ML032521358

Plant Procedures Manual - Volume 13 Package No. 2003-603 - Editorial Changes

ML032521358
Person / Time
Site:	Columbia
Issue date:	08/27/2003
From:	Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032521358 (18)

Text

ENERGY e NORTHWEST People*Vislon*Solutions INTEROFFICE MEMORANDUM DATE: August 27, 2003 TO: Distribution FROM: Procedure Control, Administrative Services, (901A)

SUBJECr: PLANT PROCEDURES MANUAL - VOLUME 13 PACKAGE NO. 2003-603

REFERENCE:

I The following are EDITORIAL CIANGES, please replace the pages located in your manual with the attached pages: -  :

Procedure Rev Pae/s

- 7 11a [*e-,

i.

13.1.1 31 1,30 13.1.1A 11 1, 3, 8, 140, 146 13.8.1 23 1,2,5 -

13.10.1 25 1, 5 To verify receipt or cancellation of the subject Procedure(s), please sign, date and return this receipt to Procedure Control, MD 901A within TEN (10) WORKING DAYS of the date of this IOM.

Energy Northwest Procedure Control (Mail Drop 901A)

PO Box 968 Richland, WA 99352 Date Signature of Manual Holder -Controlled Copy Number Aot(;

102 R8

DISTRIBUTION - VOLUME 13 Control Copy Location Mail Drop 2 *Control Room (501) (IOM to CR5) 901A 3 *Shift Manager (501) 901A 5 Licensed Traing (PSF Rm. 249) 1050 6 *Simulator (PSF Rm. 235) 1050 12 PEC Library PEC 25 Bruce Bond 964F 26 Region IV, NRC 28 Region IV, NRC -

30 EOF Support Engineering Library 1050 31 *TSC Emergency Response 901A 35 NRC Resident Inspector -

52 State of Washington, Military Deparlment/Lamax -

55 Federal Emergency Mgmt. Agency 57 Benton County Dept of Emergency Mgmt.

58 *CGS Security (SAS-CR) (13.1.1, 13.4.1, 13.3.1, 13.5.3, 13.5., 13.10.8, 13.11.10, 13.12.19, 13.13.4) 901A 59 *CGS Security (CAS-AAP) (13.1.1, 13.4.1, 13.5.1, 13.3.3, 13.5.5, 13.10.8, 13.11.10, 13.12.19, 13.13.4) 901A 60 CGS Security 988A 63 Emergency Training PE30 64 *Radwaste Control Room (467) 901A 66 *Simlator, Shift Manager (PSF Rm. 235) 1050 68 *Remote Shutdown Room (467) (13.1.1, 13.2.1, 13.2.2, 13.4.1, 13.5.1, 13.10.1, 13.10.9) 901A 75 Dept. of Health Radiation Protection 78 *Control Room - (501) STA's Desk 901A 83 *MUDAC 1020 86 Siu la_-e - 1050 87 .oument Conrol DeskNR --

++90 *Joint Information Center (Keys) 901A 94 *EOF 1050 97 *EOF 1050 114 EP Manager PE30 127-130 (4) Licensed Training (Rms. 225, 247 or 248) 1050 132 Licensed Training (Mms. 225, 247 or 248) 1050 134-136 (3) *MUDAC Field Team Kits (13.9.1, 13.9.5, 13.9.8, 13.13.4, 13.14.4) 1050

++137 *MPF Field Team Kit (13.7.5, 13.9.1, 13.9.5, 13.9.8, 13.13.4,13.14.4) 901A 142 Hanford EOC/SMT 146 FEMA RX Liaison 155 *Maintenance Library (Memo to Veena) 901A 160 *OSC Emergency Support 901A 161 Equipment Operator Training 1050 164 Oregon State Dept. of Energy 219-221 (3) Licensed Training (Rms. 225, 247 or 248) 1050 223 Franklin County Emergency Management 236 Site I (B.Lyons) (13.5.3, 13.4.1, 13.5.7, 13.13.4, 13.14.9) 817

+ +238 *Alternate EOF (Keys) 901A

+ + Procedure Control does the filing at downtown - Bring keys

• Level 1 File Page 1 of 2

DATE: 08/27/03 EDITORIAL 13.1.1

I1flhIIH1fl

• 13.1.1*

ENERGY USE CURETVISION NORTHWEST People Vilelon-Solutions COLUMBIA GENERATING STATION PLANT PROCEDURES MANUAL PROCEDURE NUMER APPROVED BY DATE ff- -DRevision31

JEW

• 13.1.1 05/10102 VOLUME NAME EMERGENCY PLAN IMPLEMENTING PROCEDURES SECTON EMERGENCY CLASSIFICATION TITLE CLASSIFYING THE EMERGENCY TABLE OF CONTENTS E...

