER EOP ENTRY TIME: TIME OF SIAS:_

STEP INSTRUCTIONS PAGE START DONE

4. Verify SIAS initiated 5

5. Ensure adequate Si flow and safeguards 6 equipment status

6. If PZR pressure lowers to less than 1300 psia 7 then establish one PCP per loop or if PCS subcooling is less than 250 F subcooled, then trip all PCPs

7. Ensure proper PCP configuration as PCS 7 temperature lowers

8. Verify operating limits for any running PCP 7

9. If open, then close CWRTs vent valves. 8

10. Isolate the LOCA 8

11. If the LOCA is outside of Containment, isolate 10 the leak and initiate CIS

12. Place Hydrogen Monitor in service 12

13. If the Containment has pressure greater than or 12 equal to 4.0 psig or has high radiation, ensure Containment Isolation signal initiated

14. If the Containment pressure is greater than or 13 equal to 4.0 psig, verify available Containment Spray Pumps running

15. If PCP seal cooling is lost, isolate seal leakoff 14 and restore PCP seal cooling

16. Secure Containment Spray 15 C)

17. Reset CHP 18 C = Continuously applicable step Hold Point A~= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 T PROCEDURE Page 103 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEKEEPER STEP INSTRUCTIONS PAGE START DONE

18. Verify condenser cooling or isolate steam to 20 condenser

19. If the LOCA is isolated, go to Step 64 20

20. Ensure at least one train of CR HVAC in 21 Emergency Mode.

21. Verify PCS boron concentration greater than or 21 C) equal to required boron concentration.

22. Commence steaming S/G(s) 23 l

23. When Main Steam pressure is between 510 and 25 550 psia, block MSIS

24. Record each occurrence of PZR spray with AT 26 © greater than 200°F

25. Verify Si Pump throttling criteria are satisfied 27 ©

26. Commence depressurizing the PCS to 270 psia 28 C)

27. When PZR pressure is less than 1687 psia and 29 SIAS is not actuated, BLOCK SIAS

28. If HPSI Pumps are operating and Si Pump 30 throttling criteria are satisfied, throttle HPSI flow or stop pumps

29. If LPSI Pumps are operating and PZR pressure 31 is being controlled greater than 200 psia, stop pumps and close valves

30. If PZR pressure lowers uncontrollably to less 31 than 200 psia and LPSI Pumps have been stopped, restart LPSI pumps and open valves

31. As resources permit, prepare post-RAS injection 32 _ l sources.

C)= Continuously applicable step) i= Hold fS= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 IEOLI PROCEDURE Page 104 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEKEEPER STEP INSTRUCTIONS PAGE START DONE

32. If Letdown is isolated and conditions allow, 32 restore Letdown

33. If SI Pump throttling criteria are met, then 33 maintain PZR level between 20% and 85%

(42% to 57% preferred)

34. Maintain PCS pressure within the limits of EOP 36 _

Supplement 1

35. Ensure at least one S/G has corrected level 37 C) being maintained or restored to between 60%

and 70%

36. Verify calculated cooldown rate does not 38 C) exceed Technical Specification limits and the cooldown is achievable with the existing PCS heat removal path

37. Monitor PCS for void formation 39 C)

38. If PCS voiding is indicated, perform void 39 elimination

39. If any vital AC or DC buses are not energized, 40 restore power to affected buses

40. If offsite power was lost and is available, restore 41 power to plant equipment

41. When 2400V Bus 1C or 1D is energized, then 43 energize Plant buses

42. Verify natural circulation flow in at least one 46 loop

43. Verify two phase natural circulation 46

44. Place LTOP in service 47 O = Continuously applicable step) A~=

t= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 N EMERGENCY OPERATING Revision 16 NUCLEAR A PROCEDURE IPage 105 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEKEEPER STEP INSTRUCTIONS PAGE START DONE

45. If desired, restart PCPs 47

46. When cold shutdown boron concentration is 48 established, swap Charging pump suction from the BASTs to the SIRWT

47. Verify Containment Sump level rises as the 48 © SIRWT level drops

48. When SIRWT level less than or equal to 25%, 49 then prior to RAS, perform Pre-RAS Actions.

49. If VC-1 0 or VC-1 1 trip on high temperature due 49 to low SW flow, reset and start VC-1 0 or VC-1 1

50. When Containment water level approaches Si 50 _

valve elevations, open and disable SI valves

. b..P. b..... ..

P. 1 RAS STEPS 51 to 56

51. When SIRWT level lowers to below 2% and 51 _

LOCA is inside Containment, then perform Post-RAS Actions.

52. IfContainment water level is less than 594' 1" 51 _

following a RAS, consult with the TSC for additional guidance

53. If RAS is initiated, ensure adequate HPSI pump 52 flow

54. Actions for when sump screen clogging is 53 © indicated.

55. Place ESS Room Sump Pumps in OFF and add 57 _

caution tag

56. If Charging Pump suction is aligned to the 57 SIRWT and RAS has initiated then, disable the Charging Pumps and add caution tag 0 = Continuously applicable step Al= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NUCLEAR PROCEDURE Page 106 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEKEEPER STEP INSTRUCTIONS PAGE START DONE

57. If Containment Area Radiation Monitors indicate 58 less than 1 x 10' R/hr and Containment pressure is less than 3.0 psig, reset CHR

58. If PZR pressure is between 350 psia and 59 300 psia and a cooldown is in progress, isolate SITs

59. If the elapsed time from the start of the LOCA is 61 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and SDC will not be inservice prior to 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months after the LOCA and any HPSI throttle criteria are not met, initiate hot leg injection

60. If Containment hydrogen concentration is 64 between 1% and 3%, place at least one Hydrogen Recombiner in service

61. Reset SIAS 64

62. If SDC entry conditions are met, go to GOP-9 65

63. If SDC entry conditions can not be established, 67 maintain long-term cooling b . . >

v. Isolated LOCA steps 64 to 96

64. If the LOCA is isolated, perform Steps 65 68 through 96

65. Verify SI Pump throttling criteria are satisfied 68 _

66. If HPSI Pumps are operating and SI Pump 70 throttling criteria are satisfied, throttle HPSI flow or stop pumps

67. If LPSI Pumps are operating and PZR pressure 71 is being controlled greater than 200 psia, stop pumps and close valves 0 = Continuously applicable step fA= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0

_ EMERGENCY OPERATING Revision 16 PROCEDURE Page 107 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEIKEEPER STEP INSTRUCTIONS PAGE START DONE

68. If PZR pressure lowers uncontrollably to less 71 than 200 psia and LPSI Pumps have been stopped, restart LPSI pumps and open valves

69. If Letdown is isolated and conditions allow, 72 restore Letdown

70. Verify the PCS is not in a water solid condition 72 _

71. If it is desired to draw a bubble in the PZR, 73 perform the actions to draw a bubble in the PZR

72. If Si Pump throttling criteria are met, maintain 74 corrected PZR level between 20% and 85%

using Charging, Letdown and HPSI

73. Maintain PCS pressure within the limits of EOP 75 _

Supplement 1

74. Ensure at least one S/G has corrected level 76 © being maintained or restored to between 60%

and 70%

75. Verify calculated cooldown rate does not 77 _

exceed Technical Specification limits and the cooldown is achievable with the existing PCS heat removal path

76. Evaluate the need for a plant cooldown 77 ___

77. Routing step if plant cooldown not required 77

78. Verify PCS boron concentration greater than or 78 © equal to cold shutdown boron concentration

79. Commence steaming S/G(s) 79 C)

80. When PZR Pressure and PCS cooldown within 82 limits, then place LTOP in service.

C)= Continuously applicable step A~= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 EMERGENCY OPERATING Revision 16 NUCLEARPLPROCEDURE Page 108 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEKEEPER STEP INSTRUCTIONS PAGE START DONE

81. Record each occurrence of PZR spray with AT 83 greater than 2000 F

82. Commence depressurizing the PCS to 270 psia 84

83. When Main Steam pressure is between 510 and 85 __ __ _ a 550 psia, block MSIS

84. When PZR pressure is less than 1687 psia and 86 .Q SIAS is not actuated, BLOCK SIAS

85. Monitor PCS for void formation 88

86. If PCS voiding is indicated, perform void 88 elimination

87. If any vital AC or DC buses are not energized, 89 Q restore power to affected buses

88. If offsite power was lost and is available, restore 90 power to plant equipment

89. When 2400V Bus 1C or 1D is energized, then 92 energize Plant buses

90. Verify natural circulation flow in at least one 95 loop

91. If desired, restart PCPs 95

92. Seek TSC guidance if plant cooldown not in 95 progress

93. If PZR pressure is between 350 psia and 96 300 psia and a cooldown is in progress, isolate SITs

94. Reset unnecessary safety actuation signals 98 0 = Continuously applicable step f-'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-4.0 E EMERGENCY OPERATING Revision 16 NEAR PROCEDURE I Page 109 of 109 TITLE: LOSS OF COOLANT ACCIDENT RECOVERY 5.0 PLACEKEEPER STEP INSTRUCTIONS PAGE START DONE

95. Disable both HPSI pumps when listed 99 conditions are met

96. When all shutdown cooling system entry 100 conditions are met, exit this procedure END OF SECTION 5.0 0 = Continuously applicable step

ATTACHMENT 3 EOP-6, -EXCESS STEAM DEMAND EVENT" 70 Pages Follow (Procedure Attachments not included)

PALISADES PALISADES NUCLEAR Proc No EOP-6.0 PLANT EMERGENCY Revision 14 UCPLN OPERATING PROCEDURE Issued Date 8/1 9/04 EXCESS STEAM DEMAND EVENT RLTucker / 8/1 9/04 Procedure Sponsor Date GGPalmisano / 1n/g/0 /n Technical Reviewer Date n Usemphr1 / 1 nRevirnD User Reviewer Date

PALISADES PALISADES NUCLEAR PLANT ProcNo EOP-6.0 EMERGENCY OPERATING Revision 14 uCLEA- rfi PROCEDURE Page 1 of 69 TITLE: EXCESS STEAM DEMAND EVENT USER ALERT CONTINUOUS USE PROCEDURE Read each step of the procedure prior to performing that step. When sign-offs are required, sign off each step as complete before proceeding to the next step.

