Text

Emergency Plan Implementing Procedure Revisions
	ML030160516
Person / Time
Site:	Point Beach
Issue date:	01/06/2003
From:	Cayia A; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Security and Incident Response
References
	NRC 2003-0002
	Download: ML030160516 (105)
	v • d • e

Nuclear Management Company, LLC Point Beach Nuclear Plant Cmmiedto M

ceee6610 Nuclear Road Two Rivers, WI 54241 NRC 2003-0002 January 6, 2003 Document Control Desk U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington DC 20555 Ladies/Gentlemen:

DOCKETS 50-266 AND 50-301 EMERGENCY PLAN IMPLEMENTING PROCEDURE REVISIONS POINT BEACH NUCLEAR PLANT, UNITS I AND 2 Enclosed are copies of revised procedures to the Point Beach Nuclear Plant Emergency Plan Implementing Procedures. The revised procedures dated January 3, 2003 should be filed in your copy of the manual.

Sincerely, yia IA Si J ice esident FA Pd Enclosures cc: NRC Resident Inspector (w/ole)

Incident Response Center, Region III

NRC 2003-0002 Page 2 bcc: EP

K. M. Duescher (2)* R. Pulec* *w/o enclosures File: A9.2.1*

POINT BEACH NUCLEAR PLANT EPIP INDEX EMERGENCY PLAN IMPLW5NTING PROCEDURES Revision 89 January 3, 2003 INDEX PROCEDURE REVISION EFFECTIVE PERIODIC NUMBER PROCEDURE TITLE NUMBER DATE REVIEW DATE EPIP 1.1 Course of Actions ................................................. 42 C 10/25/02 08/09/01 EPIP 1.2 Emergency Classification ..................................... 38 R 12/27/02 12/27/02 EPIP 1.3 Dose Assessment and Protective Action Recommendations ............................................ 29 R 06/24/02 05/03/02 EPIP 1.4 Credible High or Low Security Threat ......................... 1 C 07/12/02 12/14/01 EPIP 2.1 Notifications - ERO, State & Counties, and NRC ..... 25 R 06/25/02 02/06/02 EPIP 4.1 Technical Support Center (TSC) Activation and Evacuation .................................................... 34 R 01/03/03 01/03/03 EPIP 4.2 Operations Support Center (OSC) Activation and Evacuation ................................................... 16 R 01/03/03 01/03/03 EPIP 4.3 Emergency Operations Facility (EOF) Activation and Evacuation .................................................... 28 R 01/03/03 01/03/03 EPIP 4.7 Offsite Radiation Protection Facility (OSRPF)

Activation and Evacuation ..................................... 3 R 01/03/03 01/03/03 EPIP 5.1 Personnel Emergency Dose Authorization ............ 14 R 02/06/02 02/06/02 Radioiodine Blocking and Thyroid Dose

ý'ý IEPIP 5.2 Accounting ........................................................... 13 R 03/20/01 01/03/03 EPIP 6.1 Assembly and Accountability, Release and Evacuation of Personnel ..................................... 24 R 01/03/03 01/03/03 EPIP 7.3.1 Offsite Radiation Sampling and Survey ................ 22 R 07/12/02 07/12/02 EPIP 7.3.2 Post-Accident Isokinetic Stack Sampling System ....... 7 R 07/12/02 07/12/02 EPIP 7.3.7 Estimating Radioiodine Air Concentrations ............ 5 R 07/12/02 07/12/02 EPIP 8.4.1 Post-Accident Sampling and Analysis of Potentially High Activity Reactor Coolant ...... 16 C 10/25/02 07/12/02 EPIP 8.4.2 Post-Accident Sampling of Containment A tm osphere ............................................................. 11 C 09/13/02 07/12/02 EPIP 8.4.3 Emergency Containment Sump "A" Sampling ..... 7 07/12/02 07/12/02 EPIP 10.1 Emergency Reentry ............................................... 22 R 07/12/02 07/12/02 EPIP 10.2 Core Damage Estimation ....................................... 19 R 07/26/02 01/30/01 EPIP 10.3 Post Accident Containment Hydrogen Reduction ....... 5 R 05/19/00 05/19/00 C = Continuous Use (T - Temporary Change) R = Reference Use Page 1 of 2 I = Information Use

POINT BEACH NUCLEAR PLANT EPIP INDEX EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 89 January 3, 2003 INDEX PROCEDURE REVISION EFFECTIVE PERIODIC PROCEDURE TITLE NUMBER DATE REVIEW DATE NUMBER EPIP 11.2 Medical Emergency ................................................... 17 R 09/20/02 07/12/02 EPIP 12.1 Emergency Event De-Escalation, Termination, or Recovery Operations ................................................. 9 R 12/27/02 12/27/02 14 R 07/12/02 07/12/02 EPIP 12.2 Recovery Implementation ..........................................

C = Continuous Use R = Reference Use (T - Temporary Change)

Page 2 of 2 I = Information Use

EPIP 4.1 TECHNICAL SUPPORT CENTER (TSC)

ACTIVATION AND EVACUATION DOCUMENT TYPE: Technical CLASSIFICATION: NNSR REVISION: 34 EFFECTIVE DATE: January 3, 2003 REVIEWER: N/A APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Emergency Preparedness Verified Current Copy:

Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PU RPOSE ...................................................................................................................... 3 2.0 PREREQUISITES ...................................................................................................... 3 3.0 PRECAUTIONS AND LIMITATIONS ................................................................... 6 4.0 INITIAL CONDITIONS ............................................................................................ 6 5.0 PROCEDURE ........................................................................................................ 6 5.1 A ctivation ....................................................................................................................... 6 5.2 E vacuation ...................................................................................................................... 7

6.0 REFERENCES

...................................................................................................... 8 7.0 B A SE S ........................................................................................................................... 9 ATTACHMENT A TECHNICAL SUPPORT CENTER LAYOUT ........................................... 10 ATTACHMENT B OPERATION OF THE EMERGENCY VENTILATION AT THE TSC ........ 11 ATTACHMENT C TSC EMERGENCY POWER SUPPLY ...................................................... 15 ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING) AND PARTICULATE, IODINE AND NOBLE GAS (PING) RADIATION M ON ITO RS ................................................................................................. 19 ATTACHMENT E DELETED - MOVED TO EPIP 1.1 ............................................................ 21 ATTACHMENT F DELETED - MOVED TO EPIP 1.3 ............................. 22 ATTACHMENT G PLANT PROCESS COMPUTER SYSTEM (PPCS) ................................... 23 Page 2 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION 1.0 PURPOSE This procedure provides instructions for the activation of the Technical Support Center (TSC).

The TSC is activated upon declaration of an ALERT, or higher classification, or at any other time deemed necessary by the Shift Manager (SM) . Activation of the TSC does NOT require the declaration of an emergency. Attachment A, Technical Support Center Layout, describes the facility layout.

This procedure also describes the method by which the TSC and OSC is evacuated and responsibilities transferred to alternate locations.

2.0 PREREQUISITES 2.1 Responsibilities 2.1.1 Technical Support Center Manager:

a. Directs all onsite emergency response in support of the Control Room.

b. Upon activation of the TSC, assumes a formal turnover of responsibilities from the SM for:

Assessment of plant conditions and classification recommendations to the Emergency Director per EPIP 1.2, Emergency Classifications.

"* Onsite radiological assessments and protective action recommendations (PARs).

"* NRC (ENS) Communications.

"* Assembly and Accountability, Release and Evacuation of Personnel per EPIP 6.1.

c. Decision to evacuate the TSC and OSC and relocate to alternate areas.

2.1.2 Engineering Coordinator:

a. TSC activation prior to the arrival of the TSC Manager.

b. Directs the engineering staff in providing technical support.

