ML022970442
| ML022970442 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/15/2002 |
| From: | Conway J Constellation Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022970442 (116) | |
Text
NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-EPP-05A REVISION 02 LOCAL AREA/BUILDING EVACUATION 3 -2 Approved by:
G. L. Detter General MaT upport Services Date Effective Date: 09/16/2002 PERIODIC REVIEW DUE DATE JANUARY, 2003
LIST OF EFFECTIVE PAGES Page No. Change No. Pagie No. Change No. Page No. Change No.
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TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ................................................... 1 2.0 RESPONSIBILITIES ............................................. 1 3.0 PROCEDURE 2 3.1 Station Shift Supervisor/Emergency Director (SSS/ED ....................................................... 2 3.2 Security Site Supervisor ............................................................................................................ 3 3.3 All Station Personnel Within the Evacuated Area/Building ................................................ 3 3.4 The Chief Radiation Protection Technician or Lead Technician ........................................ 4 3.5 Relocation Building Management Representative .............................................................. 4 3.6 First Line Supervisors/Fire ................................................................................................... 4 4.0 DEFINITIONS .................................................. 5
5.0 REFERENCES
AND COMMITMENTS ............................................................................................. 5 6.0 RECORD REVIEW AND DISPOSITION ................................... 6 ATTACHMENT 1: EMERGENCY ANNOUNCEMENT ................................................................................. 7 Page ii EPIP-EPP-05A Rev 02
1.0 PURPOSE To outline the method for evacuating local areas and buildings without evacuating the entire Protected Area or Exclusion Area when required to ensure the health and safety of personnel within those areas.
2.0 RESPONSIBILITIES 2.1 The Station Shift Supervisor (SSS)/Emergency Director (SSS/ED) or Emergency Director/Recovery Manager (EDIRM) directs a Local Area or Building Area Evacuation in accordance with this procedure when the health and safety of personnel is or may be in question.
2.2 The Chief Radiation Protection (RP) Technician or Lead RP Technician provides assistance for evacuees as necessary at the Radiologically Controlled Area (RCA) access control point.
2.3 All station personnel listen to and follow instructions given in station announcements.
2.4 Security Site Supervisor coordinates with the SSS/ED as required to ensure an orderly evacuation.
2.5 Relocation Building Management Representative 2.5.1 Coordinates the arrival of evacuees to the building.
2.5.2 Provides for emergency status announcements for the building as information is made available.
2.5.3 Provides for the orderly return of personnel to work or home when appropriate.
2.6 First Line Supervisors/Fire Wardens should ensure that their people are accounted for following an evacuation involving the area/building they normally occupy.
Page 1 EPIP-EPP-05A Rev 02
3.0 PROCEDURE 3.1 Station Shift Supervisor/Emergency Director (SSSIED the 3.1.1 When it is determined that conditions exist that pose a localized hazard to employees SSSIED should:
- a. Determine extent of area/building to be evacuated.
- b. Ifaccounting of personnel is determined to be necessary, implement EPIP-EPP 05D, "Accountability".
- c. Contact Security Site Supervisor to coordinate the orderly evacuation of personnel. This discussion should include:
0 Evacuation direction based upon location of hazard and wind direction 0 Where evacuees are to be re-located (another building in a safe area or home) 0 Traffic Controls required/needed
- Order of evacuation if multiple buildings/areas are involved (to limit confusion and traffic congestion)
- d. Provide required information to the CSO.
- e. IFan emergency has been declared, ensure the announcement for a Local Area/
Building Evacuation is made in accordance with EPIP-EPP-18.
OR IFno emergency has been declared, ensure the announcement for a Local Area/
Building Evacuation is made in accordance with Attachment 1.
3.1.2 When conditions that necessitated the evacuation have been terminated the SSS/ED shall:
- a. Ensure the announcement for termination in accordance with EPIP-EPP-18 is made.
Page 2 EPIP-EPP-05A Rev 02
3.2 Security Site Supervisor 3.2.1 When notified that a local area/building evacuation may be in order, coordinate with the SSS/ED to:
- a. Determine where evacuees should be relocated to ensure safety and minimize confusion and traffic congestion.
- b. Recommend order of area/building evacuation ifmultiple areas/building are involved.