1.0 PURPOSE This procedure provides operator actions which must be accomplished in the event of an Excess Steam Demand Event (ESDE). These actions are necessary to ensure that the Plant is placed in a safe, stable condition.

The goal of this procedure is to safely establish a plant condition that will allow the implementation of an appropriate existing procedure or a procedure provided by the Plant Technical Support Center for operation of the plant in hot shutdown or below.

End of Section 1.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 X EMERGENCY OPERATING Revision 14

_is PROCEDURE Page 2 of 69 TITLE: EXCESS STEAM DEMAND EVENT 2.0 ENTRY CONDITIONS

1. EOP 1.0, "Standard Post Trip Actions," has been performed.

OR The event initiated from a lower mode when the Shutdown Cooling System is NOT initially in service.

2. Plant conditions indicate an Excess Steam Demand Event has occurred.

ANY of the following may be present:

a. Loud noise indicative of a high energy steam line break.

b. Lowering PCS TAvE.

c. Steam flow/feed flow mismatch.

d. Rise in feedwater flow.

e. Possible rise in Containment temperature, humidity, and Containment Sump level, with no significant radiation level increase on Containment Hi Range radiation monitors (Containment Area Monitors may fail high due to high temperature and humidity conditions).

f. Low pressure in affected S/G(s) following MSIV closure.

g. Possible rise in reactor power.

End of Section 2.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 PROCEDURE Page 3 of 69 TITLE: EXCESS STEAM DEMAND EVENT 3.0 EXIT CONDITIONS

1. The diagnosis of an Excess Steam Demand Event is NOT confirmed.

2. ANY of the Safety Function Status Check Sheet acceptance criteria are NOT satisfied AND corrective actions to restore the safety function are NOT effective.

OR

3. The Excess Steam Demand Event procedure has accomplished its purpose by satisfying ALL of the following:

a. All Safety Function Status Check acceptance criteria are being satisfied.

b. Shutdown Cooling Entry conditions are satisfied or a cooldown is NOT required and maintaining the plant in Hot Shutdown condition is desired.

c. An appropriate, approved procedure to implement exists or has been approved by the plant Technical Support Center.

End of Section 3.0

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 j EMERGENCY OPERATING Revision 14 EOws PROCEDURE Page 4 of 69 TITLE: EXCESS STEAM DEMAND EVENT 4.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS CAUTION During degraded Containment conditions, the operator should not rely on any single instrument indication due to large instrument errors. Alternate/additional instrumentation should be used to confirm trending of PCS conditions.

C 1. CONFIRM proper event diagnosis 1.1. GO TO ONE of the following:

by performing ALL of the following:

EOP-1.0, "Standard Post Trip

a. VERIFY Attachment 1, "Safety Actions," Attachment 1, "Event Function Status Check Sheet' Diagnostic Flowchart" AND acceptance criteria: RE-DIAGNOSE the event.

1) Are satisfied at intervals of

For events initiated from a lower approximately fifteen mode, GO TO the EOP minutes. considered appropriate by the Shift Supervisor.

EOP-9.0, "Functional Recovery

2) Corrective actions to restore Procedure."

Attachment 1, "Safety Function Status Check Sheet," acceptance criteria are effective.

(continue)

C)=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 N EMERGENCY OPERATING Revision 14 NUCLEAR ANT PROCEDURE Page 5 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

1. (continued)

b. JI ALL of the following conditions exist:

Steam Generator Blowdown Monitor, RIA-0707, has NOT alarmed

SIAS has NOT occurred OR has been reset

CHP and CHR signals are NOT present, THEN SAMPLE S/Gs for activity and Lithium AND VERIFY sample results do NOT indicate a SGTR.

c. Observation of NO abnormal S/G level rise (NOT attributable to feed flow or swell).

3. OPEN the placekeeper AND RECORD the time of EOP entry.

4. IF PZR pressure is less than or 4.1. PUSH BOTH left and right equal to 1605 psia INJECTION INITIATE pushbuttons ORl Containment pressure is on EC-13.

greater than or equal to 4.0 psig, THEN VERIFY "SAFETY INJ

PB1-1 INITIATED" (EK-1342) is alarmed.

PB1-2 C)= Continuously applicable step t,= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 PROCEDURE Page 6 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

5. IF SIAS is present, THEN PERFORM ALL of the following:

a. ENSURE available safeguards equipment operated or operating. Refer to EOP Supplement 5.

b. VERIFY at least minimum SI b.1. IF SI flow is NOT within the limits of flow. Refer to EOP EOP Supplement 4, Supplement 4. THEN PERFORM ANY of the following to restore SI flow:

1) ENSURE electrical power available to SI pumps and valves.

2) ENSURE correct SI valve lineup.

3) ENSURE adequate SI pump seal cooling.

4) START additional SI pumps as needed until SI flow is within the limits of EOP Supplement 4.

c. IF Letdown Orifice Stop Valves are closed, THEN PLACE handswitches in the CLOSE position:

HS-2003 0 HS-2004 HS-2005 C = Continuously applicable step '(= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 N PROCEDURE FPage 7 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Failure to close MSIV and MSIV bypass valves on the unaffected S/G will result in steaming the unaffected S/G through the break.

6. ENSURE MSIVs and MSIV Bypass Valves are closed:

SIG VALVE: DESCRIPTION-.

CV-0510 MSIV

'A' MO-0510 MSIV BYPASS CV-0501 MSIV

.___ MO-0501 MSIV BYPASS NOTE: P-50A and P-50B shall not be operated simultaneously when Tc is less than 3000F.

7. IE PZR pressure lowers to less than 1300 psia AND SIAS is initiated, THEN PERFORM BOTH of the following:

a. ENSURE one PCP is stopped in each loop.

b. IF PCS is less than 250 F subcooled, THEN ENSURE ALL PCPs stopped.

0 = Continuously applicable step tf= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 w EMERGENCY OPERATING Revision 14 NUCLEAR PU PROCEDURE Page 8 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

8. COMMENCE emergency boration to establish PCS boron concentration greater than or equal to the boron concentration needed for TAVE greater than 5250 F as verified by sample or hand calculation. Refer to EOP Supplement 35.

a. WHEN PCS boron concentration is greater than or equal to the required boron concentration, THEN emergency boration may be secured. REFER TO EOP Supplement 40.

9. WHEN PCS temperature lowers, THEN ENSURE PCPs configured as follows:

.IVIMAXIMUMI-V PCS Tc OPERATING PCPs

<450'F 3

<300'F 2

10. IF PCPs are operating, 10.1. STOP PCPs which do NOT satisfy THEN VERIFY PCP operating PCP operating limits.

limits are satisfied. Refer to EOP Supplement 1.

0 = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14

_ 2-o PROCEDURE [Page 9 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

11. VERIFY BOTH of the following: 11.1. ENSURE CLOSED BOTH MSIVs:

At least one Cooling Tower

CV-0510 ('A' S/G)

Pump operating

CV-0501 ('B' S/G) o P-39A 11.2. ENSURE CLOSED from the Control o P-39B Room BOTH MSIV Bypass valves:

At least one Condensate Pump

MO-0510 ('A' S/G) operating

MO-0501 ('B' S/G) o P-2A a. IF ANY MSIV Bypass valves o P-2B were open when power/position indication was lost, THEN LOCALLY CLOSE ANY open MSIV Bypass valve.

b. ENSURE CLOSED ALL S/G Blowdown Valves:

1.-- IG; A9 '.- --- I -S/G - -

CV-0739 CV-0738 CV-0771 CV-0770 CV-0767 CV-0768 0 = Continuouslv aD~licable steD H d Point ft= Hold

- - Cn o -I-*Ia-- b- - --

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 PROCEDURE Page 10 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Each D/G is limited to a 2500 KW continuous load rating and a 2750 KW two-hour load rating. Operation of VC-10 (VC-1 1) will draw approximately 44 KW.

12. ENSURE at least one train of CR HVAC in Emergency Mode. Refer to SOP-24, "Ventilation and Air Conditioning System."

High steam flow from S/G

Lowering S/G pressure

Lowering S/G level

Lowering Loop Tc temperature 0 =

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 8 EMERGENCY OPERATING Revision 14 NUCLEARPLANT PROCEDURE Page 11 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Maintenance of heat removal via the least affected S/G during dual events (SGTR/SGTR, ESD/ESD, or SGTR/ESD combinations) is preferable to isolation of both S/Gs and going to once-through-cooling.

14. IF MSIS has NOT isolated the leak, THEN ISOLATE the most affected steam generator. Refer to the following applicable EOP supplement:

EOP Supplement 17 ('A' S/G)

EOP Supplement 18 ('B' S/G)

= Continuously applicable stepH fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEA I PROCEDURE Page 12 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

15. VERIFY the correct S/G is isolated 15.1. IF the wrong S/G was isolated, by comparing ALL of the following: THEN PERFORM ALL of the following on the least affected S/G:

S/G pressures

a. OPEN the Atmospheric Steam

S/G levels Dump Valve air supply valves and manual isolation valves.

PCS Loop Tc temperatures Refer to the following applicable EOP Supplement:

EOP Supplement 17

('A' S/G)

EOP Supplement 18

('B' S/G)

b. ESTABLISH Auxiliary Feedwater flow through ANY associated AFW valve:

'A SIG :-.:.-l 'B'SiG-CV-0737A CV-0736A CV-0749 CV-0727 15.2. GO TO Step 14 to isolate the affected S/G.

0 = Continuously applicable step A= Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 PROCEDURE Page 13 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS CAUTION When ALL PCPs are stopped, steaming the least affected S/G must occur prior to dryout of the most affected S/G to prevent lifting PZR Code Safety Valves or Pressurized Thermal Shock rupture of the PCS.

a. MAINTAIN level in the least affected S/G between 60% and 70%.

b. IF the steam leak is isolated, THEN ESTABLISH steam flow from BOTH S/Gs using the Atmospheric Steam Dump Valves.