Page 3 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION 2.1.3 Operations Coordinator:

a. TSC Emergency Power per Attachment C, TSC Emergency Power Supply.

b. Interface with Control Room and input to classification based on plant conditions.

c. Monitors EPIP 1.2 based on plant conditions and provides event classification recommendations. Assists in setting priorities in support of the Control Room.

d. Notify personnel in the protected and exclusion areas of the event classification changes.

e. Initiate full-site (protected and exclusion areas) assembly.

2.1.4 Rad/Chem Coordinator:

a. Activates the TSC emergency ventilation system per Attachment B, Operation of The Emergency Ventilation at the TSC.

b. Activates the Wisconsin Electric Dose Assessment Program - WEDAP (if EOF is NOT being activated) per EPIP 1.3, Attachment C.

c. Activates the Iodine and Noble Gas (ING) Monitors per Attachment D, Activation of the Iodine and Noble Gas Radiation Monitors.

d. Assesses onsite radiological conditions in addition to plant and facility habitability.

e. Assumes offsite dose assessment and protective action recommendations (PARs) to the Emergency Director in the event the EOF cannot perform that function.

f. Coordinates the release or evacuation of all non-essential personnel (protected and exclusion areas).

2.1.5 ENS Communicator - Maintains communications with NRC headquarters.

2.1.6 Plant Status Monitor:

a. Activates Plant Process Computer System (PPCS) workstation per Attachment G, Plant Process Computer System (PPCS).

b. Verifies the Emergency Response Data System (ERDS) is activated at an ALERT or higher classification if NOT previously done in the Control Room per EPIP 1.1 Attachment C.

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION

c. Supports event monitoring by serving as resource for plant and environment data.

d. Maintains plant status boards.

2.1.7 ERF Communicator - Maintain continuous communication between Control Room, EOF, TSC, and JPIC. Assists with monitoring plant conditions and event classifications.

2.1.8 OSC Coordinator - Ensures OSC priorities and reentry teams are in direct support of the Control Room and TSC. Maintains oversight of the OSC in response to medical emergencies.

2.1.9 Rad/Chem Monitor - Support radiological response by serving as resource for onsite assessment of radiological conditions in addition to plant and facility habitability. Maintains rad/met status boards.

2.1.10 Security Coordinator - Controls ingress/egress to PBNP, monitors personnel accountability, and is a liaison between Emergency Response Organization and Security.

2.1.11 Reactor/Core Physics Engineer - Provides engineering support.

2.1.12 PRA Engineer - Provides engineering support.

2.1.13 Mechanical System Engineer - Provides engineering support.

2.1.14 Electrical/I&C - Provides engineering support.

2.1.15 Administrative Support Leader - Provides clerical and administrative support to the Emergency Response Organization.

2.2 Equipment 2.2.1 TSC inventory per EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC, and OSC Emergency Preparedness Supplies 2.2.2 TSC Satellite File and Drawing System Aperture Cards 2.2.3 PPCS Workstations 2.2.4 WEDAP Workstation 2.2.5 Radiation Monitoring System 2.2.6 Communications equipment per EPMP 2.1, Testing of Communications Equipment Page 5 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION 3.0 PRECAUTIONS AND LIMITATIONS Evacuation of the TSC shall include the coordination of the evacuation for the OSC.

4.0 INITIAL CONDITIONS 4.1 This procedure shall be implemented upon declaration of an ALERT or higher classification or at the discretion of the Shift Manager to provide the Control 'Room technical support.

4.2 Evacuation of the TSC and OSC shall be completed when any of the following conditions exist:

4.2.1 Emergency response personnel radiation doses in the TSC/OSC are exceeding or are projected to exceed the following for the duration of the event:

a. Whole body (TEDE) 4 rem (calculated)

b. Thyroid (CDE) 25 rem (calculated)

I 4.2.2 Other emergency conditions (e.g., fire, toxic or flammable gases, or loss of power).

5.0 PROCEDURE 5.1 Activation 5.1.1 The TSC Manager shall ensure the completion of the TSC Position Instruction Manual, PIM TSC 2.1, TSC Manager.

NOTE: The facility may be activated earlier based upon the TSC Manager's discretion if determined there is an understanding of the events in progress and adequate staffing resources in place to respond to the emergency.

5.1.2 Minimum staff positions are:

a. TSC Manager

b. Operations Coordinator

c. ERF Communicator

d. OSC Coordinator

e. Rad/Chem Coordinator Page 6 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION

f. Engineering Coordinator

g. ENS Communicator 5.1.3 The TSC emergency ventilation system, iodine and noble gas (ING) radiation monitors, and PPCS equipment will be activated per the attachments within this procedure.

5.1.4 The WEDAP equipment and emergency power supply will be activated, as appropriate, per the attachments within this procedure.

5.1.5 Each ERO position shall activate and assume their area of responsibility and function within the TSC using their Position Instruction Manual.

5.2 Evacuation 5.2.1 The TSC and OSC shall be evacuated under the direction of the TSC Manager.

5.2.2 The key to an orderly evacuation is good communications, formal turnover with personnel who are assuming TSC/OSC responsibilities, and documentation of actions and notifications.

5.2.3 The Operations Coordinator and Operations Support Center Coordinator shall report to the Control Room to coordinate current and projected support of the operating crew.

5.2.4 Select the best relocation area(s) (i.e., the EOF, upper level of the Admin Building, North Service Building cafeteria, computer room above the Control Room) within the plant to relocate all remaining TSC and OSC personnel.

5.2.5 Transfer responsibility for all communications to the EOF. The ENS Communicator may relocate to that facility.

5.2.6 Direct the Control Room to take responsibility for in-plant teams until the relocation area is functional.

5.2.7 Ensure all personnel are accounted for after reaching the relocation area(s).

5.2.8 Develop an immediate plan for reentry of the TSC/OSC area, if possible.

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION

6.0 REFERENCES

6.1 Point Beach Nuclear Plant Emergency Plan 6.2 EPIP 1.2, Emergency Classifications 6.3 EPIP 1.3, Dose Assessment and Protective Action Recommendations 6.4 EPIP 4.2, Operations Support Center (OSC) Activation and Evacuation 6.5 EPIP 6.1, Assembly and Accountability, Release and Evacuation of Personnel 6.6 EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC, and OSC Emergency Preparedness Supplies 6.7 EPMP 2.1, Testing of Communications Equipment 6.8 PIM TSC 2.1, TSC Manager 6.9 PIM TSC 2.2, Administrative Support Leader 6.10 PIM TSC 2.3, Operations Coordinator 6.11 PIM TSC 2.4, ERF Communicator 6.12 PIM TSC 2.5, Plant Status Monitor 6.13 PIM TSC 2.6, Operations Support Center Coordinator 6.14 PIM TSC 2.7, Rad/Chem Coordinator 6.15 PIM TSC 2.8, Rad/Chem Monitor 6.16 PIM TSC 2.9, Engineering Coordinator 6.17 PIM TSC 2.10, Reactor/Core Physics Engineer 6.18 PIM TSC 2.11, Probabilistic Risk Assessment Engineer 6.19 PIM TSC 2.12, Mechanical Systems Engineer 6.20 PIM TSC 2.13, Electrical/Instrumentation & Control Engineer 6.21 PIM TSC 2.14, ENS Communicator 6.22 PIM TSC 2.15, Security Coordinator Page 8 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION 7.0 BASES B-1 10 CFR 50.47(b), Emergency Plans B-2 10 CFR 50.47, Appendix E.IV, Content of Emergency Plans B-3 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Response Plans and Preparedness in Support of Nuclear Power Plants B-4 NUREG-0737, Clarification of TMI Action Plan Requirements Page 9 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT A TECHNICAL SUPPORT CENTER LAYOUT rowavel WORK I Engineers:

PrA TABLE for Plant PRA Drawings Elec/I&C Rx/Core Mech

'Microwave Unes

"* Milw - (414) 221-5190

"* Appleton - (920) 380-3501

"*Kewaunee- Future SEC ENS NRC ENG Coord Comm Seat Coord 6585 WEDAP Admin Support Rad/Chem Monitor Ringdown to EOF:

RAD/MET x6394 Page 10 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EMERGENCY VENTILATION AT THE TSC Page I of 4

1.0 DESCRIPTION

- EMERGENCY VENTILATION SYSTEM The Technical Support Center (TSC) heating and ventilating system has a normal and emergency operating mode. Under normal operation, the air intake is from the outside air vent on the east wall of the TSC building. The intake air under normal operation is essentially unfiltered.