1.0 PURPOSE . .................................

2.0 REFERENCES

.............................. 2 3.0 RESPONSIBILITIES .................. - 3 3.1 Emergency Classification Responsibilities ........ . .. .. .. .. . ..... 3 3.2 Use of Plant Instruments and Indications ......... ,.. .. .. .. .. ..... 4 3.3 Emergency Class Description ................ . .. .. .. .. . ..... 5 3.4 Recovery vs. Downgrading Emergency Classifications . .. .. .. .. . .... .5 3.5 Mode Applicability. . .. .. .. .. . ..... 5 Mode ~ Ic~~

Aphht...................

..... 6 3.6 Emergency Classification Chart .............. . .. .. .. .. .

3.7 Transitory Event Classification ............... . .. .. .. .. . ..... 6 4.0 PROCEDURE .................................................. 7 4.1 Initial Classification/Control Room Actions ....... ...........

4.2 Continued Classification/Emergency Director Actions ...........

4.3 Terminating The Emergency Classification. ...........

4.4 Transitory Event Classification Notification ....... ... . ....... ..

5.0 ATTACHMENTS ... 9 5.1 Columbia Generating Station Emergency Classification Table .10 5.2 Columbia Generating Station Emergency Classification Chart Distribution .34 PROCEDURE NUMBER REVISION PAGE 13.1.1 31 1 of 37

C c (

rATF.nAtVV 1lN11TITAT VFNT Al RT QrrM ADPA kAPrfWrV ENER AT. MFfRlf1Nr'V

- -.- Narand destructiv -hnom 9 Hazards 9.4 Natural Events Natural and destructive phenomena Natural and destructive pheno ea affecting the Protected Area affecting Safe Shutdown Buildings Boundary 9.4.U.I 1112131415ddef 121314151 defl I :I OPERATING BASIS MINIMUM SEISMIC EARTHQUAKE alarm EARTHQUAKE alarm (H13-P851-SI-5.1)

(H13-P851-SI-2.5) AND AND CR receives report from plant CR receives report from plant personnel who have felt an earthquake personnel who have felt an k earthquake a f 12114151

[t def ~~~~~~~~~~~

~

9.4.U.2 I1121314151def Weather Service projected winds GT - ~ ~~~~~~

I 100 mph .

Weather Service projected winds UT OR 80 mph CR measured winds GT 70 mph (15 OR minute average at 33 f) 41 CR measured winds GT61 mph (15 OR minute average at 33 ft) Report by plant personnel confirming OR the occurrence of a tornado stnikdng a . . .~~~~~~~

Report by plant personnel confirming plant safe shutdown building, Table S the occurrence of a tornado striking within the Protected Area Boundary l12lH45defl Ash hflout from volcanic activity is severe enough to warrant plant 2L4.U13 shutdown Range fires near the plant which threaten to reduce the level of safety

DATE: 08/27/03 EDITORIAL 13.1.1A

.1 ~ ~ ~ *1..A USE TRESON NORTHWEST People Vision 6olutlons ._-

COLUMBIA GENERATING STATION PLANT PROCEDURES MANUAL PROCEDURE KUMBER APPROVED BY  :- :VDATE 13.1.1A  :}SLS - Revision II 05/02/03 VOLUME NoAME EMERGENCY PLAN IMPLEMENTING PROCEDURES SECTION EMERGENCY CLASSIFICATION CLASSIFYING THE EMERGENCY - TECHNICAL BASES TABLE OF CONTENTS age 1.0 PURPOSE ... . . . . . . . . . .... . . . ... . . ... .... 2

2.0 REFERENCES

.................................... . . ... . . ... .... 2 3.0 PROCEDURE .................................... . . ... .... 4 3.1 Plant Emergency Response Personnel Responsibilities ...... . . ... .... 4 3.2 Use Of Plant Instruments And Indications .............. . . ... .... 4 3.3 Emergency Class Description ...................... . . ... .... 4 3.4 Mode Applicability ............................ . . .. . ....