(continue) 0 =

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 8 EMERGENCY OPERATING Revision 14 NUCLEAR A PROCEDURE Page 14 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

16. (continued)

WARNING IF Containment pressure is higher than the most affected S/G pressure AND the ESDE is inside of containment, THEN opening of the ASDVs on the most affected S/G will provide a direct release path to the environment.

NOTE: Steaming BOTH S/Gs using ASDVs is permitted prior to isolation of the most affected S/G if necessary to control temperature /pressure of the least affected S/G.

c. IF the steam leak is NOT isolated, THEN STEAM the least affected S/G as necessary to maintain the following, as applicable:

WHEN Tcs in the affected loop are lowering, THEN MAINTAIN the least affected S/G pressure within 50 psid above the most affected S/G pressure

WHEN Tcs in the affected loop are NOT lowering, THEN STABILIZE PCS Tcs using the least affected SIG

©= Continuously applicable step f,= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR PROCEDURE Page 15 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Use ANY of the following to determine Average of Qualified CETs:

PPC point 'KCETA" (Average of Qualified CETs)

PPC Incore Qualified CET Map (PPC page 313)

Manual calculation. Refer to SOP-34, "Plant Process Computer (PPC) System."

© 17. VERIFY SI Pump throttling criteria 17.1. IF ANY of the SI Pump throttling are satisfied by ALL of the criteria can NOT be maintained, following: THEN RAISE HPSI flow AND START HPSI Pumps as necessary.

a. Based on the Average of Qualified CETs, PCS PM lI - - VALVE-A subcooling meets ONE of the NUMBER DESCRIPTION following: .Train 1 -

At least 25 0 F subcooled for MO-3009 HPSI Train 1 to Loop IB non-degraded Containment P-66B MO-3011 HPSI Train 1 to Loop 2A conditions MO-3007 HPSI Train I to Loop 1A MO-3013 HPSI Train I to Loop 2A

Greater than the minimum -Train 2 subcooling curve on EOP MO-3066 j HPSI Train 2 to Loop 1B Supplement 1 for degraded Containment conditions MO-3064 HPSI Train 2 to Loop 2A MO-3068 HPSI Train 2 to Loop 1A

b. Corrected PZR level is greater MO-3062 HPSI Train 2 to Loop 2B than 20% (40% for degraded Containment) and controlled.

REFER TO EOP Supplements 9 and 10.

(continue) 0 = Continuously applicable step A_= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR MPLAN PROCEDURE J Page 16 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

17. (continued)

c. At least one S/G is available for PCS heat removal with corrected level being maintained or being restored to between 60% and 70%.

REFER TO EOP Supplement 11.

d. Operable RVLMS channels indicate greater than 102 inches above the bottom of fuel alignment plate (621' 8").

18. IF HPSI Pumps are operating AND SI Pump throttling criteria are satisfied, THEN THROTTLE HPSI flow OB STOP one HPSI Pump at a time.

PUMP I NUMBER l VALVE DESCRIPTION >

.Train -

MO-3009 HPSI Train 1 to Loop 1B P-66B MO-3011 HPSI Train 1 to Loop 2A MO-3007 HPSI Train 1 to Loop 1A MO-30130 HPSI Train 1 to Loop 2B Train 2 --

1 MO-3066 H PSI Train 2 to Loop 1B I MO-3064 HPSI Train 2 to Loop 2A MO-3068 HPSI Train 2 to Loop 1A MO-3062 HPSI Train 2 to Loop 2B C) = Continuously applicable step t,= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 3 EMERGENCY OPERATING Revision 14 NUCLE PLAT PROCEDURE Page 17 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

19. IE LPSI Pumps are operating AND PZR pressure is being controlled greater than 200 psia, THEN PERFORM BOTH of the following:

a. STOP the operating LPSI Pumps:

P-67A

P-67B

b. CLOSE the LPSI injection valves:

MO-3008 LPSI Loop 1A

MO-3010 LPSI Loop 1B

MO-3012 LPSI Loop 2A

MO-3014 LPSI Loop 2B

20. IF PZR pressure lowers to less than 200 psia AND LPSI pumps have been stopped, THEN PERFORM BOTH of the following:

a. ENSURE OPERATING ALL available LPSI pumps:

P-67A

P-67B

b. ENSURE OPEN LPSI injection valves:

MO-3008 LPSI Loop 1A

MO-3010 LPSI Loop 1B

MO-3012 LPSI Loop 2A

MO-3014 LPSI Loop 2B 0 = Continuously applicable step

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 tC2RPLJ PROCEDURE Page 18 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Failure to maintain greater than 100 gpm AFW flow to at least one S/G will result in an automatic start of the next available AFW pump if the pump controls are in Auto.

C 21. ENSURE the least affected S/G has corrected level being maintained or being restored to between 60% and 70%. Refer to EOP Supplement 11.

NOTE: Use the following instruments to determine spray nozzle AT:

PZR Vapor Phase Temperature, TI-0101

Spray line temperature, TIA-0103 or TIA-0104 (use the lowest temperature if using main sprays)

Charging line temperature, TI-0212 (if using Auxiliary Spray)

0 = Continuously applicable step A'= Hold Point Hold Point

PAUSADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 A PROCEDURE LPage 19 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

© 23. MAINTAIN PCS pressure within the 23.1. IF the PCS is oversubcooled limits of EOP Supplement 1 by OR PZR pressure is greater than performing ANY of the following: the maximum limits of EOP Supplement 1,

a. CONTROL the following: THEN PERFORM ANY of the following to restore subcooling or 0 PZR heaters PCS pressure to within the 0 Main Spray appropriate limit:

S Auxiliary Spray (Supplement 37) a. OPERATE available S/G(s) to stop the cooldown

b. IF SI Pump throttling criteria are AND STABILIZE Qualified CET met, temperatures and Loop TCs.

THEN CONTROL HPSI, Charging, and Letdown flows. b. OPERATE the following to lower PZR pressure within allowable limits:

0 Main Spray 0

Auxiliary Spray (Supplement 37)

c. IE SI Pump throttling criteria are met, THEN CONTROL HPSI, Charging, and Letdown flows.

(continue) (continue) 0 = Continuously applicable step Hold Point f-= Hold

(= Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NEOPJ PROCEDURE Page 20 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

23. (continued) (continued)

d. IF ALL of the following conditions are met:

Above actions to lower PCS pressure are NOT effective

PORVs are required to open to reduce PCS pressure

PZR level is less than 85%

THEN PERFORM BOTH of the following:

1) OPEN PORV Isolation Valves:

0 MO-1 042A 0 MO-1 043A CAUTION Rupture of the Quench Tank rupture disk is likely during any sustained opening of PORVs. This would result in rising Containment atmosphere temperature and pressure. Quench Tank temperature and pressure should be monitored during PORV operation.

2) CYCLE the PORVs as necessary to maintain BOTH of the following:

(continue) (continue)

C)== Continuously applicable step

= Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 PROCEDURE Page 21 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

23. (continued) (continued)

PZR corrected level less than 85% (REFER TO EOP Supplements 9 and 10)

PZR pressure within the limits of EOP Supplement 1.

3) IF ALL of the following PORV closing criteria are met:

PZR pressure is less than 2100 psia

PZR pressure is less than the maximum limits of EOP Supplement 1

PORVs are NOT required open to reduce PZR pressure, THEN CLOSE the PORVs:

PRV-1042B

PRV-1043B

4) IF the PORV closing criteria are met AND either PORV will NOT close, THEN CLOSE associated PORV Isolation Valve:

MO-1 042A

MO-1 043A (continue) (continue)

C = Continuously applicable step A~= Hold Point

= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 en EMERGENCY OPERATING Revision 14 PROCEDURE Page 22 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

23. (continued) (continued)

5) ENSURE started the following containment cooling fans:

a) ALL available Containment Air Cooler 'A' fans for ALL available Containment Air Coolers.

b) IF SIAS not present, THEN ALL available Containment Air Cooler 'B' fans for ALL available Containment Air Coolers.

6) IE ANY of the following conditions exist:

Containment pressure is greater than or equal to 4.0 psig.

Any operable CONTAINMENT Radiation Monitor rises to 1 x 101 Rthr, THEN PERFORM ALL of the following:

(continue) (continue)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 PROCEDURE Page 23 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

23. (continued) (continued) a) VERIFY CIS INITIATED" (EK-1 126) is alarmed MANUALLY INITIATE CIS by pushing left or right HIGH RADIATION INITIATE pushbuttons on EC-1 3:

CHRL-CS

CHRR-CS b) VERIFY Containment Isolation. Refer to EOP Supplement 6.

7) IE the Pressure Control safety function is still in jeopardy, THEN GO TO EOP-9.0.

23.2. IF PCS cooldown rate exceeds Technical Specification limits, THEN PERFORM ANY of the following to restore the cooldown rate to within Technical Specification limits:

a. OPERATE available S/G(s) to stop the cooldown AND STABILIZE Qualified CET temperatures and Loop Tcs.

(continue) (continue)

C = Continuously applicable step > A= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 EAR PROCEDURE Page 24 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

23. (continued) (continued)

b. OPERATE the following to maintain PZR pressure within limits of EOP Supplement 1:

PZR heaters

Main Spray

Auxiliary Spray (Supplement 37)

Letdown

c. As directed by the Shift Supervisor, CONTINUE the PCS cooldown at less than or equal to Technical Specification limits.

Refer to EOP Supplement 33.

24. PLACE at least one Hydrogen Monitor in operation, ensuring the appropriate Key Switch in the "ACCI" position. Refer to SOP-38, "Gaseous Process Monitoring System."