- c. Determine security needs to ensure an orderly evacuation. Consider:
- Evacuation control at evacuation site and relocation area
- Traffic control at parking areas near evacuation site, at relocation area and along access road. (Request assistance as necessary from any available department or Local Law Enforcement Agency)
- d. Ifevacuating to another building, contact a management representative located in the building (ex: Training Manager at NLC, VP Engineering at ESB etc.) and inform them to prepare for the arrival of evacuees.
- e. Ifaccountability is directed, implement EPIP-EPP-05D.
3.2.2. When the emergency requiring evacuation has been terminated, and return of personnel is permitted, coordinate with the SSS/ED for the orderly return of evacuees.
3.3 All Station Personnel Within the Evacuated Area/Buildinq NOTE: Ensure compliance with all escort responsibilities. Visitors should be escorted to site access and carded out of the area.
3.3.1 Immediately upon hearing the Evacuation Alarm and announcement to evacuate the area/building:
- a. Leave the area immediately, as directed.
- b. Adhere to directions provided by the announcement.
- c. Do not return until the situation is terminated or your assistance is required to resolve the situation as directed by SSS/ED or your supervisor.
- d. Ifthe area/building is contaminated
- 1. Leave the area removing PC's as directed by the announcement.
- 2. Go directly to the nearest Radiologically Controlled Area (RCA) access control point.
- 3. Ifnecessary, obtain Radiation Protection Technician assistance in removal of PC's and decontamination.
- 4. Leave the RCA access control point and remain out of the area until informed that the situation has been terminated or your assistance is required to resolve the situation as directed by the SSS/ED or your supervisor.
Page 3 EPIP-EPP-05A Rev 02
3.4 The Chief Radiation Protection Technician or Lead Technician 3.4.1 Immediately upon hearing the Evacuation Alarm and announcement to evacuate the arealbuilding:
- a. Ensure an RP Tech reports to the RCA access control point to provide assistance as required for evacuees requiring PC removal and/or decontamination until situation is terminated or directed otherwise by the SSS/ED or your supervisor.
- b. On back shift, request the SSS/ED contact RP Supervision and obtain additional RP Support as necessary.
3.5 Relocation Building Management Representative 3.5.1 Coordinate the arrival of evacuees to the building by ensuring adequate space is made available. (Cancel classes, open/unlock doors, direct personnel to where you want them etc..).
3.5.2 Obtain emergency status information from the control room and provide emergency status announcements for the building, using available PA systems, or runners.
3.5.3 Ifaccountability was not announced, obtain accountability information from first line supervisors/fire wardens from building being evacuated.
3.5.4 Ifanyone is reported missing, contact the SSS/ED and request the implementation of EPIP-EPP-03 for the missing person(s).
3.5.5 Contact the SSS/ED and determine future plans for evacuees. (Home or return to work) 3.5.6 Coordinate with Security Site Supervisor to ensure the orderly return of personnel to work or home when appropriate.
3.6 First Line Supervisors/Fire 3.6.1 Ifaccountability was not announced for the evacuation involving the area/building you normally occupy, ensure your people are accounted for at the relocation building.
3.6.2 Inform the Relocation Building Management Representative of the status of your department personnel. (All accounted for or provide names of those missing)
Page 4 EPIP-EPP-05A Rev 02
4.0 DEFINITIONS 4.1 A local area may be any area that is physically separated from other areas, by walls or elevation differences, or partitions, or doors.
4.2 A building may be any enclosed structure, such as the Reactor Building, Turbine Building, Screen house, L-Building, etc, whose ventilation system is separate from other structure's ventilation system.
5.0 REFERENCES
AND COMMITMENTS 5.1 Technical Specifications None 5.2 Licensee Documentation Nine Mile Point Site Emergency Plan 5.3 Standards, Regulations, and Codes NUREG-0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, November 1980 5.4 Policies, Programs, and Procedures 5.4.1 EPIP-EPP-18, Activation and Direction of the Emergency Plans 5.4.2 EPIP-EPP-05D, Accountability 5.5 Commitments Sequence Commitment Number Number Description None Page 5 EPIP-EPP-05A Rev 02
6.0 RECORD REVIEW AND DISPOSITION The following records generated by this procedure shall be maintained by Records Management for the Permanent Plant File in accordance with NIP-RMG-01, Records Management
- Attachment 1, Emergency Announcement The following records generated by this procedure are not required for retention in the Permanent Plant File:
- None LAST PAGE Page 6 EPIP-EPP-05A Rev 02
ATTACHMENT 1: EMERGENCY ANNOUNCEMENT LOCAL AREA/BUILDING EVACUATION (No emergency has been declared)
Instructions: (check boxes to select appropriate announcement)
- 1. Place GAltronics in Merge,
- 2. Sound the EVACUATION alarm for 10 seconds
- 3. Announce (ifchecked, include in announcement),
0 a. Attention, Attention all personnel,this (is/isnot) - a drill.