4.0 ATIACHMENTS ........................- . . ... ....

4.1 EAL Technical Bases . .............. .... . . ... .... 6 4.2 Table 6, Fission Product Barrier Degradation Table Bases ... . . ... .. 160 PROCEDURE NUMBER REVISION PAGE

13. 1. 1A I11 1 of 166

2.17 NUREG-0654/FEMA-REP-1, Rev. 1, Appendix 1 ("Basis For Emergency Action Levels For Nuclear Power Facilities")

2.18 Columbia Generating Station Safeguards Contingency Plan 2.19 ABN-CR-EVAC, Control Room Evacuation and Remote Cooldown 2.20 ABN-FLOODING, Flooding 2.21 ABN-WIND, Tornado/High Winds 2.22 PPM 5.0. 10, EOP Flowchart Training Manual 2.23 PPM 5.1.2, RPV Control-ATWS 2.24 PPM 5.7.1, RPV & Primary Containment Flooding Severe Accident Guidelines 2.25 G12-03-020, Elimination of Requirements for Post Accident Sampling System {C-11712}

PROCEDURE NUMBER REVISION PAGE 13.1.1A 11 3 of 166

I Reactor Fuel 1.1 Coolant Activity 1.I.A.1 Alert NUMARC IC: Loss or potential loss of fuel clad APPLICABILITY:

Operating Conditions I 12 3 1 - I I EMERGENCY ACTION LEVEL:

Coolant activity GT 300 gCi/gm dose equivalent iodine BASES:

This EAL is indicative of the loss of the fuel clad barrier. Fuel Clad barrier damage is indicated by a coolant activity of 300 gCi/gm dose equivalent 1-131. This amount of activity is well above that expected for iodine spikes and corresponds to approximately 2-5% fuel clad failure in accordance with assessment performed by the NUMARC EAL task force. This amount of clad failure indicates significant clad heating and, thus, the Fuel Clad barrier is considered lost. {C-11712}

REFERENCE(S):

Columbia Generating Station Technical Specifications NUMARC NESP-007, Methodology for Development of Emergency Action Levels, Rev. 2, Fission Product Barrier Basis Information for Table 3 Columbia Generating Station Fission Product Barrier Evaluation Columbia Generating Station Plant Specific EAL Guideline, FCL.l

9 Hazards 9.4 Natural Events 9.4.U.2 Unusual Event NUMARC IC: HU - Natural and destructive phenomena affecting the Protected Area Boundary.

APPLICABILITY: -__

Operating Conditions 1 2 3 4 5 def EMERGENCY ACTION LEVEL:

Weather Service projected winds GT 80 mph OR CR measured winds GT 61 mph (15 minute average at 33 ft)

OR Report by plant personnel confirming the occurrence of a tornado striking within the Protected Area Boundary BASES:

This event is a natural and potentially destructive phenomena that may accompany certain events such as a tornado or hurricane. These sustained high winds may also be produced by unstable weather conditions. However this event occurs, it may be a precursor to a more serious event and, therefore, represents a potential degradation in the level of safety of the plant.

A tornado touching down within the Protected Area is an observed event with the potential to cause damage to structures containing systems or functions necessary for the safe shutdown of the plant.

As such, the occurrence of a tornado strike represents a potential degradation in the level of safety of the plant. If structural damage is confirmed, this event would be escalated to Alert 9.4.A.2. If it is determined that the occurrence of the tornado strike has either affected or caused the loss of shutdown cooling functions, then the consequences of the event are assessed under event category 7.1, "System Failures". The event may then be escalated via this category if appropriate.

REFERENCE(S):

NUMARC NESP-007, Methodology for Development of Emergency Action Levels, Rev. 2, Unusual Event HUI Columbia Generating Station Tornado/High Winds, ABN-WIND Columbia Generating Station Plant Specific EAL Guideline, HU1.

Attachment 4.1 PROCEDURE NUMBER REVISION PAGE 13.1.1A 11 140 of 166

9 Hazards 9.4 Natural Events 9.4.A.2 Alert NUMARC IC: HA - Nituial and destructive phenomena affecting Safe Shutdown Buildings.

APPLICABILITY:

Operating Conditions I1 2 3 4 5 def EMERGENCY ACTION LEVEL:

Weather Service projected winds GT 100 mph OR CR measured winds GT 70 mph (15 minute average at 33 ft)

OR Report by plant personnel confirming the occurrence of a tornado striking a plant safe shutdown building, Table 5 BASES:

This event is a natural and potentially destructive phenomena that may accompany certain events such as a tornado or hurricane. These sustained high winds may also be produced by unstable weather conditions. However this event occurs, it may be a precursor to a more serious event and, therefore, represents a potential for substantial degradation in the level of safety of the plant. Sustained high winds at this level are beyond the design basis limits for the plant as described in SAR Section 3.3, Wind Loading. Wind loads of this magnitude have the potential to damage safety-related systems and functions. As such, the potential exists for substantial degradation of the level of the safety of the plant.