C) = Continuously applicable step

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 RULAR PROCEDURE Page 25 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

25. IF ANY of the following conditions exist:

Containment pressure is greater than or equal to 4.0 psig

Any operable Containment Radiation Monitor rises to 1 x 10' R/hr, THEN PERFORM ALL of the following:

a. VERIFY "CIS INITIATED" a.1. MANUALLY INITIATE CIS by (EK-1 126) is alarmed. pushing left or right HIGH RADIATION INITIATE pushbutton on EC-13.

CHRL-CS

CHRR-CS

b. VERIFY Containment Isolation. b.1. CLOSE valves that failed to Refer to EOP Supplement 6. automatically operate.

C)= Continuously applicable step G'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14

_ PROCEDURE [Page 26 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

26. IF Containment pressure is greater than or equal to 4.0 psig, THEN PERFORM ALL of the following:

a. VERIFY Containment Spray a.1. OPEN available Containment Spray alignment valves to obtain required AND at least minimal configuration and at least minimum acceptable spray flow per flow.

following table:

CV-3001

-NUMBER - i

CV-3002 OF - NUMBEROF -- CS FLOW.<:-l RUNNING. 1' OPEN CS .MUST BE AT. AND CS PUMPS :.VALVES LEAST:.

START available Containment

-RAS NOT Present Spray pumps 1 at least 1 2185 gpm total 0 P-54A 22 2939 gpm total P-54B 0

RAS Present P-54C 1 l 1 l 1540gpm 2 or 3 _ _2 l 3113 gpm total

b. ENSURE at least one Containment Air Cooler Accident Fan operating.

V-1A

V-2A

V-3A

V-4A C=

t'= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NEUCLFAR P"WPROCEDURE Page 27 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

27. IF Containment pressure rises to greater than or equal to 35 psia AND CCW Containment Isolation Valves were opened, THEN PLACE the following CCW Containment Isolation Valve

[ keyswitches to CLOSE:

CCW Valve 1-- Keyswitch CV-0910 CV-0911 HS-0910 HS-0911

- -1':Keyv]

337 338 CV-0940 HS-0940 336 CAUTION Operation of PCPs should be minimized when seal cooling is NOT present or controlled bleedoff is isolated.

28. IF PCP seal cooling is unavailable, THEN PERFORM ALL of the following:

a. CLOSE PCP Controlled Bleedoff valves:

CV-2083

CV-2099

b. CLOSE PCP Controlled Bleedoff Relief Stop, CV-2191.

c. RESTORE PCP seal cooling.

Refer to ONP-6.2, "Loss of Component Cooling."

C)=

=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 PROCEDURE _Page 28 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

a. INITIATE actions to makeup to the SIRWT. Refer to ONE of the following:

SOP-2A, "Chemical &

Volume Control System Charging & LetdownN

SOP-1 7A, "Clean Radioactive Waste System"

b. IF CIS INITIATED" (EK-1126) is clear, THEN MANUALLY INITIATE CIS by pushing left or right HIGH RADIATION INITIATE pushbuttons on EC-13.

30. WHEN SIRWT level less than or equal to 25%,

THEN prior to RAS, PERFORM Pre-RAS Actions. Refer to EOP Supplement 42.

0 = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR-PIPROCEDURE Page 29 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Premature initiation of RAS can lead to insufficient Containment Sump inventory for Si Pump operation. Minimum Containment Water level of 594' 1 is necessary for adequate ESS pump NPSH.

31. WHEN SIRWT level lowers to below 2%,

THEN PERFORM Post-RAS Actions. Refer to EOP Supplement 42.

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 INEUCLPLAN IPROCEDURE JPage 30 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

32. IF Charging Pump suction is aligned to the SIRWT AND RAS has initiated, THEN PERFORM ALL of the following:

a. STOP ALL Charging Pumps:

P-55A 0

P-55B P-55C

b. RACK OUT ALL Charging Pump breakers:

CHARGING - ; -R:E -

PUM ;`:BREAKER"'

P-55A 52-1205 P-55B52-1 308 P-55B 52-1206 P-55C 52-1105

c. PLACE a Caution Tag on their handswitches that reads "Do NOT Use - No suction source available 0

52-1 205CS S0 52-1 206CS 52-11 05CS O = Continuously applicable step 0= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NUCLEAR PROCEDURE Page 31 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

33. WHEN Containment pressure is less than 3.0 psig, AND CHP has initiated, THEN PERFORM ALL of the following:

a. IF CV-3001, Containment Spray Valve, is open, THEN PLACE HS-3001A to the OPEN position.

b. IF CV-3002, Containment Spray Valve, is open, THEN PLACE HS-3002A to the OPEN position.

c. IF MFW or Condensate pumps are operating AND feedwater from these sources is NOT desired, THEN PLACE ALL of the following controllers in MANUAL AND CLOSE:

1) Feedwater Regulating Valves

LIC-0701 ('A' S/G)

LIC-0703 ('B' S/G)

2) Feedwater Regulating Bypass Valves

LIC-0735 ('A' S/G)

LIC-0734 ('B' S/G)

(continue)

C)= Continuousiv aDplicable_ step f5= H Point Hold P

_ Cl I*I

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 T PROCEDURE Page 32 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

33. (continued)

d. IF CCW to containment has NOT been restored, THEN PLACE the following CCW valve keyswitches to CLOSE:

lValve Keyswitch Key CV-0910 HS-0910 337 CV-0911 HS-0911 338 lCV-0940 HS-0940 336 NOTE: Automatic reinitiation of spray will not occur until after SIAS has been reset.

e. RESET CHP circuits by pushing left and right HIGH PRESSURE RESET pushbuttons on C-13 0

CHPL - Reset 0

CHPR - Reset

Continuously applicable step 0)

= Point Hold Point

PALISADES PALISADES NUCLEAR PLANT ProcNo EOP-6.0 N EMERGENCY OPERATING Revision 14 PROCEDURE Page 33 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Continued operation of the sprays after pressure has been reduced to an acceptable level increases the possibility of wetting electrical connectors which may result in electrical grounds, shorts and other malfunctions.

34. IF the Containment Spray System is operating, AND ALL of the following conditions are satisfied:

l,Parameter. Condition Containment less than 3 psig pressure NOT required for CTMT ambient cooling NOT required for HPSI subcooling NOTE: These conditions must be met prior to securing the last Containment Spray pump.

Containment NOT needed for iodine removal Spray as determined by Chemistry operation OR ALL of the following:

Containment high range Gamma monitors read less than 1800 R/Hr

Containment isolated per EOP Supplement 6

less than one hour has l________ elapsed since reactor trip (continue)

C = Continuously applicable step 0t= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 N PROCEDURE (Page 34 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

34. (continued)

THEN Containment Spray Pumps may be secured by performing the following:

NOTE: Securing spray pumps one at a time and waiting a short period to see the effect of reduced sprays will aid in the determination of the need for continued spray.

a. IF three Containment Spray Pumps are operating, THEN STOP one Containment Spray Pump as directed by the Shift Supervisor.

b. IF two Containment Spray Pumps are operating, THEN PERFORM the following as directed by the Shift Supervisor:

1) CLOSE one Containment Spray Valve.

CV-3001

CV-3002

2) STOP one Containment Spray Pump.

c. IF one Containment Spray Pump is operating, THEN STOP the Containment Spray Pump as directed by the Shift Supervisor.

(continue)

C) = Continuously applicable step 'M= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NUCLEARPROCEDURE Page 35 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

34. (continued)

d. WHEN ALL Containment Spray Pumps have been stopped, THEN ENSURE CLOSED BOTH Containment Spray Valves.

CV-3001

CV-3002

e. IF CHP has been reset, THEN ENSURE both Containment Spray Valve CHP Bypass Keyswitches are in NORMAL:

HS-3001C

HS-3002C

35. IF ALL operable Containment Area Radiation Monitors indicate less than 1 x 101 R/hr AND Containment pressure is less than 3.0 psig, THEN RESET CHR by pushing the following:

The RESET pushbutton on each Containment Area Radiation Monitor.

BOTH left and right HIGH RADIATION RESET pushbuttons on C-13.

C = Continuously applicable step l t= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR PROCEDURE Page 36 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Subsequent to the actions in Step 36, the TSC must approve closure of ANY of the failed open valves.

36. WHEN Containment water level approaches the level specified below, THEN ENSURE OPEN the following valves ANM OPEN associated breakers:

Cntmt - Valve ,

Water Level. Number l Bkro

Description:

____ ;- MCC No.1 MO-3008 52.141 LPSI Loop 1A MO-3010152-147l LPSI Loop 1B

.-> 9 MCC No. 2 MO-3012 52-2471 LPSI Loop2A MO-3014 52-251i LPSI Loop 2B

-_ _ MOO C-No. 1 MO-3009 52-197 HPSI Train 1 to Loop 1B MO-3011 52-157 HPSI Train 1 to Loop 2A MO-3007 52-137 HPSI Train 1 to Loop 1A MO-3013 52-151 HPSI Train 1 to Loop 2B 596'4" .- -MCCNo.2 MO-3066 52-257 HPSI Train 2 to Loop 1B MO-3064 52-237 HPSI Train 2 to Loop 2A MO-3068 52-261 HPSI Train 2to Loop 1A MO-3062 52-241 HPSI Train 2 to Loop 2B O= Continuously applicable step 16= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NUCLEAR PLNT PROCEDURE [Page 37 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

37. IE Letdown is isolated AND BOTH of the following conditions exist:

Si Pump throttling criteria are met

Letdown is needed or desired, THEN RESTORE Letdown. Refer to EOP Supplement 27.

38. IF ANY of the following criteria are met:

PCS boron concentration is at the required shutdown boron concentration based on sample or hand calculation. REFER TO EOP Supplement 35.

"CONCENTRATED BORIC ACID TANK LO-LO LEVEL" (EK-0716 and EK-0722) are alarmed.

THEN ALIGN the Charging Pump suction to the VCT (if Letdown is in service) or SIRWT as directed by the Shift Supervisor. Refer to EOP Supplement 40.