Figure 1 TSC Normal Ventilation Flow Paths Page I11 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EMERGENCY VENTILATION AT THE TSC Page 2 of 4 In the emergency mode, there are two optional air intake locations. One is adjacent to the normal intake on the east wall of the TSC building (see Figure 2), and the other is on the north wall of the Unit 2 turbine hall. (See Figure 3).

Figure 2 Figure 3 TSC Emergency Ventilation Flow Path TSC Emergency Ventilation Flow Path (South Inlet) (North Inlet) 2.0 OPERATION OF THE EMERGENCY VENTILATION SYSTEM 2.1 Assure that air flow is from the TSC to the turbine building. Check DPI-4713A on the annunciator panel (El. 18.5') to verify that the TSC is pressurized relative to the turbine building.

2.2 IF NOT, coordinate manipulation of the turbine building supply fans, dampers, and exhaust fans with the Operations Coordinator to achieve air flow from the TSC at Door 116.

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EMERGENCY VENTILATION AT THE TSC Page 3 of 4 2.3 To shift the heating, ventilating, and air conditioning system from the normal to emergency mode, locate Panel M-1.

Figure 4 El. 18.5' - Administrative Building With TSC 2.3.1 Turn the "auto/unocc/occupied" switch on Panel M-1 to the "occupied" position.

2.3.2 Turn the "normal/emergency" control switch on Panel M-1 to the "Ilemergency"position.

2.3.3 Select the north or south (east) emergency intake depending on meteorological conditions. Select the upwind intake duct.

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EMERGENCY VENTILATION AT THE TSC Page 4 of 4 2.4 TSC Auxiliary Air Conditioning 2.4.1 Select "hand" on compressor K22 located on the west wall of El. 18.5' of the TSC building (see Figure 4).

2.4.2 Turn the air handling unit (W89) disconnect to the "on" position in the TSC room north wall (see Attachment A).

2.4.3 Push "start" pushbutton.

3.0 RETURNING THE EMERGENCY VENTILATION SYSTEM TO NORMAL MODE 3.1 Heating, Ventilating, and Air Conditioning System 3.1.1 Turn the "auto/unocc/occupied" switch on Panel M-1 to the "auto" position (see Figure 4).

3.1.2 Turn the "normal/emergency" control switch on Panel M-1 to the "normal" position (see Figure 4).

3.2 TSC Auxiliary'Air Conditioning 3.2.1 Select "auto" on compressor K22 located on the west wall of El. 18.5' of the TSC building (see Figure 4).

3.2.2 Push the air handling unit "stop" pushbutton.

3.2.3 Turn the air handling unit (W89) disconnect to the "off' position in the TSC room north wall (see Attachment A).

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 January 3, 2003 TECHNICAL SUPPORT CENTER (TSC)

ACTIVATION AND EVACUATION ATTACHMENT C TSC EMERGENCY POWER SUPPLY Page 1 of 4

1.0 DESCRIPTION

1.1 The power source for the Technical Support Center (TSC) is IB-01 480 V. (See Figure 1 for the main disconnect locations.)

Figure 1 El. 18.5'- Administrative Building With TSC 1.2 The emergency power supply is available by operation of the auxiliary diesel for G05 and the auto bus transfer switch. (See Figure 1 for the emergency transfer switch location.)

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT C TSC EMERGENCY POWER SUPPLY Page 2 of 4 1.3 Narrative Description 1.3.1 The small 225 kV diesel generator, which supplies backup power to the gas turbine auxiliary loads, has the capability of supplying an alternate source of power to the TSC via 480 V breaker (52T) located in the southwest comer of the gas turbine building. Control power is directly from the output of the auxiliary diesel generator. However, Breaker 52T close-open (maintained position) control switch is only electrically in the circuit when the auto/manual selector switch is in the manual position.

1.3.2 The TSC's normal (1B-01) and alternate (52T) power supplies are connected on El. 18.5' of the TSC, via normal manual fused disconnects, to a normal seeking auto bus transfer (ABT) switch. Upon sensing an undervoltage on the TSC's normal feeder (1B-01) for one second, the electronics within the ABT energize relay 52TX off the 24 Vdc TSC emergency lighting batteries via a 10 amp fuse located within the battery enclosure. Energizing the 52TX relay starts the diesel generator and with selector switch in auto, allows closure of alternate breaker 52T as soon as sufficient voltage is present on the output of the generator unless G05 auxiliaries have taken priority (52E emergency supply closed and/or G05 auxiliary bus undervoltage). The closing of breaker 52T establishes voltage on the alternate feeder, and the ABT switches to the alternate supply; this connects the TSC loads to the diesel generator.

Subsequently, when voltage is restored to the TSC normal feeder for 30 minutes to assure stability, the ABT shifts to the "preferred" normal supply. This action activates a 5-minute time delay relay. The diesel generator continues to operate until the 5 minutes expire, whereupon relay 52TX deenergizes, opening alternate supply breaker (52T) and shutting down the diesel engine.

1.3.3 Apparently all time delays associated with this system are generated by the electronics package located within the auto bus transfer (ABT) switch.

Relay 52TX is located just above and to the left of the TSC heating and ventilating control air compressors, also on El. 18.5'. The TSC emergency lighting batteries are located adjacent to the manual fused disconnect of the alternate supply to the ABT.

1.3.4 The control logic on breaker closure is arranged such that the need for the diesel to supply gas turbine auxiliaries has priority over the need to supply the TSC loads. This is true so long as the auto/manual selector switch on the original breaker control panel (in the G05 building) is left in the "AUTO" position.

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT C TSC EMERGENCY POWER SUPPLY Page 3 of 4 2.0 OPERATION 2.1 With the diesel generator supplying the G05 auxiliaries should it be discovered that G05 is inoperable, and it is deemed necessary to supply the TSC with emergency power, complete Steps 2. 1.1 through 2.1.4 IN ORDER:

CAUTION With the diesel generator in operation (voltage present), breaker 52T will operate to its control switch "maintained position" (close or open) coincident with placing the auto/manual selector switch to manual.

CAUTION No generator overload protection is provided to trip open breaker 52T.

However, it does have breaker thermal and magnetic overcurrent trips.

CAUTION In the manual mode it is possible to operate both breaker 52E and 52T to the closed position. If the normal feed to the TSC is deenergized, this could result in an abrupt overload of the diesel generator with no automatic tripping of either output breaker (the 480 V supply to breaker 52T is taken off upstream of the overload protection which trips breaker 52E) unless all G05 auxiliary 480 VAC loads are stripped except for P105, the fuel oil transfer pump. This stripping should only be done if it is obvious that G05 will remain inoperable for a relatively long period.

2.1.1 Place 52T control switch to OPEN position.

2.1.2 The auto/manual selector switch must be placed to MANUAL.

2.1.3 Breaker (52E) to G05 auxiliaries, OPENED locally via its control switch.

2.1.4 Breaker (52T) TSC loads, CLOSED locally via its control switch.

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT C TSC EMERGENCY POWER SUPPLY Page 4 of 4 2.2 It should be realized that so long as an undervoltage condition exists on the G05 auxiliaries the fuel oil transfer pump (P105) is inoperable. The diesel generator fuel tank limits operation to approximately three hours at full TSC load. It is recommended that you attempt to fill the fuel oil tank utilizing the static head provided by the fuel oil storage tanks. If this proves to be inadequate, placing the auto/manual selector switch to "AUTO" will energize the G05 auxiliaries but simultaneously deenergize the TSC. In the interim, should the normal supply to the G05 auxiliaries (H01 bus) be restored, breaker 52N should be manually closed to provide power to the fuel oil transfer pump in lieu of repositioning the auto manual transfer switch.