This EAL is intended to address events that may have resulted in Safe Shutdown Buildings being subjected to forces beyond design limits and, thus, damage may be assumed to have occurred to safe shutdown systems. The initial "report" should not be interpreted as mandating a lengthy damage assessment prior to classification. No attempt is made in these EALs to assess the actual magnitude of the damage. Escalation to a higher emergency class, if appropriate, will be based on the specific system malfunctions, fission product barrier degradation, abnormal radiological releases, or Emergency Director judgment ICs.

For the purposes of this EAL, Safe Shutdown Buildings are considered to be the following locations:

• Vital portions of the Radwaste/Control Building

• Reactor Building

• Vital portions of the Turbine Building

• Standby Service Water Pump Houses

• Diesel Generator Building

• Diesel Generator Fuel Oil Storage Area Attachment 4. 1 PROCEDURE NUMBER REVISION PAGE 13.1.1A l 11 146 of 166

DATE: 08/27/03 EDITORIAL 13.8.1

• 13.8.1*

ENERGY ENERGY 0 ~~~~~~USECURRENTREISMO NORTHWEST People .Vislon Soutions

• COLUMBIA GENERATING STATION PLANT PROCEDURES MANUAL  :

PROCEDURE NUMBER APPROVED BY  ::DATE:

• 13.8.1 - Revision 23 JJEW 05/10/02 VOLUME NAME EMERGENCY PLAN IMPLEMENTING PROCEDURES SECTION OFFSITE DOSE CALCULATIONS TLE EMERGENCY DOSE PROJECTION SYSTEM OPERATIONS TABLE OF CONTENTS Rage 1.0 PURPOSE .................. . . ... ............ .. ......... ...... .

2.0 REFERENCES

3.0 DEFINITIONS ............... ............ ........... ...... .

4.0 PROCEDURE ............... ............

4.1 General Instructions ....... ....  :........ ...... 4 4.2 Dose Estimation Using QEDPS ............ ...... 5 4.3 Dose Estimation Using EDPS . ............ ...... 7 4.4 Historical Dose Projections ............ ...... 8 5.0 ATTACHMENTS .............. . . ... . .. .. .. .. .. . ...... 9 5.1 EDPS User; Guidance ...... ............ ...... 10 PROCEDURE NUMBER REVISION PAGE 13.8.1 1 23 1 1of 23

1.0 PURPOSE This procedure provides instructions for the use of the computerized Emergency Dose Projection System (EDPS) to predict offsite dose rates, integrated doses and radioactive material deposition for locations within the 10-mile Plume Emergency Planning Zone (EPZ) and the 50-mile Ingestion EPZ. Actual manipulation of system display terminals is described in the Emergency Dose Projection System Users Manual referred to as the Users Manual.

(R1594}

2.0 REFERENCES

2.1 10 CFR 50 .47(b) {R1594}

2.2 G2-03-020, Elimination of Requirements for Post Accident Sampling System

{C-1 1714}

2.3 Emergency Dose Projection System Users Manual 2.4 FSAR, Chapter 13.3, Emergency Plan, Section 5.3 2.5 NUREG 1228, Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents 2.6 PPM 13.1.1, Classifying the Emergency 2.7 PPM 13.2.1, Emergency Exposure Levels/Protective Action Guides 2.8 PPM 13.2.2, Determining Protective Action Recommendations 3.0 DEFINITIONS 3.1 Contours - Lines on the output map(s) connecting points of equal dose/dose rate/deposition.

3.2 Delta T - The temperature difference between two sensors located at different elevations on a meteorological tower.

3.3 EDPS (Puff) - A dose projection computer program which employs all the design capabilities of multi-meteorology station data, variable source term via iterative data entry, full release time specification and a full output map selection. EDPS will compute dose/dose rate/deposition based on effluent monitor releases or reactor conditions out to 50 miles. EDPS provides the opportunity to modify the source term, reactor power, and release rates. EDPS will accept data from up to 50 meteorology stations to more realistically model the radioactive release via the puff dispersion model.

PROCEDURE NUMBER REVISION PAGE 13.8.1 23 2 of 23

4) Once the release has stabilized or is decreasing, then sole use of EDPS is appropriate with constant meteorological conditions.

5) Use of the EDPS Puff model at the end of the Early (plume) phase, in the Intermediate phase, or with variable meteorological conditions, is appropriate.

4.1.6 Refer to Attachment 5.1 as a guide through EDPS. For more detail consult the EDPS Users Manual.

4.1.7 Real time radiological and meteorological data is used by QEDPS and EPDS by default. Historical dose projections are estimated in Section 4.5.