0 = Continuously applicable step fl= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0

_ EMERGENCY OPERATING Revision 14

-Eoj PROCEDURE Page 38 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

© 39. VERIFY the PCS is NOT in a water 39.1. IF water solid PCS condition is solid condition as indicated by indicated, BOTH of the following: THEN MAINTAIN the PCS within the limits of EOP Supplement 1 by

a. No exaggerated or severe ANY of the following:

pressure response to PCS inventory or temperature a. OPERATE available S/G(s) to changes. control the cooldown AND STABILIZE Qualified CET

b. ANY of the following: temperatures and Loop Tcs.

Corrected PZR level is less b. IF SI Pump throttling criteria are than 100%. REFER TO met, EOP Supplements 9 and 10 THEN CONTROL HPSI, Charging, and Letdown flows.

RVLMS indicates voiding

40. IF it is desired to draw a bubble in the PZR, THEN PERFORM ALL of the following:

a. ENSURE ENERGIZED ALL available PZR heaters.

b. IF ANY of the following conditions exist:

Both S/G pressures can be maintained below the existing PCS pressure

At least one PCP is operating THEN PERFORM ALL of the following to reduce PCS pressure:

(continue) 0 = Continuously applicable step ty= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 LEA PL PROCEDURE J Page 39 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

40. (continued)

1) IF SI Pump throttling criteria are met, THEN CONTROL Charging, Letdown, and HPSI flow.

2) INITIATE PCS cooldown within Technical Specification limits.

3) MONITOR the PCS cooldown rate using PPC.

Refer to EOP Supplement 33.

4) MAINTAIN PCS temperature and pressure within the limits of EOP Supplement 1.

5) MAINTAIN 250 F subcooling.

c. IE a bubble forms in the Reactor Vessel Upper Head region, THEN PERFORM BOTH of the following:

1) CONTROL Charging, Letdown, and HPSI flow to maintain PCS level greater than the 102 inches above the bottom of fuel alignment plate (621' 8").

2) CONTINUE efforts to draw a bubble in the PZR.

C = Continuously applicable step > = Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR I PROCEDURE Page 40 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS NOTE: PZR level instrument de-calibration occurs due to PCS pressure and containment temperature changes. Level correction is per EOP Supplements 9 and 10.

NOTE: IF the PCS is in a water solid condition for PCS Pressure Control, THEN the PZR level limit of 85% may be exceeded.

NOTE: PZR level should be maintained greater than 36% (40% for degraded Containment) to have continued availability of PZR Heaters.

41. IF SI Pump throttling criteria are met, THEN MAINTAIN corrected PZR level between 20% and 85% (42%

to 57% preferred) by performing ANY of the following:

a. THROTTLE HPSI flow.

b. CONTROL Charging and Letdown.

(continue)

Q)= Continuously applicable step fA= Hold Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NUCLEAR A PROCEDURE Page 41 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

41. (continued)

NOTE: IFan interruption in boration via Charging Pump to HPSI Train 2 occurs, THEN a different SI cold leg injection nozzle should be used when restoring flow.

1) ENSURE normal charging 1.1) IF the normal charging path is NOT path aligned as follows: available AND HPSI Train 2 is available, a) OPEN Charging Line THEN CHARGE to the PCS via the Stop Valve, CV-21 11. HPSI header by performing ALL of the following:

b) OPEN at least one Charging Stop Valve: 1) STOP ALL Charging Pumps.

CV-2113 2) CLOSE Charging Line Stop

CV-2115 Valve, CV-211 1.

c) IF BOTH Charging Stop 3) CLOSE Letdown Orifice Stop Valves fail to open THEN Valves:

ENSURE greater than 33 gpm flow through

CV-2003 CK-CVC21 12.

CV-2004

CV-2005

4) CLOSE Letdown Containment Isolation Valve CV-2009.

5) ENSURE CLOSED HPSI Pump B Discharge to Train 2, CV-3018.

(continue) (continue)

C = Continuously applicable step f-TV= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 t EMERGENCY OPERATING Revision 14 NUCLEART- PROCEDURE JPage 42 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

41. (continued) (continued)

6) OPEN ONE HPSI Train 2 Injection Valve:

0 MO-3062 MO-3064 MO-3066 MO-3068

7) PLACE SIT Pressure Indicating Controller associated with valve opened above to MANUAL AND CLOSE:

0 PIC-0338, MO-3062 a PIC-0347, MO-3064 a PIC-0346, MO-3066 a PIC-0342, MO-3068

8) OPEN Charging Pump Discharge to Train 2, MO-3072.

9) START Charging pumps as necessary to control PZR level.

C = Continuously applicable step > A= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14

_EO- PROCEDURE Page 43 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

42. IE ANY of the following AC or DC 42.1. IF Bus 1D and Bus 1E are NOT buses are NOT energized, energized, THEN RESTORE power to the THEN as resources permit, affected buses. Refer to the PROVIDE power to PZR Heaters following applicable procedure: from Bus 1C. Refer to ONP-2.1, "Loss of AC Power," Attachment 1.

BUS PROCEDURE; 1C or 10 EOP Supplement 29 1E with No SIAS EOP Supplement 29 1E with SIAS SOP-30 Y10 ONP-24.1, "Loss of Preferred AC Bus Y1O" Y20 ONP-24.2, 'Loss of Preferred AC Bus Y20" Y30 ONP-24.3, 'Loss of Preferred AC Bus Y30" Y40 ONP-24.4, "Loss of Preferred AC Bus Y40" Y01 ONP-24.5, 'Loss of Instrument AC Bus Y01" Any DC Bus ONP-2.3, "Loss of l__ _ DC Power"

'6= Hold Point

=

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 RPLART PROCEDURE Page 44 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

43. IE offsite power was lost AND offsite power is available, THEN RESTORE power to plant equipment by performing ALL of the following:

a. IF NONE of the following are energized:

'R' Bus

'F' Bus

Cook 1 Line, THEN INITIATE actions to restore power to 'F' or 'R' Bus, as available. Refer to EOP Supplement 21.

b. WHEN ANY of the following are energized:

'R' Bus

'F' Bus

Cook 1 Line, THEN INITIATE actions to restore Plant power. Refer to EOP Supplement 29.

(continue) 0 = Continuously applicable step ft= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 PROCEDURE Page 45 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

43. (continued)

c. RESTORE power to the affected bus(es). Refer to the following applicable procedure:

.--< BUS -- - - PROCEDURE-.

1E EOP Supplement 29 1E SOP-30 1A or 1B ONP-2.1, "Loss of

____ ____ AC PPo e

d. RESTART plant equipment as desired.

0 == Continuously applicable step

¶= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR UIPROCEDURE Page 46 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Each D/G is limited to the following load rating:

2500 KW continuous

2750 KW two hours per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period

44. WHE#N 2400V Bus 1C or Bus 1D is 44.1. IF equipment needed to maintain energized, Safety Functions is available from a THEN as resources permit, de-energized 2400V Vital Bus ENERGIZE Plant buses by AND a power supply is available, performing ALL of the following: THEN ENERGIZE the bus AND RESTORE the needed equipment.

a. JE Bus 1C is energized, THEN PERFORM ALL of the following:

1) ENSURE CLOSED the following breakers:

152-115 (Bus 1Cto Transformers 11 and 19)

152-108(BuslCto Transformer 13)

(continue)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 jEOCj PROCEDURE Page 47 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

44. (continued)

2) ENSURE 480V MCCs are energized as appropriate:

MCC 1: 52-1906 (Bus 19)

MCC 3: 52-1301 (Bus 13)

MCC 7: 52-1103 (Bus 11)

b. IF Bus 1D is energized, THEN PERFORM the following:

1) ENSURE CLOSED 152-201 (Bus 1D to Transformers 12 and 20)

2) ENSURE 480V MCCs energized as appropriate:

MCC 2: 52-2006 (Bus 20)

MCC 8: 52-1201 (Bus 12)

(continue)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NEOPJ PROCEDURE Page 48 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

44. (continued)

NOTE: IF only one MCC is available (MCC 1 or MCC 2),

THEN BOTH vital DC Buses should be powered from the two Battery Chargers supplied by the same energized MCC.

c. ENSURE CLOSED Battery Charger Feeder Breakers from available MCCs:

1) MCC 1 Charger No 1 Feeder 52-1 46

Charger No 4 Feeder 52-1 86

2) MCC 2

Charger No 2 Feeder 52-225

Charger No 3 Feeder 52-285

d. VERIFY 125V DC Buses D10 d.1. PLACE Battery Chargers in and D20 are powered by a operation. Refer to SOP-30, Battery Charger. "Station Power."

45. WHEN PCP restart is desired, THEN RESTART desired PCPs.

Refer to EOP Supplement 3.

C = Continuously applicable step 0 = Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR A PROCEDURE Page 49 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

46. IF ALL PCPs are stopped, 46.1. ENSURE proper control of S/G THEN VERIFY natural circulation feeding and steaming rates.

flow in at least one PCS loop by ALL of the following:

Core AT less than 50°F (Average of Qualified CETs minus Tc)

Loop THs and Loop Tcs constant or lowering

Average of Qualified CETs at least 250 F subcooled

Difference between Loop TH and Average of Qualified CETs is less than or equal to 150 F

47. IE ALL PCPs are stopped, ANM natural circulation criteria are NOT satisfied, THEN ENSURE ALL of the following conditions exist:

All available Charging pumps are operating

SI flow is within the limits of EOP Supplement 4

At least one S/G is available for removing heat from PCS with level being maintained or restored to between 60%

and 70%

Average of Qualified CETs is less than superheated C)= Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT ProcNo EOP-6.0

~ EMERGENCY OPERATING Revision 14 UCRPLANT PROCEDURE Page 50 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

48. IF measured Containment hydrogen concentration is between 1%and 3%,

THEN PERFORM ALL the following:

CAUTION Each D/G is limited to a 2500 KW continuous load rating and a 2750 KW two-hour load rating. A hydrogen recombiner will draw a maximum of 75 KW.

a. PLACE at least one Hydrogen Recombiner in service. Refer to SOP-5, "Containment Air Cooling and Hydrogen Recombining System.'

b. OPEN MCC 9 Feeder Breaker, 52-1 304.