13 b. Nine Mile Point (Unit 1 or 2) is orderingan evacuation of the (Unit 1 or 2): (Provide specific location or building to be evacuated)
El c. Due to: (provide conditions necessitatingthe evacuation)
El d. All personnel are to leave the (Unit 1 or2) (area/building)
El 1. Staying clearof (area/elevation)and report to OR El 2. Using the closest possible exit, and report to El e. Accountability is beingperformed, all personnel shall report to an assembly area, card in and remain in the area until further notice.
l f. Personnelin protective clothing should (select appropriate):
El 1. Leave the area removing PC s as indicatedat the step off pad.
OR El 2. Leave the area immediately and obtain Radiation Protectionassistance at the control point.
El g. I repeat this isfis not a drill.
- 4. Repeat the alarm and announcement.
- 5. Consult with opposite unit SSS and determine ifGAltronics should be left in Merge (required for declared emergencies for the duration of the event.
Page 7 EPIP-EPP-05A Rev 02
NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-EPP-08 REVISION 13 OFF-SITE DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION 11TECHNICAL SPECIFICATION REQUIRED, Approved by: Date G. L. Detter Effective Date: 09/30/2002 PERIODIC REVIEW DUE DATE: SEPTEMBER, 2003
LIST OF EFFECTIVE PAGES Change No. Page No. Change No. Page No. Change No.
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Page i EPIP-EPP-08 Rev 13
TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.0 PRIMARY RESPONSIBILITIES ........ ... .......................
2 3.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . 2 3.1 Dose Assessment and Protective Action from the Control Room 3 3.2 Dose Assessment and Protective Actions from the EOF ....
4.0 DEFINITIONS . . . . . . . . . . . . . . . . . . . . . .
5
5.0 REFERENCES
/COMMITMENTS ........ ..................
7 6.0 RECORDS REVIEW AND DISPOSITION .... ...............
8 ATTACHMENT 1: INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS USE OF THE EDAMS COMPUTER .......... . . .
... 12 ATTACHMENT 2:
.. 14 ATTACHMENT 3: METEOROLOGICAL DATA ACQUISITION
. . . . . . 24 ATTACHMENT 4: RELEASE RATE DETERMINATION ..... ..........
ATTACHMENT 4A: DETERMINATION OF PERCENT OF TECHNICAL SPECIF ICATION RADIOLOGICAL RELEASE ........... 32 33 ATTACHMENT 5: REFINED DOSE ASSESSMENT AND PROTECTIVE ACTIONS 39 ATTACHMENT 5.1: CHRONOLOGICAL RELEASE RATE LOG ... .......
40 ATTACHMENT 5.2: EDAMS DATA ENTRY FORM ...........
Page ii EPIP-EPP-08 Rev 13
1.0 PURPOSE To provide the m6thods for determining meteorology data, release rates, dose assessment and protective actions during accident conditions at Nine Mile Point.
2.0 PRIMARY RESPONSIBILITIES 2.1 The Station Shift Supervisor/Site'Emergency Director (SSS/ED):
2.1.1 Ensures meteorological data acquisition, release-rate determination, and dose assessment are performed during the initial stages of an emergency to support development of Protective Action Recommendations (PARs) 2.1.2 Approves PARs and ensures their timely issue to the State and County 2.2 The Emergency Director/Recovery Manager (ED/RM) approves PARs prior to their transmittal to the State and County, following EOF activation.
2.3 The Radiation Assessment Manager (RAM) is responsible to the TSC Manager for managing the onsite radiological monitoring and assessment aspects-of the station during an emergency, following TSC activation.
2.4 Chemistry Technicians perform release rate assessments, obtain meteorological data, and develop PARs, prior to EOF.activation.