The fuel usage for the auxiliary diesel is a conservative estimate based on communications with the diesel manufacturer, operational experience and calculations provided by the system engineer.

Page 18 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING) AND PARTICULATE, IODINE AND NOBLE GAS (PING) RADIATION MONITORS Page 1 of 2 1.0 ACTIVATION 1.1 Technical Support Center 1.1.1 Install a new charcoal filter in the iodine and noble gas (ING) monitor.

1.1.2 Start the iodine and noble gas sample pump on the west side of the El. 18.5' mechanical equipment room.

1.1.3 Record the initial sample flow rate and start time.

Flow Rate Start Time '

1.2 North Service Building 1.2.1 Install a new air particulate and charcoal filter in the NSB PING.

1.2.2 Plug in the monitor and start the pump.

1.2.3 Record the initial sample flow rate and start time.

Flow Rate Start Time 2.0 INTERPRETATION OF RMS READOUTS 2.1 The concentration of noble gas is determined by multiplying the observed count rate on the readout labeled "RE-238" by the calibration constant posted adjacent to the meter.

The units are gCi/cc Xe-133 dose equivalents.

2.2 The iodine activity in the charcoal cartridge is determined by multiplying the observed count rate on the readout labeled "RE-237" by the calibration constant posted adjacent to the meter. The units are giCi 1-131 dose equivalents.

2.3 To convert the iodine activity into a concentration, calculate the volume of air that passed through the filter. The concentration of iodine is approximately the activity on the filter (tCi) divided by the total volume (cm 3) for sampling periods less than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months assuming no short-lived isotopes are present.

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POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING) AND PARTICULATE, IODINE AND NOBLE GAS (PING) RADIATION MONITORS Page 2 of 2 NOTE: For longer sampling periods and when short-lived isotopes are expected to be present, the following formula may be used to calculate the iodine concentration.

C= (2XAe"j)t, Vol f (I- e-Xt,)

Where: Units C = concentration in air tCi/cc Vol = sample volume cc

= decay constant, 0.693/T 1/2 min" A = total activity on filter aCi t = elapsed time from sample stop to count start min t = total sample time min f = filter collection efficiency 2.4 Any changes to the alarm setpoints shall be made in accordance with the Radiation Monitoring System Alarm Setpoint & Response Book (RMSASRB).

Page 20 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT E DELETED - MOVED TO EPIP 1.1 Page 21 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT F DELETED - MOVED TO EPIP 1.3 Page 22 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT G PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page I of 8 NOTE 1: Use PPCS terminal drops 121 (TSC) and 125 (EOF) to display the plant status board.

NOTE 2: Use PPCS terminal drops 122 (TSC) and 126 (EOF) to display the rad/met status board.

NOTE 3: If the PPCS workstation is inoperable, you can access PPCS data on a LAN computer per EPIP 4.3, Attachment H, Activation of the Remote PPCS Wave Application.

1.0 PPCS START UP (applies to all PPCS monitor drops) 1.1 Turn on the monitors, if not already on.

1.2 Check if the affected unit is selected. PB 1@PPCS or PB2@PPCS displayed in the lower right hand corner of screen.

1.3 IF the affected unit is selected,

-THEN go to Step 1.13 NOTE: The computer reboots when changing between units.

1.4 IF the affected unit is not selected on the PPCS screen, TH-EN obtain the PPCS user name and password from the envelope in the sealed facility storage cabinet.

1.5 Select the arrow above the menu icon and left click to bring up the WDPF Main Menu.

1.6 Click on the user/login menu:

NOTE 1: The user name and password are case sensitive (i.e. make sure Cap Locks is off).

NOTE 2: If multiple attempts to enter the user/login password fail, the system will lock out the drop for approximately 15 minutes before allowing a login to occur.

1.7 Enter the user name and password.

1.8 Left click on login.

1.9 Click on PB I @PPCS or PB2@PPCS in the lower right corner to bring up the "Change Unit" window.

Page 23 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT G PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 2 of 8 1.10 Click on the desired unit, PBl @PPCS or PB2@PPCS, in the "Change Unit" window pull down menu.

-1.11 Click on "OK."

1.12 Click on "OK" in response to the "Change Unit Warning."

NOTE: You do not need to select "acknowledge" for the shutdown and reboot to occur.

1.13 Turn on the overhead projector by depressing the power (0/I) switch at the front of the unit.

2.0 DISPLAY OF PPCS DATA 2.1 To display the Plant Status Board (PSB), go to Step 2.1.1, OR to display the Rad/Met Status Board proceed to step 2.2 2.1.1 Select window number (W I) from the menu bar.

NOTE: The DIRECTORY screen provides a display of all the screens available to the PPCS user.

2.1.2 Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

2.1.3 Click on the Plant Status Board button under Miscellaneous (2225 for Unit 1 or 2725 for Unit 2) in the DIRECTORY window.

NOTE: If unable to view the menu bar, move the cursor to the very bottom of the screen and click, downsize the displayed window, or move the displayed window to the back of the desktop.

2.1.4 Select window number (W5) from the menu bar. This selects the window for the projected image.

2.1.5 To display the Plant Status Board screen with the projector:

a. Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

Page 24 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION G k,._.iATTACHMENT PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 3 of 8

b. Move the mouse to the far right (off the monitor screen and onto the projected screen) and click on the Plant Status Board button under Miscellaneous (2225 for Unit 1 or 2725 for Unit 2) from the DIRECTORY window.

2.1.6 Go to Step 2.3 to manually enter data onto the projected screen and to Step 2.4 to trend plant data.

2.2 Displaying the Rad/Met Status Board 2.2.1 Select window number (WI) from the menu bar.

NOTE: The DIRECTORY screen provides a display of all the screens available to the PPCS user.

2.2.2 Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

2.2.3 Click on the Rad/Met button under Miscellaneous (2226 for Unit 1 or 2726 for Unit 2) from the DIRECTORY window.

NOTE: If unable to view the menu bar, move the cursor to the very bottom of the screen and click, downsize the displayed window, or move the displayed Window to the back of the desktop.

2.2.4 Select window number (W5) from the menu bar. This selects the window for the projected image.

2.2.5 To display the Rad/Met Status Board screen with the projector:

a. Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

b. Move the mouse to the far right (off the monitor screen and onto the projected screen) and Click on the Rad/Met Status Board button under Miscellaneous (2226 for Unit 1 or 2726 for Unit 2) from the DIRECTORY window.

2.2.6 Go to Step 2.3 to manually enter data onto the projected screen and to Step 2.5 to trend Radiation Monitoring System (RMS) data.

Page 25 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT G PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 4 of 8 2.3 Manual Entry of Data Fields 2.3.1 Move the mouse to the far right (off the monitor screen and onto the projected screen).

2.3.2 Click on the desired blue outlined block(s) to select the area for data or information entry.

NOTE: Use capital letters to increase the readability of the projected image.

2.3.3 Type the data or information to be displayed.

2.3.4 After updating the status board, print the applicable PPCS window in accordance with Step 3.0.

NOTE: All trends are viewed on the drop's monitor, not the projected image.

2.4 View and Trend Plant Status Data 2.4.1 Ensure a different window number W-2, W-3, or W-4 is selected.

2.4.2 Click on the plant system to be viewed or trended from the DIRECTORY screen.

2.4.3 Move the cursor to the desired data point (e.g. temperature, pressure).

2.4.4 Right click to bring up the menu window.

2.4.5 Left click on the menu option desired (Information or Mini-Trend). The information or trend will be displayed on the monitor screen.