LOCATION: On Bus 13

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NUCLEAR PROCEDURE JPage 51 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS C) 49. PERFORM ALL of the following:

a. CALCULATE minimum PCS cooldown rate. Refer to EOP Supplement 2.

b. VERIFY BOTH of the following: b.1. IF additional sources of inventory which allow the requirements to be

The calculated cooldown met are NOT available, rate does NOT exceed THEN GO TO EOP-9.0, Technical Specification "Functional Recovery Procedure."

limits.

The calculated cooldown rate is achievable with the existing PCS heat removal path.

50. EVALUATE the need for a plant cooldown based on ALL of the I following:

Technical Specifications require plant cooldown

Plant equipment repair requires plant cooldown

Availability of Auxiliary systems

Available Feedwater reserve inventory

The Shift Supervisor deems plant cooldown is necessary 0 = Continuously applicable step f.= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 i EMERGENCY OPERATING Revision 14 NCE PROCEDURE Page 52 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

51. IF plant cooldown is NOT desired, I THEN PERFORM ANY of the following:

MAINTAIN the plant in a stabilized condition.

GO TO an alternate TSC/PRC approved procedure.

NOTE: IF emergency boration is in progress, THEN cooldown may commence/continue while the required shutdown margin value is calculated.

© 52. VERIFY PCS boron concentration 52.1. IF PCS boron concentration is less greater than or equal to required than required boron concentration, boron concentration as verified by THEN PERFORM BOTH of the sample or hand calculation. Refer following:

to EOP Supplement 35.

a. ENSURE emergency boration is

a. IF Emergency boration is in in progress.

progress AND PCS boron concentration b. WHEN required boron is greater than or equal to concentration is reached, required boron concentration, THEN SECURE emergency THEN SECURE emergency boration. Referto EOP boration. Refer to EOP Supplement 40.

Supplement 40.

'F= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 PROCEDURE Page 53 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

53. WHEN BOTH of the following conditions exist:

PZR Pressure within limits of EOP Supplement 1

PCS Cooldown rate is within required limits THEN PLACE LTOP in service as follows:

a. ENSURE OPEN PORV Isolation Valves. Refer to SOP-1 B, "Primary Coolant System -

Cooldown," Attachment 6.

b. PLACE BOTH of the following PORV LTOP enable keyswitches to ENABLE:

HS-0105A (Key: 1)

HS-0105B (Key: 4)

c. PLACE BOTH of the following PORV Handswitches to AUTO:

HS-1042B

HS-1043B

d. MAINTAIN PZR pressure within limits of EOP Supplement 1.

C = Continuously applicable step > A= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 N EMERGENCY OPERATING Revision 14 NUCLEAR A PROCEDURE Page 54 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS CAUTION A maximum PZR cooldown rate of 2000F/Hr and a maximum PZR Spray AT (PZR vapor temp - spray temp) of 3500 F should be observed to prevent damage to the PZR or Spray Nozzle.

NOT.E: PZR level indication decalibration will occur during cooldown. Correction curves in EOP Supplement 9, "Pressurizer Level Corrections Hot Calibrated" or EOP Supplement 10, "Pressurizer Level Corrections Cold Calibrated" should be used.

NOTE: Reactor Vessel Upper Head voiding resulting from controlled PCS pressure reductions is not expected to result in safety functions being jeopardized.

NOTE: Steam flow through two of the four Atmospheric Steam Dump Valves should be adequate to establish an initial cooldown rate of 750F/hr.

54. COOLDOWN by performing the following:

a. DETERMINE the PCS cooldown rate since event initiation using EOP Supplement 33.

(continue)

C) = Continuously

'r= Hold Point Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 p EMERGENCY OPERATING Revision 14 NUCLEAR PROCEDURE Page 55 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

54. (continued)

b. WHEN the PCS cooldown rate is within required limits, THEN COMMENCE a cooldown within the required limits using the Atmospheric Steam Dump Valves.

NOTE: P-50A and P-50B shall not be operated simultaneously when Tc is less than 3000F.

c. ENSURE not more than two PCPs operating (preferably one pump in each loop).

d. MONITOR the PCS cooldown rate. Refer to EOP Supplement 33.

55. MAXIMIZE PZR spray flow while controlling PCS pressure by using PZR heaters to equalize PCS and PZR boron concentration.

56. IF the PCS is to be opened AND PCS activity is acceptable for flow outside of containment, THEN DEGASIFY the PCS. Refer to SOP-2A, "Chemical And Volume Control System Charging And Letdown; Concentrated Boric Acid.'

C)= Continuously applicable step tr= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 N PROCEDURE rPage 56 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

57. IF BOTH of the following conditions exist for each SIG:

At least three of four S/G pressure sigmas indicate between 510 and 550 psia (indicators between alarm flags)

A controlled cooldown is in progress THEN BLOCK MSIS for the S/G meeting the above conditions by performing ALL the following:

a. BLOCK MSIV closure signal for the applicable SIG by pushing the appropriate pushbutton on Control Panel C-01:

HS/LPE-50A ('A' S/G)

HS/LPE-50B ('B' S/G)

b. VERIFY "STEAM GEN VALVES ISOLATION LOCKOUT" (EK-0970) is alarmed.

c. ENSURE CLOSED BOTH Main Feed Reg Valves:

CV-0701 ('A' S/G)

CV-0703 ('B' SIG)

d. ENSURE CLOSED BOTH Bypass Feed Reg Valves:

CV-0735 ('A' S/G)

CV-0734 ('B' S/G)

C)= Continuously applicable step ff Hold

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 I 1 EMERGENCY OPERATING Revision 14 IPROCEDURE Page 57 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

58. IF ALL of the following conditions exist:

PZR pressure is less than 1687 psia

SIAS is NOT actuated or blocked

'Safety Injection Signal Block Permit" (EK-1 369) is alarmed

A controlled cooldown and/or controlled depressurization is in progress, THEN BLOCK SIAS by performing ALL of the following:

a. PLACE AND HOLD SIAS block handswitch PB3-1 to BLOCK.

1) VERIFY the following annunciator in alarm:

"SAFETY INJ BLOCK RELAY SI-1 " (EK-1 337)

2) RELEASE SIAS block handswitch PB3-1.

(continue) 0 = Continuously applicable step ff= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 i EMERGENCY OPERATING Revision 14 NUCLAR PROCEDURE Page 58 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

58. (continued)

b. PLACE AND HOLD SIAS block handswitch PB3-2 to BLOCK.

1) VERIFY the following annunciators in alarm:

"SAFETY INJ BLOCK RELAY SI-2" (EK-1338)

"SAFETY INJ BLOCKED" (EK-1339)

2) RELEASE SIAS block handswitch PB3-2.

Indicated Charging and Letdown flows do NOT correspond to PZR level trend.

PZR level rising significantly faster than trend expected from Auxiliary Spray flow.

Core AT (Average of Qualified CETs - Tc ) or Loop AT (TH - Tc) rising for same secondary steaming and Auxiliary Feed rates.

Any operable PCS temperature indication is less than 250 F subcooled.

Operable RVLMS indicates voiding in the Reactor Vessel.

= Continuously applicable step ft= Hold O

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 N PROCEDURE Page 59 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

60. IF PCS voiding is indicated AND ANY of the following exist:

PCS pressure reduction is inhibited

PCS heat removal is inhibited

The Shift Supervisor directs void elimination, THEN PERFORM void elimination actions. Refer to EOP Supplement 26.

C = Continuously applicable step '6= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 t EMERGENCY OPERATING Revision 14 NUCLEAR NTPROCEDURE Page 60 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS NOTE: Failure of Instrument Air to containment will prevent venting the SITs.

61. IF PZR pressure is between 61.1. IF ANY SIT could NOT be isolated, 350 psia and 300 psia as read on THEN VENT the unisolated SIT PI-0104 (NR) or PR-0125 and using ONE of the following:

controlled AND a controlled cooldown is in a. VENT to containment as follows:

progress, THEN ISOLATE SITs as follows: 1) ENSURE CLOSED CWRT Vent Isolation Valves:

a. UNLOCK AND CLOSE the following breakers:

CV-1 064

CV-1 065 BREAKER

~OUTLET VALVE -

r

2) VENT each unisolated SIT 52-2129 MO-3041 T-82A one tank at a time by opening 52-2329 MO-3045 T-82B the Vent Valve and closing 52-2229 MO-3049 T-82C when tank is vented.

52-2429 MO-3052 T.82D

-SIT

-: :--VENTVALVE--

T-82A CV-3067 KEY: Locked Valve Key T-82B CV-3065

b. CLOSE the following SIT Outlet T-82C CV-3063 Valves: T-82D 1 CV-3051 l:BREAKER OUTLET KEY 3) WHEN ALL the following

-VALVE ___ conditions are met:

52-2129 MO-3041 98 52-2329 MO-3045 99

Unisolated SITs are 52-2229 MO-3049 100 vented and their associated vent valve 52-2429 MO-3052 101 closed

Plant conditions allow venting containment (continue) (continue)

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 i EMERGENCY OPERATING Revision 14 NULA PROCEDURE Page 61 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

61. (continued) (continued)

THEN OPEN CWRT Vent Isolation Valves:

0 CV-1 064 CV-1 065

b. VENT unisolated SITs via Clean Waste Receiver Tank Header per SOP-3, 'Safety Injection and Shutdown Cooling System.!

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 N EMERGENCY OPERATING Revision 14 NUCLEAR A PROCEDURE Page 62 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

62. IF ALL of the following conditions are met:

Tc is below 325OF AND prior to Tcs less than 300°F

SI Pump throttling criteria are met

HPSI pumps are NOT required for inventory control

A cooldown is in progress, THEN DISABLE BOTH HPSI pumps by removing Control Power fuses and fuse holders from the following breakers:

152-207, HP Safety Injection Pump P-66A LOCATION: 'D' Bus

152-113, HP Safety Injection Pump P-66B LOCATION: 'C' Bus

63. IF SI Pump Throttling criteria are satisfied, THEN RESET SIAS. Refer to SOP-3, "Safety Injection and Shutdown Cooling System,'

Attachment 4.