4.1.8 Review dose projection printouts, note any qualifying factors, as appropriate, initial for release and brief the RPM or REM, as appropriate, on the dose projection.

4.1.9 Refer to PPM 13.2.2 for Protective Action Recommendation (PAR) guidelines.

4.2 Dose Estimation Using OEDPS {C-1 1714}

4.2.1 Verify that system is operational by turning on the surge protector, CPU, monitor, and printer, if necessary.

4.2.2 Activate QEDPS by double clicking the QEDPS icon.

a. The Monitoring/Field Data screen lists the Plant Monitors and Field Team options used to calculate a release. Readings for all monitors listed are normally available on the Rad Status screen in PDIS for use in the TSC or EOF.

b. Select monitor to be used for the calculations from Columbia Generating Station and enter data in appropriate blocks.

1) If the release path is out the Reactor Building, the primary choice is a Stack Monitor.

2) When a Stack Monitor is selected, a screen will be displayed requesting Standby Gas Treatment System (SGT) information.

• If you receive notification that the Control Room has received a high moisture alarm on Standby Gas Treatment, ensure that dose projections are performed with the SGTS Damaged option checked.

PROCEDURE NUMBER REVISION PAGE 13.8.1 23 5 of 23

DATE: 08/27/03 EDITORIAL 13.10.1

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• 13.10.1*

.~~~~~~~~~~~~~~~~~~~~~~~~

People

@ NERGY

~NORTHWEST Vislon Solutions COLUMBIA GENERATING STATION PLANT PROCEDURES MANUAL I

l ~~~~~~~~~~USECURRBNT REVISION-PROCEDURE NUMBER APPROVED BY DATE

'*'13.10.1 SLS - Revision 25 02/03/03 VOLUME NAME EMERGENCY PLAN IMPLEMENTING PROCEDURES SECION PLANT EMERGENCY FACILITES TITLE CONTROL ROOM OPERATIONS AND SHIFT MANAGER DUTIES TABLE OF CONTENTS 1.0 PURPOSE ..................................... 2 .

2.0 REFERENCES

...............- 2 .

3.0 DISCUSSION ................................... 4 .

4.0 PROCEDURE ................................. 4 .

4.1 Shift ManagerActions ......................... 4 .

4.2 Control Room Supervisor Actions ................. 9 .

4.3 Control Room Operator Actions .................. ...... .

4.4 Shift Technical Advisor/Emergency Response SRO Actions ...... .

4.5 All Control Room Personnel ..................... 12 .

4.6 Transfer Of Emergency Director Duties ............. 12 .

4.7 Actions As Emergency Director .................. 12 .

5.0 ATTACHMENTS ............................ 15 .

5.1 Shift Manager Checklist ....................... 16 .

PROCEDURE NUMBER REVUON PAGE 13.10.1 25 I of 20

- t -

a) With assistance from the STA, Incident Advisor, or Emergency Response SRO, determine the necessity to change the emergency clissification in accordance with PPM 13.1.1. Make the necessary public address announcements:

CAUTION: At the Unusual Event level when it is desired to activate the TSC and OSC, DO NOT activate the standard auto-dialer scenario for Unusual Event. Record an on-the-fly message to summon TSC and OSC staff using form 26171, Partial Activation or Manpower Schedule, instead.

1) Emergency center activation. Refer to Emergency Classification or Other Emergency Messages, 26045, (pink form) or,

2) Localized evacuation. Refer to Public Address Emergency Message Format - Localized Evacuation, 26048, (blue form) or,

3) Protected Area Evacuation. Refer to Public Address Emergency Message Format - Protected Area Evacuation, 26050, (green form) or

4) Exclusion Area Evacuation. Refer to Public Address Emergency Message Format - Exclusion Area Evacuation, 26051, (yellow form).

b) Ensure appropriate Control Room log entries are made for the emergency classifications and offsite notification actions.

c) At Site Area Emergency or higher classification, assign an individual in the Control Room to perform center accountability duties per PPM 13.5.5 if manual accountability is necessary.

4.1.3 If it becomes necessary to activate the TSC and OSC at an Unusual Event for additional support, activate both centers.

a) Use form 26171, Partial Activation or Manpower Schedule, to record an on-the-fly auto-ialer message to summon OSC and TSC staff at Unusual Event.

4.1.4 For any potential security scenario that could pose a threat to emergency center activation and personnel safety, confer with the Security Supervisor to determine:

PROCEDURE NUMBER REVISION PAGE 13.10.1 25 5 of 20