2.4.6 If desired, groups or selected data points may be displayed by using the Trend Group Attribute Window by performing the following:

a. Left click on the Graphics icon on the lower tool bar to bring up the "Trend Display" window.

Page 26 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT G PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 5 of 8

b. Click on "Create."

c. Click on "Live Trend."

d. Click on "Modify Properties" to bring up the "Group Attributes Window."

e. To display a group, click on "Copy from Group" and perform Steps 2.4.6.f-g. If an individual data point is desired to be trended go directly to Step 2.4.6 h.

f. Click on the group you wish to trend from the Group listing in the "Select a Group" window.

g. Click "Apply", which closes the Select a Group window and then go to Step 2.4.6 1.

h. To display an individual point, click on "Add Point" on the Group Attribute Window.

NOTE 1: Up to eight (8) data points may be trended in each Trend Display Window.

NOTE 2: The point names may be found on the group listing as described in Step 2.4.6 f above. A list of Point Names is also available on an operator aid at the Plant Status Board work areas.

i. Enter the point name (e.g. LT972 or 1RE21 1).

j. Click on "OK."

k. Continue to add points by repeating Steps 2.4.6 h. -j.

1. Select and change the live time interval, if desired.

m. Change the graph scales, if desired, by performing the following:

"* Click on the point you which to change the scale.

"* Click on modify.

Page 27 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (ISC) January 3, 2003 ACTIVATION AND EVACUATION G S~ATTACHMENT PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 6 of 8

"* Click on "Default" in Scale Limits

"* Select "User Entered" from menu

"* Select linear or logrithmic scale

"* Enter the High scale value in the High block

"* Enter the Low scale value in the Low block

Click on "OK".

n. Click on "Apply." The graph will appear and display the information.

2.5 View and Trend Radiation Monitoring System (RMS) Data.

2.5.1 Ensure a different window number W-2,W-3, or W-4 is selected and then click on the RMS grid icon (2260 for Unit I and 2760 for Unit 2) from the DIRECTORY. The RMS Grid should be displayed.

2.5.2 Move the cursor to the desired RMS monitor number to be viewed or trended on the RMS Grid.

2.5.3 Right click to bring up the menu window.

2.5.4 Left click on the menu option desired (Information or Mini-Trend). The information or trend will be displayed on the monitor screen.

2.5.5 If desired, selected RMS points may be displayed by using the Trend Group Attribute window by performing Step 2.4.6.

2.5.6 To view the RMS history bar graph trends (last 24-1 minute periods, 24-10 minute periods, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or 24 days) click on the box in front of the desired RMS monitor.

Page 28 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION K_ ATTACHMENT G PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 7 of 8 3.0 PRINTING PPCS SCREENS 3.1 If the background area behind the windows is not exposed, reduce the window size slightly.

NOTE: A screen printout may be obtained by following Step 3.2. Select "Print Screen" instead of "Snapshot." No further actions are needed and the printout is routed automatically to the color printer.

3.2 With the cursor over the background area, hold down the right mouse button and scroll down until "Snapshot" is highlighted, then release the right button.

3.3 In the SNAPSHOT window, select HIDE WINDOW DURING CAPTURE and then click on the SNAP button. "Select Window" will appear on the bottom of the window.

NOTE: It takes approximately 5-8'seconds for the snapshot to be recorded. If you do not left click on the window desired within approximately 8 seconds after "Select K,_ window" is displayed, the snap process will stop.

3.4 Within 5 seconds of clicking on the SNAP button, left click on the window you desire to print. "Snap Succeeded" will appear on the bottom of the snapshot window after 5-8 seconds.

3.5 Click on "View" in the SNAPSHOT window. The Image Tool (V3.6FCS) window will appear and display the captured window.

3.6 Click on File>Print Preview on the Image Tool (V3.6FCS) window to preview the image to be printed. Do not confuse this with the Image Tool: Palette, which is not used and may be closed, if desired.

3.7 Click on File>Print on the Image Tool (V3.6FCS) window to display the tools used to modify the size and orientation of the print image.

3.8 Make adjustments to the orientation and size of the printed image:

3.8.1 Select the orientation (landscape or portrait).

3.8.2 Scale the size of the image using the slider or AV buttons, while viewing the image on the Image Tool Print Preview window.

Page 29 of 30 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.1 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 34 TECHNICAL SUPPORT CENTER (TSC) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT G PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 8 of 8 3.9 When in the TSC, select:

3.9.1 TSCLJ to print black and white.

3.9.2 TSCSC to print color.

3.10 When in the EOF, select:

3.10.1 SBCLJ to print black and white.

3.10.2 SBCSC to print color.

3.11 Click on "Print" in the Print or Print Preview window to print the selected screen.

3.12 IF the printer fails to print in the TSC, THEN check the ethernet switches on TSC-T on the rack in the Southwest corner wall rack are plugged in.

3.13 IF the printer fails to print in the EOF, THEN contact security to open the door to the Switch Room in the SBCC and check the ethernet switches on SBC-T are plugged in.

Page 30 of 30 REFERENCE USE

EPIP 4.2 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION AND EVACUATION DOCUMENT TYPE: Technical CLASSIFICATION: NNSR REVISION: 16 EFFECTIVE DATE: January 3, 2003 REVIEWER: N/A APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Emergency Preparedness Supervisor OWNER GROUP: Emergency Preparedness Verified Current Copy:

Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT EPIP 4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 16 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION January 3, 2003 AND EVACUATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE ...................................................................................................................... 3 2.0 PREREQUISITES .............................................................. ;........................................... 3 3.0 PRECAUTIONS AND LIMITATIONS ................................................................... 4 4.0 INITIAL CONDITIONS ............................................................................................ 4 5.0 PROCEDURE ................................................................................................................ 5 5.1 Activation ....................................................................................................................... 5 5.2 Evacuation ..................................................................................................................... 5

6.0 REFERENCES

...................................................................................................... 6 7.0 BASES ........................................................................................................................... 6 ATTACHMENT A OPERATIONS SUPPORT CENTER LAYOUT ............................................. 7 Page 2 of 7 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 16 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION January 3, 2003 AND EVACUATION 1.0 PURPOSE This procedure provides instructions for the activation of the Operations Support Center (OSC).

The OSC is activated upon declaration of an ALERT or higher classification, or at any other time deemed necessary by the SM. Activation of the OSC does not require the declaration of an emergency. Attachment A, Operation Support Center Layout, describes the facility layout.

This procedure also describes the evacuation of the OSC, which will be done in unison with the TSC.

2.0 PREREQUISITES 2.1 Responsibilities 2.1.1 Reentry Team Coordinator:

a. Activation and oversight of the OSC activities and reentry team dispatch (repair, fire, search and rescue), including non-PBNP or contractor teams per EPIP 10.1, Emergency Reentry.

b. Tracking reentry teams previously dispatched from the Control Room prior to OSC activation.

c. Medical emergencies per EPIP 11.2, Medical Emergency.

2.1.2 Operations Leader:

a. OSC activation prior to the arrival of the Reentry Team Coordinator.

b. Supervises the operations reentry teams.

2.1.3 Radiation Protection (RP) Leader - Supervises onsite radiation protection tasks and briefs/debriefs reentry teams on radiological concerns.