0 = Continuously applicable step 1(= Hold Point

('= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 I PROCEDURE [Page 63 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

64. WHEN ALL of the following Shutdown Cooling System entry conditions are met:

PCS parameters are acceptable for existing Containment conditions:

S ......

z . . .,-. -:.

Containment

. - -- :-. .- - .- . Containment Greater Than or

.:Less Than -. Equal To. 175F

-175 0F AMM 1 .. Greater

..Less Than-. ~Than or Equal

... r -, .. .... 3*psig at all: -To 3 psig at any times during time during the event

-. Parameter.. . the event PCs Pressure Less Than REFER TO EOP 270 psia Supplement 1 PZR Level Greater Than Greater than (corrected) 36% and 40% and controlled controlled Avg of Qualified Greater Than REFER TO EOP CETs 25 0F Supplement 1 Subcooling Avg of Qualified Less Than REFER TO EOP CETs and Loop 3000F Supplement 1 Temperature L

TSC has determined that PCS activity is acceptable for circulation outside Containment.

Containment Spray Pumps are not in use for Containment Atmosphere safety function.

Shutdown Cooling System monitoring equipment power is available from Y01 (continue) 0 =

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 N EMERGENCY OPERATING Revision 14 NUCLEAR ,NTPROCEDURE Page 64 of 69 TITLE: EXCESS STEAM DEMAND EVENT INSTRUCTIONS CONTINGENCY ACTIONS

64. (continued)

ORf Alternate measures for loss of Y01 are established per ONP-17, "Loss of Shutdown Cooling."

LTOP is operable.

Power to the following Shutdown Cooling Return Valves is available:

0 MO-3015 (MCC-1) 0 MO-3016 (MCC-2)

Access to Containment is acceptable for manual valve operation, THEN GO TO GOP-9, 'PIant Cooldown From Hot Standby/Shutdown" or TSCIPRC approved procedure.

End of Section 4.0 C = Continuously applicable step fA= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 NUCLEAR PANT PROCEDURE Page 65 of 69 TITLE: EXCESS STEAM DEMAND EVENT 5.0 PLACEKEEPER EOP ENTRY TIME:

STEP INSTRUCTIONS PAGE START DONE

4. Verify SIAS initiated 5

5. Ensure adequate SI flow and safeguards 6 equipment status

6. Ensure MSIVs and MSIV Bypass Valves are 7 closed

7. If PZR pressure lowers to less than 1300 psia 7 then establish one PCP per loop or if PCS subcooling is less than 25 0 F subcooled, then trip all PCPs

8. Determine required margin boron concentration 8

9. Ensure proper PCP configuration as PCS 8 temperature lowers

10. Verify operating limits for any running PCP 8

11. Verify condenser cooling or isolate steam to 9 condenser

12. Ensure at least one train of CR HVAC in 10 Emergency Mode.

13. Determine the most affected SIG 10 _

14. Isolate the most affected steam generator 11

15. Verify the correct S/G is isolated 12

17. Verify SI Pump throttling criteria are satisfied 15 _

18. If HPSI Pumps are operating and SI Pump 16 throttling criteria are satisfied, throttle HPSI flow or stop pumps Q = Continuously applicable step It,= Hold Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 N PLNT PROCEDURE JPage 66 of 69 TITLE: EXCESS STEAM DEMAND EVENT 5.0 PLACEKEEPER EOP ENTRY TIME:

STEP INSTRUCTIONS PAGE START DONE

19. If LPSI Pumps are operating and PZR pressure 17 is being controlled greater than 200 psia, stop pumps and close valves

20. If PZR pressure lowers uncontrollably to less 17 than 200 psia and LPSI Pumps have been stopped, restart LPSI pumps and open valves

21. Ensure the least affected S/G has level being 18 a maintained or being restored to between 60%

and 70%

22. Record each occurrence of PZR spray with AT 18 _

greater than 200OF

24. Place Hydrogen Monitor in service 24

25. If the Containment has pressure greater than or 25 equal to 4.0 psig or has high radiation, ensure Containment Isolation signal initiated

26. If the Containment pressure is greater than or 26 equal to 4.0 psig, verify available Containment Spray Pumps running

27. If Containment pressure rises to greater than or 27 equal to 35 psia, then close the CCW containment isolation valves

28. If PCP seal cooling is lost, isolate seal leakoff 27 and restore PCP seal cooling

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 EMERGENCY OPERATING Revision 14 NUCLEAR PLANT PROCEDURE Page 67 of 69 TITLE: EXCESS STEAM DEMAND EVENT 5.0 PLACEKEEPER EOP ENTRY TIME:

STEP INSTRUCTIONS PAGE START DONE

30. When SIRWT level less than or equal to 25%, 28 then prior to RAS, perform Pre-RAS Actions.

31. When SIRWT level lowers to below 2%, then 29 perform Post-RAS Actions.

32. If Charging Pump suction is aligned to the 30 SIRWT and RAS has initiated then, disable the Charging Pumps and add caution tag

33. When Containment pressure is less than 31 3.0 psig and CHP has initiated, align components and reset CHP

34. If Containment Spray System is operating and 33 conditions are satisfied, secure Containment Spray

35. If Containment Area Radiation Monitors indicate 35 less than 1 x 101 R/hr and Containment pressure is less than 3.0 psig, reset CHR

36. When Containment water level approaches Si 36 valve elevations, open and disable Si valves

37. If Letdown is isolated and conditions allow, 37 restore Letdown

38. If requirements are met, then establish charging 37 pump suction from the VCT or SIRWT

40. If it is desired to draw a bubble in the PZR, 38 perform the actions to draw a bubble in the PZR

41. If SI Pump throttling criteria are met, then 40 maintain PZR level between 20% and 85%

(42% to 57% preferred) 0 = Continuously applicable step Irf= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0 E EMERGENCY OPERATING Revision 14 PROCEDURE [Page 68 of 69 TITLE: EXCESS STEAM DEMAND EVENT 5.0 PLACEKEEPER EOP ENTRY TIME:

STEP INSTRUCTIONS PAGE START DONE

42. If any vital AC or DC buses are not energized, 43 restore power to affected buses

43. If offsite power was lost and is available, restore 44 power to plant equipment

44. When 2400V Bus 1C or 1D is energized, then 46 energize Plant buses

45. If desired, restart PCPs 48

46. Verify natural circulation flow in at least one 49 loop

47. Verify two phase natural circulation 49

48. If Containment hydrogen concentration is 50 between 1% and 3%, place at least one Hydrogen Recombiner in service

49. Verify calculated cooldown rate does not 51 _

exceed Technical Specification limits and the cooldown is achievable with the existing PCS heat removal path

50. Evaluate the need for a plant cooldown 51 _

51. Determine alternatives if plant cooldown is not 52 _

desired

52. Verify PCS boron concentration greater than or 52 C) equal to required boron concentration.

53. When PZR Pressure and PCS Cooldown rate 53 within required limits, place LTOP in service.

54. Commence a PCS cooldown 54

55. Maximize PZR spray flow while controlling PCS 55 pressure by using PZR heaters to equalize PCS and PZR boron concentration C)= Continuously applicable step '&= Hold Point Point

PALISADES PALISADES NUCLEAR PLANT Proc No EOP-6.0

! EMERGENCY OPERATING Revision 14 NUCLRLNT PROCEDURE Page 69 of 69 TITLE: EXCESS STEAM DEMAND EVENT 5.0 PLACEKEEPER EOP ENTRY TIME:

STEP INSTRUCTIONS PAGE START DONE

56. If the PCS will be opened and PCS activity 55 allows, then lineup for PCS degasification

57. When Main Steam pressure is between 510 and 56 550 psia, block MSIS

58. When PZR pressure is less than 1687 psia and 57 SIAS is not actuated, BLOCK SIAS

60. If PCS voiding is indicated, perform void 59 elimination

61. If PZR pressure is between 350 psia and 60 300 psia and a cooldown is in progress, isolate SITs

62. Disable both HPSI pumps when listed 62 conditions are met

63. Reset SIAS 62

64. When all shutdown cooling system entry 63 conditions are met, exit this procedure End of Section 5.0

ATTACHMENT 4 EOP SUPPLEMENT 1, "PRESSURE TEMPERATURE LIMIT CURVES" 5 Pages Follow

Y-q.

Pressure and Temperature Limit Curves 2500 -..

Unner Portion

......... - .I.-.I .- I

. .. , . . . . I.1.

. . 1.

. .%.!.!.1.

200 'IF Subcooling Curve Z.. .... 1. 1.1. .I . . I.. .:. . . . 1. . . .I...I.I.

. . . . .... 1. . . . . . .

(Usc lowest operable temperature) . . . .1.

2250 - Supercedes VLTOP curve if PCS - . . . . . . .

4.-I I -i Mu

":has experienced an uncontrolled 7-cooldown which causes PCS .:7.-... . 4.. -4.'... m r-tempcrature to go below 500 PFo rc1 2000 _ ! . . . 'A i-n

>IK,..':.......

-I-. ... ... -:--

-- N. -:- ... -

.... 1.

........ 1. . 4

. .:. ... ... 7---

. . . . . ... ... . f-CD G) 0 1750 - ... ....-.... ' aI 10 m m (U)1500 -

22 Use lowest opcrable T i$.l. I . -r.

0 C 0 r-m -o m lr tr. A1. . . I I C

'-125C m

a) lOOC .t.*.i. ... . . . . .1/4 .1/46 . t

i H

Z r-

-I 75 0- - .~. 9 .Saturation Curve C) Z 7 t7. . ....

CD CI H1 jj-*Curves based on highestaviblteprue 50 0- -r yr.reading in PCS including

-u CW -o ar.F 25 Subcoobn jQ Avg. Qualiflied CETs 0) C la 0

-I to 25 CD 0 0 2 rn S*.. 3

-. ..i.i.4 . .f

. Use highest operable T,

.. w 1i O prtigRgo 44 CD a I1I11I11I11I1II1II1II1II1I11I11I11I11I1II1II1II1II1I11I1111kI I II lII II I I I I I I I I I I I I I I I I I I I

-u 300 325 350 375 400 425 450 475 500 525 550 575 600 625 650 W

Ternperature (0 F) Note: Use degraded Containment condition curves if Containment -1, C_

la condition is or has exceeded 1750 F or 3 psig. 0 MI C1iI -&

Pressure and Temperature Limit Curves 00a2'"r, P W

Lower Portion 8M 800 _ e. j ;; r - --- ;Tr..........

I I .- -

U)

.I ... .. .... . j ... S.I.~ . ... 4... .

..... ..... ...f

Non Operating Region ; .... , , I.:

. . / ......... :.....

700 inimum temperature with the reactor vessel head tensioned is 75 0F

.4

.I

-i

....;.:....T............:......

.~...../........... =i M J ...... ................. ........... .............. ..... ....... .... ;.......... r- M r

...... I... .

M 9 600 .. . .....

.. ..... ... M Fn Curves based on highest ......... ........ ;...i ................... 7

..... I.......... :.....

I -.:1. ..... :I.... .I..... 10 I M available temperature I.....

. . CD lu 0 D

.. reading in PCS including ...........

....... ... ...... (.... ......I.... i..... !.....

..... I........... ;......I..... W M M M 500 ,Avg. Qualified CETs 4.

4. - .4

. . . . W I= 0 Z W 00- .....

. ...... .. ................ :..... :..... N CD 0 0 Z M a

~~~~... ,,......

.. .;4.. . . . . .. . .. ;.z

..D.... .% .......-- I. ---- w..j......................

..... I ........... I..... :.....

......................... :..... J 0 0 0

%E.Le 4 0 0 a M f-

..... a

'IC M M M a) .......................... . .... ..................... . .......... ..... . . ................ . . .

....................................... .... . ............... ..... ......I.... ..... I............I.......... .....

(D M M M

-1 .......... ..................... ..... ........... ........... ..... ..... ............ ................. 2) f.f. la W

0 300 W . . ...........

.......... .... ..... ..... ......I.... .....

i=

CD I Z 0

r I- . . .............. .................. ----------------

r- Z a- . . ........... .. ..... ..... .......... . . . .... .......... ................

3. q 200 ........................ Curve Minimum Pressure for PCP Operation

.... ............ based on use of PI-0104 narrow range 25-F Subcoolin

.......... ..... ...... 0 W Use highest operable TC .......... ...... 6*- C9 lu M M C lu I

................ ......... ...... 2) dc la 0 la 0 100 CD W

..... ......I......I .... I..... ..... .......... I..... .......... ............... .......... 6 Z

. . ........... .......................................... ................. ..... ..... ....................... ....... ......... .............. W 0

3 3 0

....................... ........... ..... ......................... .......... CD m

...... I...........

Iuraat tinon C iu Wel'.. M 0 7 lu 0 I I I I I i i I i I i I i i I I i i I I I I I I I I I I W

a 10 50 100 150 200 250 300 350 la F

Temperature (OF ) No,-te: Use degraded Containment condition curves if Containment 0 3 condition is or has exceeded 175-F or 3 psig. M tn tn -L r-0

Pressure and Temperature Limit Curves Shutdown Coolinq Curve 600 IlNon Operating ...............

Minumum temperature with the reactor vessel head tensioned is 75 OF -4

-i 500 I-m m r-

Curves based on highest available temperature m Z-n

-U

reading in PCS including ......... ... ....................... -I

Avg. Qualified CETs :..... P.... .... CD

-o a 400 CD 0 0

-I C) C CD m 0m L..

Ii.:11 a I-C') CD a la -I (D200 CD z C) I-CD 100 ...............

Jj......

Minimum Pressure for PCP Operation Curve based on use of PI-0104 narrow range Use highest operable Tc

. *..............I............

[

I-Z

-I CD 0 - ........................................ 250...F

-a

0) CD C W' so

.*................................. Saturation Curve..... CD to *0 0 0

CD CDI 0 la Z

............. CD 0 m

_ _ _ __ _ - - -- ..-.-- .x 0

(IV 50 100 150 200 250 300 C la Temperature (OF) -N-ote-: Use degraded Containment condition curves if Containment la

.condition is or has exceeded 175 0 F or 3 psig. CD 0 CD

-4.

U'

2C M P

Pressure and Temperature Limit Curves r,0 U)

Degraded Containment Conditions 8M I U) 2500 - - - -

1: .. .. ...... ;...;... :... ... ;...

... - I ... I... :... *I IIi .

Non Operating Region., ... .. . . .

... 11111111111:11.

... I...I...

... I..;. .. ~ ....

. . . ........ I...!... I., !pi. ..

-q I ... ........ ,

... -i

...... ....... :... ....... V ,I I- m 200'F Subcoolingjf 2000 m

m C')

Note l:This curve applies whenever Containment . .... ... :............... ..................

.ii...

. /

t:/

I.

1

,v has exceeded 175 0F or 3 psig. . . . .

f>k?

.. :./. 1.

./....". ... I....... ... I... ... I........... I...

./

-I a

Note 2:Add Containment pressure (psig) to . ....... .. 1....... ... - I... ; ....... I...I.. .. CD U) -u

-..... / . , U) indicated pressure to correct to psia. ....... ...... :... ... . .. I....... . . :...

0 z C) C) z

.. . .. . . . . . . . . CD U)1500 -I

. . . .11 . . . . .

0.1 Note 3:VLTOP curve is more restrictive than calculated VLTOP setpoint. Use lowest 4 ...

1

/ CD m C) a operable Tc _____I

... ;................. .................. .. /.....

. C 0 I-ai) ....... T .... .... ......

I7.

... :......I...; ... ....A....I. /

V

-I an m 7 .... .... .... .. .. .. .... / ... ....... .......... Z... ;... [/.

a)1 000 - - - - - - - -- ---- 6 4 5 -

- 4 P 4. *

- - 4. S- - -

4- h- d-EL Minimum Pressure for (Note G) z

1 Primary Coolant Pump

.T~KNTT7 operation

. . . . lo CD CD -I 500 1 I/: : : :

-o Co *0 "I

... e- -

... *Minimum Subcooling CD 0 So 0

11 : I .. .. .. , . la

-. ~ .. t ... !... :~6 Co is z0

............. :... ......... 0 I.

. I.

INon Operating Regioni:". 0

-.4 -

I S j...j...F...........j...

I I 5 a

.. - -.r.4- . -.-.

. I

..+

I 5 I

j...j...

4.4.4-4

.+ --I

.I J...j i

........ :... j.. .

, .4.

. .I

.I II*.

U

.I I i. .

. -. 711.14..-T-.; ...

. . I 5

(n

-o la 200 250 300 3150 400 450 500 550 600 650

Curves based on the highest available temperature Ternperature (O F) reading in PCS including Avg. Qualified CETs

-h U'

tn I -

0

Shutdown Cooling Entry Window m j0 I pIC/2 225 For Degraded Containment Conditions I Ii(0 Note l:This curve applies whenever Containment h.... pi-........1..... .... NON OPERATING REGION Notc 2:Add Containment pressure (psig) to Maximum allowed Shutdown Cooling inlet pressure I ....

indicated pressure to correct to psia. .

_;___._____I -

-i 200 i-m -n

.......... ....... ........ ......... I........ ........ I........ ....... I.. A^...... ........ ....... ........ ..... ,... ....... ........ ........ ......... I....I..:

r- r

.. . . . .. . . . . . . . ................ ... . . ...... ................ ..... . .,1z,,....... ....... ........ ........ .. . ........ ... ...

I-

....... , i ............................ i1'i' z

175 0 C) m

......... ................. .. .. . ... .. ......... ,. :,................ .................. ........ ........ .........I................ I........ . . . .I ClD Cl) z ci2 ......... .......... ........ ........ ......... ................. ........ ................ ........... ... .................. ............. .... ... ClD M 0 C

.. ^' 2..... ........ ..... , ',.. ........ .. . . .I ,,j8 CD ,CD cm o150

-I 0m -u I................ ......... .......... ......................... ....... .......... ................... ............ ..,,

'-4 m

................... ...... ................. ....... ........'-1'-: --

Xi

.. . . ... . . . ........ .. .. . ....... ................................ . . . . . . ......................... . . . ... .....- .. . . . . .. . . .. :0

................................. ........ . . .... .............. ........... ......................... . ....... ...... .. .. . ... ... .. z

.. . . . ........ ........ . . ........... .. .. . ... . .. . . ...................... ... ....................................... ubcooling.. .... .. C) G)z 100 . ........ ....... ...... .. . . .I.. %1' ................. . 1..... ........ ..... . . . . .. . . z....

.. -i

.. . . . . ...... ... ..... .... .... Miiuubol CD 75 _ . X ',--'. < x ' ' .a,.; , .8 tMaximum Shutdown l 1 U,

-o 0 -a

......... l....::^l;............... .................... :; .ColnTeprte

-!* Cn 0 to

-- Note: Use Pl-0104 (narrow range) OR PR-0125 l......... .............. l-..... -.- .--I-*-:1;.............;0 (0 a_ a 10 F 0 z

....... ;,;:.... OPERATING

-:1' O REGIONI 3

. ....... ....... . ....... . . . . ... , 'i 0

-u 75 Cn 200 225 250 275 300 'a la

Curves based on the highest available (1 Tem perature (OF) temperature reading in PCS including Avg. 0 Qualified CETs 0 ft 01 -L

ML052870473

Contents

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Continuously applicable step t'

Continuously aDDlicable step) 't,

Continuously applicable step 0)

Description:

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ML052870473

Text

Continuously applicable step t'

Continuously aDDlicable step) 't,

Continuously applicable step 0)

Description:

Navigation menu

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