2.1.4 Instrumentation and Control (I&C) Leader - Supervises I&C reentry teams.

2.1.5 Mechanical Leader - Supervises mechanical reentry teams.

2.1.6 Electrical Leader - Supervises electrical reentry teams.

2.1.7 Chemistry Leader - Supervises chemistry reentry teams.

2.1.8 Team Lead - Reentry team member assigned-to direct reentry team response during dispatch.

2.1.9 TSC Manager - Decision to evacuate the OSC and relocate to alternate areas.

Page 3 of 7 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 16 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION January 3, 2003 AND EVACUATION 2.2 Equipment 2.2.1 OSC Inventory

a. EPMP 1.1, Routine Check, Maintenance, Calibration and Inventory Schedule for Radiation Protection Emergency Preparedness Equipment

b. EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies 2.2.2 Communications equipment per EPMP 2.1, Testing of Communications Equipment 2.2.3 Other equipment determined necessary to support the event (i.e., Maintenance, Radiation Protection, Radiochemical, etc.)

3.0 PRECAUTIONS AND LIMITATIONS Until the OSC is activated and formally assumes responsibility for teams, the SM maintains responsibility for reentry teams.

4.0 INITIAL CONDITIONS 4.1 Declaration of an ALERT or higher classification or in conjunction with the Technical Support Center (TSC) if it is deemed necessary to support plant operations.

4.2 Evacuation of the TSC and OSC shall be considered when any of the following conditions exist:

4.2.1 Emergency response personnel radiation doses in the TSC/OSC are exceeding or are projected to exceed the following for the duration of the event:

a. Whole body (TEDE) 4 rem (calculated)

b. Thyroid (CDE) 25 rem (calculated) 4.2.2 Other emergency conditions (e.g., fire, toxic or flammable gases, or loss of power).

Page 4 of 7 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 16 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION January 3, 2003 AND EVACUATION 5.0 PROCEDURE 5.1 Activation 5.1.1 The Reentry Team Coordinator shall ensure the completion of the OSC Position Instruction Manual, OSC 3.1, Reentry Team Coordinator.

NOTE: The facility may be activated earlier based upon the Reentry Team Coordinator's discretion if determined there is an understanding of the events in progress and adequate stalling resources in place to respond to the emergency.

5.1.2 Minimum staff position in the OSC are:

a. Reentry Team Coordinator

b. Operations Leader

c. I&C Leader

d. Mechanical Leader or Electrical Leader

e. RP Leader

f. Chemistry Leader 5.1.3 Each ERO position shall activate and assume their area of responsibility and function within the OSC using their Position Instruction Manual.

5.2 Evacuation 5.2.1 The OSC will be evacuated in accordance with EPIP 4.1, Technical Support Center (TSC) Activation and Evacuation, under the direction of the TSC Manager and coordinated with the Reentry Team Coordinator.

5.2.2 The key to an orderly evacuation is good communications, conducing a formal turnover with personnel assuming OSC responsibilities, and documentation of actions.

5.2.3 The Control Room will take responsibility for in-plant teams until the relocation area is functional.

5.2.4 Ensure all personnel are accounted for after reaching the relocation area(s).

Page 5 of 7 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 16 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION January 3, 2003 AND EVACUATION

6.0 REFERENCES

6.1 Point Beach Nuclear Plant Emergency Plan 6.2 EPIP 4.1, Technical Support Center (TSC) Activation and Evacuation 6.3 EPIP 10.1, Emergency Reentry 6.4 EPIP 11.2, Medical Emergency 6.5 EPMP 1.1, Routine Check, Maintenance, Calibration and Inventory Schedule for Radiation Protection Emergency Preparedness Equipment 6.6 EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies 6.7 PIM OSC 3.1, Reentry Team Coordinator 6.8 PIM OSC 3.2, Radiation Protection Leader 6.9 PIM OSC 3.3, I&C Leader 6.10 PIM OSC 3.4, Mechanical Leader 6.11 PIM OSC 3.5, Electrical Leader 6.12 PIM OSC 3.6, Chemistry Leader 6.13 PIM OSC 3.7, Operations Leader 6.14 PIM TSC 2.1, TSC Manager 7.0 BASES B-1 10 CFR 50.47(b), Emergency Plans B-2 10 CFR 50.47, Appendix E.IV, Content of Emergency Plans B-3 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Response Plans and Preparedness in Support of Nuclear Power Plants B-4 NUREG-0737, Clarification of TMI Action Plan Requirements Page 6 of 7 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 16 OPERATIONS SUPPORT CENTER (OSC) ACTIVATION January 3, 2003 AND EVACUATION ATTACHMENT A OPERATIONS SUPPORT CENTER LAYOUT I

Page 7 of 7 REFERENCE USE

EPIP 4.3 EMERGENCY OPERATIONS FACILITY (EOF) ACTIVATION AND EVACUATION DOCUMENT TYPE: Technical CLASSIFICATION: NNSR REVISION: 28 EFFECTIVE DATE: January 3, 2003 REVIEWER: N/A APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Emergency Preparedness Verified Current Copy:

Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PU R PO SE ....................................................................................................................... 3 2.0 PREREQUISITES ........................................................................... 3 3.0 PRECAUTIONS AND LIMITATIONS ................................................................... 5 4.0 INITIAL CONDITIONS ............................................................................................ 5 5.0 PROCEDURE ........................................................................................................ 6 5.1 A ctivation ....................................................................................................................... 6 5.2 Evacuation ...................................................................................................................... 7

6.0 REFERENCES

...................................................................................................... 7 7.0 B A SE S ........................................................................................................................... 8 K, ATTACHMENT A EMERGENCY OPERATIONS FACILITY LAYOUT ................................. 9 ATTACHMENT B OPERATION OF THE EOF EMERGENCY VENTILATION SYSTEM &

ANNUNCIATOR PANEL ............................................................................ 10 ATTACHMENT C DELETED - MOVED TO EPIP 1.3 ............................................................... 12 ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING)

RADIATION MONITORS ........................................................................... 13 ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS) .................. 15 ATTACHMENT F WPS - KNPP SITE BOUNDARY FACILITY ............................................ 23 ATTACHMENT G ALTERNATE EMERGENCY OPERATIONS FACILITY (AEOF) 700 NORTH ADAMS STREET, GREEN BAY ........................................... 24 ATTACHMENT H ACTIVATION OF THE REMOTE PPCS WAVE APPLICATION ............. 26 Page 2 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION 1.0 PURPOSE This procedure provides instructions for the activation of the Emergency Operations Facility (EOF). The EOF is activated upon declaration of an ALERT, or higher classification, or at any other time deemed necessary by the Shift Manager (SM). Activation of the EOF does not require the declaration of an emergency. Attachment A, Emergency Operations Facility Layout, describes the facility layout.

This procedure also describes the method by which the EOF and Offsite Radiation Protection Facility (OSRPF) is evacuated and responsibilities transferred.

2.0 PREREQUISITES 2.1 Responsibilities 2.1.1 Emergency Director:

a. Directs the overall management of the emergency response and recovery operations, including requests for federal assistance.

b. Upon activation of the EOF, assumes a formal turnover from the SM for non-delegable responsibilities, including:

"* Classification/Re-classification of emergencies

"* Protective Action Recommendations

"* Notification of Federal, State, and County authorities 0 Authorizing the use of potassium iodide

"* Authorizing emergency radiation dose extensions

c. Decision to evacuate the EOF and OSRPF and relocate to alternate areas.

2.1.2 EOF Manager:

a. EOF activation prior to the arrival of the Emergency Director.

b. Commands and controls the EOF emergency response activities.

Page 3 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003

._ ACTIVATION AND EVACUATION 2.1.3 Dose/PAR Coordinator:

a. Directs the Offsite Radiation Protection Facility Coordinator to activate the EOF emergency ventilation system per Attachment B, Operation of the EOF Emergency Ventilation System & Annunciator Panel.

b. Activates the Wisconsin Electric Dose Assessment Program - WEDAP per EPIP 1.3, Dose Assessment and Protective Action Recommendations.

c. Initiates the activation of the Iodine and Noble Gas (ING) Monitors per Attachment D, Activation of the Iodine and Noble Gas (ING) Radiation Monitors.

d. Directs offsite dose assessment. Develops Protective Action Recommendations (PARs) based on dose for the Emergency Director's approval.

2.1.4 Plant Status Monitor:

a. Activates Plant Process Computer System (PPCS) workstation per K>Attachment 1, Plant Process Computer System (PPCS).

b. Supports event monitoring by serving as the resource for plant and environmental data. Maintains plant status boards.

2.1.5 ERF Communicator - Maintains continuous communications between the CR, TSC, EOF and JPIC. Assists with event classification.

2.1.6 Dose/PAR Monitor - Supports radiological response by serving as resource for offsite assessment of radiological conditions and assists with development of Protective Action Recommendations (PARs) based on dose. Maintains rad/met status boards.

2.1.7 HPN/SRC Communicator - Communicates information to NRC and State of Wisconsin Department of Health and Family Services - State Radiological Coordinator.

2.1.8 State/County Communicator - Communicates information to State and County agencies.

2.1.9 State Liaison - Ensures that the State of Wisconsin has adequate information to implement offsite emergency plans. Reports to the State Emergency Operations Center.

Page 4 of -27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION 2.1.10 County Liaison - Ensures that Kewaunee County and Manitowoc County has adequate information to implement offsite emergency plans. Reports to the County Emergency Operation Centers.

2.1.11 Resource Coordinator - Obtains resources needed for emergency response, including communications with supporting agencies.

2.1.12 Offsite Assembly Area Coordinator - Assists the Security Coordinator in controlling site ingress/egress, including release and/or evacuation of personnel to offsite assembly areas.

2.1.13 Administrative Support Leader - Provides clerical and administrative support to emergency organization.

2.2 Equipment 2.2.1 EOF inventory per EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies.

2.2.2 PPCS Workstations 2.2.3 WEDAP Workstation 2.2.4 Communications equipment per EPMP 2.1, Testing of Communications Equipment.

3.0 PRECAUTIONS AND LIMITATIONS Evacuation of the EOF shall include the coordination of the evacuation for the OSRPF.

4.0 INITIAL CONDITIONS 4.1 This procedure shall be implemented upon declaration of an ALERT or higher classification or at the discretion of the Shift Manager to provide the Control Room support with offsite interfaces.

4.2 Evacuation of the EOF and OSRPF shall be completed when any of the following conditions exist.

4.2.1 Emergency response personnel radiation doses in the EOF/OSRPF are exceeding or are projected to exceed the following for the duration of the event:

a. Whole body (TEDE) 4 rem (calculated)

b. Thyroid (CDE) 25 rem (calculated)

Page 5 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 NNSR EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 28 January 3, 2003 EMERGENCY OPERATIONS FACILITY (EOF)

ACTIVATION AND EVACUATION 4.2.2 Other emergency conditions exist (i.e., fire, toxic or flammable gases, or loss of power).

5.0 PROCEDURE 5.1 Activation 5.1.1 The EOF Manager shall ensure the completion of the EOF Position Instruction Manual 4.2, EOF Manager.

NOTE: The facility may be activated earlier based upon the EOF Manager's discretion if determined there is an understanding of the events in progress and adequate staffmg resources in place to respond to the emergency.

5.1.2 Minimum staff positions are:

a. Emergency Director

b. EOF Manager

c. Dose/PAR Coordinator

d. State/Counties Communicator

e. ERF Communicator

f. OSRPF Coordinator

g. Resource Coordinator 5.1.3 The EOF emergency ventilation system, iodine and noble gas (ING) radiation monitors, and PPCS equipment shall be activated per the attachments to this procedure.

5.1.4 Each ERO position shall activate and assume their area of responsibility and function within the EOF using their Position Instruction Manual.

Page 6 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION 5.2 Evacuation 5.2.1 The EOF and OSRPF will be evacuated under the direction of the EOF Manager.

5.2.2 The key to an orderly evacuation is good communications, formal turnover with personnel assuming EOF and OSRPF responsibilities, and documentation of actions and notifications.

5.2.3 Minimize the number of vehicles used to transport people and equipment to other facilities.

a. The Alternate Offsite Radiation Protection Facility is the.KNPP Site Boundary Facility (SBF) located about one mile west of KNPP on Kewaunee County Nuclear Road per Attachment F, WPS - KNPP Site Boundary Facility.

b. The Alternate EOF (AEOF) is located in the Wisconsin Public Service corporate office at 700 North Adams Street, Green Bay, WI in Room D2-3 (per Attachment G, AEOF - Green Bay). Data from the PPCS is obtained per Attachment H, Activation Of The Remote PPCS WAVE Application.

5.2.4 Transfer responsibility for all communications to the TSC until the AEOF is activated. Some communicators may temporarily relocate to that facility prior to activation of the AEOF.

5.2.5 Transfer responsibility for the OSRPF oversight and offsite dose assessments for protective action recommendations to the TSC.

5.2.6 Ensure all personnel are accounted for after reaching the relocation area(s).

5.2.7 Activate the AEOF by each ERO position reassuming their area of responsibility and function using their Position Instruction Manual.

5.2.8 Develop an immediate plan for reentry of the EOF/OSRPF area, if possible.

6.0 REFERENCES

6.1 Point Beach Nuclear Plant Emergency Plan 6.2 EPIP 1.3, Dose Assessment and Protective Action Recommendations 6.3 EPIP 4.7, Offsite Radiation Protection Facility (OSRPF) Activation and Evacuation Page 7 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION 6.4 EPMP 1.3, Routine Inventory of TSC, EOF, AEOF, JPIC and OSC Emergency Preparedness Supplies 6.5 EPMP 2.1, Testing of Communications Equipment 6.6 PIM EOF 4.1, Emergency Director 6.7 PIM EOF 4.2, EOF Manager 6.8 PIM EOF 4.3, Administrative Support Leader 6.9 PIM EOF 4.4, Resource Coordinator 6.10 PIM EOF 4.5, Dose/PAR Coordinator 6.11 PIM EOF 4.6, Dose/PAR Monitor 6.12 PIM EOF 4.7, HPN/SRC Communicator 6.13 PIM EOF 4.10, State/County Communicator 6.14 PIM EOF 4.11, State Liaison 6.15 PIM EOF 4.12, County Liaison 6.16 PIM EOF 4.13, Offsite Assembly Area Coordinator 6.17 PIM EOF 4.14, ERF Communicator 6.18 PIM EOF 4.15, Plant Status Monitor 7.0 BASE5 B-1 10 CFR 50.47(b), Emergency Plans B-2 10 CFR 50.47, Appendix E. IV, Content of Emergency Plans B-3 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Response Plans and Preparedness in Support of Nuclear Power Plants B-4 NUREG-0737, Clarification of TMI Action Plan Requirements B-5 Calculation 2002-0017, RE-242 High Alarm Setpoint Analysis, 8/19/02 B-6 CA025588, SBCC RMS Alarms Page 8 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT A EMERGENCY OPERATIONS FACILITY LAYOUT OSRPF Page 9 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EOF EMERGENCY VENTILATION SYSTEM & ANNUNCIATOR PANEL Page 1 of 2 NOTE: Contact the Control Room prior to implementing this procedure to advise them of the RMS alarm they will be receiving.

1.0 DESCRIPTION

- EMERGENCY VENTILATION SYSTEM The EOF's emergency ventilation system has a normal and emergency operation mode. Under all modes of operation, fresh air is taken in from the vent on the south end of the west side of the building. Under normal conditions the air is filtered by roughing and electrostatic filters. In the emergency mode, a minimum amount of outside air is taken into the building and incoming air is routed through an additional high efficiency particulate filter.

2.0 EMERGENCY OPERATION OF THE EMERGENCY VENTILATION SYSTEM 2.1 The control panel for the SBCC ventilation system (Ml) is located in the mechanical equipment room. Access to the mechanical equipment room is through the men's restroom and locker area.

2.2 To shift from the normal to the emergency mode, manually place the switch S3 on panel M l to the "Emergency" position.

3.0 EMERGENCY OPERATIONS POWER SUPPLY Electrical power to the Site Boundary Control Center, and therefore the EOF, is provided by Wisconsin Public Service Corporation (WPSC) via a distribution feeder. In case of loss of electrical power, call WPSC. The telephone number for WPSC can be found in the Emergency Telephone Directory.

4.0 DESCRIPTION

- EOF ANNUNCIATOR PANEL 4.1 The EOFs annunciator panel monitors eight parameters in the Site Boundary Control Center building. The control room may receive a common alarm upon annunciation of some of the eight alarms.

4.1.1 Holding tank high level - alarms on high level, holding tank must be pumped by a contractor.

4.1.2 Dosing tank high level - alarms on high level.

4.1.3 Fire detector - annunciates upon detection of a fire.

4.1.4 Emergency mode - annunciates when building HVAC system is switched to the emergency mode.

Page 10 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT B OPERATION OF THE EOF EMERGENCY VENTILATION SYSTEM & ANNUNCIATOR PANEL Page 2 of 2 4.1.5 Building temperature low - annunciates upon exceeding the setpoint for the building temperature. This usually indicates a heating system failure.

4.1.6 Pump failure - annunciates whenever a pump associated with control panel M I, does not start on demand, after a 30-second time delay.

4.1.7 Air filter plugged - annunciates when the electrostatic air filter is plugged and the differential pressure across the filter exceeds the setpoint.

4.1.8 Compressed air low pressure - annunciates when the air pressiire in the supply header to the Johnson Controls control system falls below the setpoint.

4.2 Response to annunciator panel alarms.

4.2.1 Be prepared to respond to the Control Room questions regarding the cause of the alarm.

4.2.2 Take actions and/or call for the assistance as required.

Page I11 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 NNSR EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision 28 January 3, 2003 EMERGENCY OPERATIONS FACILITY (EOF)

ACTIVATION AND EVACUATION ATTACHMENT C DELETED - MOVED TO EPIP 1.3 Page 12 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING) RADIATION MONITORS Page 1 of 2 Coordinate with the Offsite Radiation Protection Coordinator:

1.0 ACTIVATION 1.1 Install a new charcoal filter in the Iodine and Noble Gas Monitor.

1.2 Start the iodine and noble gas sample pump in the heating and ventilation room adjacent to the men's lavatory.

1.3 Record the initial sample flow rate and start time.

Flow Rate Start Time 2.0 INTERPRETATION OF RMS READOUTS 2.1 The concentration of noble gas is determined by multiplying the observed count rate on the readout labeled "RE-242" by the calibration constant posted adjacent to the meter.

The resulting units are j+/-Ci/cc Xe-133 dose equivalents.

2.2 The iodine activity on the charcoal cartridge is obtained by multiplying the observed count rate on the readout labeled "RE-241" by the calibration constant posted adjacent to the meter. The resulting units are tCi 131 dose equivalents.

2.3 Calculation 2002-0017 determined for RE-242 under LOCA accident conditions that each interval of 5000 cpm on the meter readout corresponds to a submersion dose rate of 100 mrem/hour in the environs outside the SBCC. (B-5) (B-6)

Page 13 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT D ACTIVATION OF THE IODINE AND NOBLE GAS (ING) RADIATION MONITORS Page 2 of 2 2.4 To convert the iodine activity into a concentration, calculate the volume of air that passed through the filter. The concentration of iodine is approximately the activity on the filter (gCi) divided by the total volume (cm 3) for sampling periods less than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , this assumes no short-lived isotopes are present.

NOTE: For longer sampling periods and when short-lived iodine isotopes are expected to be present, the following formula may be used to calculate the iodine concentration:

C= (XAet)ts F v(1-e-Xts)

Where: Units C = concentration in air tCi/cc F - sample volume cc min'i X - decay constant, 0.693T1/ 2 A - total activity on filter tCi t = elapsed time from sample stop to count start min ts = total sample time min p = filter collection efficiency Any changes to the alarm setpoints shall be made in accordance with the Radiation Monitoring System Alarm Setpoint & Response Book (RMSASRB) kept in the Control Room.

Page 14 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 1 of 8 NOTE 1: Use PPCS terminal drops 121 (TSC) and 125 (EOF) to display the plant status board.

NOTE 2: Use PPCS terminal drops 122 (TSC) and 126 (EOF) to display the rad/met status board.

NOTE 3: If the PPCS workstation is inoperable, you can access PPCS data on a LAN computer per EPIP 4.3, Attachment H, Activation of the Remote PPCS Wave Application.

1.0 PPCS START UP (applies to all PPCS monitor drops) 1.1 Turn on the monitors, if not already on.

1.2 Check if the affected unit is selected. PB1 @PPCS or PB2@PPCS displayed in the lower right hand corner of screen.

1.3 IF the affected unit is selected, THEN go to Step 1.13 NOTE: The computer reboots when changing between units.

1.4 IF the affected unit is not selected on the PPCS screen, THEN obtain the PPCS user name and password from the envelope in the sealed facility storage cabinet.

1.5 Select the arrow above the menu icon and left click to bring up the WDPF Main Menu.

1.6 Click on the user/login menu:

NOTE 1: The user name and password are case sensitive (i.e. make sure Cap Locks is off).

NOTE 2: If multiple attempts to enter the user/login password fail, the system will lock out the drop for approximately 15 minutes before allowing a login to occur.

1.7 Enter the user name and password.

1.8 Left click on login.

1.9 Click on PB 1@PPCS or PB2 @PPCS in the lower right corner to bring up the "Change Unit" window.

Page 15 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 2 of 8 1.10 Click on the desired unit, PBl @PPCS or PB2@PPCS, in the "Change Unit" window pull down menu.

1.11 Click on "OK."

1.12 Click on "OK" in response to the "Change Unit Warning."

NOTE: You do not need to select "acknowledge" for the shutdown and reboot to occur.

1.13 Turn on the overhead projector by depressing the power (O/I) switch at the front of the unit.

2.0 DISPLAY OF PPCS DATA 2.1 To display the Plant Status Board (PSB), go to Step 2.1.1, OR to display the Rad/Met Status Board proceed to step 2.2 2.1.1 Select window number (W 1) from the menu bar.

NOTE: The DIRECTORY screen provides a display of all the screens available to the PPCS user.

2.1.2 Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

2.1.3 Click on the Plant Status Board button under Miscellaneous (2225 for Unit 1 or 2725 for Unit 2) in the DIRECTORY window.

NOTE: If unable to view the menu bar, move the cursor to the very bottom of the screen and click, downsize the displayed window, or move the displayed window to the back of the desktop.

2.1.4 Select window number (W5) from the menu bar. This selects the window for the projected image.

2.1.5 To display the Plant Status Board screen with the projector:

a. Click the DIRECTORY icon at the bottom of the screen to bring up the DIRECTORY window.

Page 16 of 27 REFERENCE USE

POINT BEACH NUCLEAR PLANT EPIP 4.3 EMERGENCY PLAN IMPLEMENTING PROCEDURES NNSR Revision 28 EMERGENCY OPERATIONS FACILITY (EOF) January 3, 2003 ACTIVATION AND EVACUATION ATTACHMENT E PLANT PROCESS COMPUTER SYSTEM (PPCS)

Page 3 of 8

b. Move the mouse to the far right (off the monitor screen and onto the projected screen) and click on the Plant Status Board button under Miscellaneous (2225 for Unit 1 or 2725 for Unit 2) from the DIRECTORY window.

2.1.6 Go to Step 2.3 to manually enter data onto the projected screen and to Step 2.4 to trend plant data.

2.2 Displaying the Rad/Met Status Board 2.2.1 Select window number (W1) from the menu bar.