2.5 The Offsite Dose Assessment Manager (ODAM) manages the offsite dose aspects of an emergency in order to assess the radiological consequences to the public, following EOF activation.
2.6 The Radiological Assessment Staff is responsible to the ODAM for obtaining meteorological data, determining source term, performing dose assessment, and developing PARs, following EOF activation.
Page 1 EPIP-EPP-08 Rev 13
3.0 PROCEDURE 3.1 Dose Assessment and Protective Action from the Control Room CAUTION Calculation involving the determination of release rates and/or protection action shall be self-checked for accuracy.
3.1.1 Chemistry Technician Actions
- a. Consult the SSS/ED on plant conditionsand possible release paths. If a General Emergency has-been declared, assist SSS/ED in making Protective Action Recommendations based on plant conditions using Attachment 1.
- b. Access EDAMS computer using Attachment 2
- c. Obtain meteorological data using Attachment 3.
- d. Assess effluent monitor readings and conditions.
- e. Determine release rate using Attachment 4. Combine multiple release points as follows:
- 1. Sum all release points from the same elevation (ground or elevated).
- 2. Calculate the total release rate from combined ground and elevated sources using the workspace on Attachment 1.
- f. Use Attachment I flowchart and advise SSS/ED of any PARs recommended by the flowchart.
- g. IF an unmonitored atmospheric release is suspected or known to be in progress, then assist the SSS/ED in the following actions:
- 1. Advise the SSS/ED to expedite the dispatch of Radiation Protection (RP) Technician. Request assistance of the unaffected Unit or J.A. Fitzpatrick if needed.
- 2. The RP Technician should be dispatched to potential plume centerline (wind direction (degrees) +/- 180' =
plume centerline), as close to the site boundary as practicable. See Attachment 1, Figure 1.4 for Site boundary location.
- 3. IF readings indicate > 1 rem/hr based on field survey perform the actions indicated in Attachment 1.
Page 2 EPIP-EPP-08 Rev 13
3.1.1 (Cont)
- h. Assist Communications' Aide in completing'the meteorological data and release rate sections of the Part I Notification Fact Sheet.
- i. Continue to monitor meteorological data, changes in effluent conditions or conditions that might lead to abnormal radiological effluents.
- j. When contacted by EOF Dose Assessment Staff, provide briefing on:
- Status of any radiological releases
- Dose assessments efforts to date
- a. Verify that the Chemistry Technician is performing dose assessment and protective action development in a timely with Attachment 1.
fashion and in accordance
- b. Assess any release rates provided by the Chemistry Technician against the Emergency Actio6 Levels (EAL).
- c. Review AND approve PARs recorded on the Notification Fact Sheet Part 1, as required. Use ERPA map in Attachment 1 if desired.
3.2 Dose Assessment and Protective Actions from the EOF 3.2.1 Offsite Dose Assessment Manager (ODAM) Actions
- a. IF at any time the initiating conditions listed in Attachment 1 are met; THEN perform the actions listed in that attachment.
- b. Perform actions as indicated in EPIP-EPP-23.
- c. Verify Environmental Survey Sample Team Coordinator has been assigned and is:
- 1. Preparing for the dispatch of downwind survey teams.
- 2. Aware of meteorological advisor status.
Page 3 EPIP-EPP-08 Rev 13
"Nf 3.2.1 (Cont)
- d. Perform or have performed the following:
- 1. Obtain meteorology data using Attachment 3 of this procedure.
- 2. Obtain effluent monitor readings and calculate release rate using Attachment 4 of this procedure.
- 3. Perform dose assessment calculations and PARs using Attachment 5 of this procedure.
- e. Interface with State and County representatives in the EOF.
- 1. Keep State/County representatives informed of confirmed data and results.
- f. Complete Part 2 Notification Fact Sheet in accordance with EPIP-EPP-23.
- g. Constantly reassess effluent monitors (release rate) and meteorological data for changes. Perform new dose assessment as needed. Develop new PARs and/or verify the adequacy of PARs already made.
_ h. As Downwind Survey Team (DST) becomes available, utilize it to verify release rates. If these refined release rates differ significantly from those calculated from effluent monitor readings, reperform dose assessment using refined release rates.
- i. Provide data for the Part I Notification Fact Sheet as requested.
- j. Provide ED/RM with pertinent information as needed.
- 2. Protective actions for site staff.
- k. Maintain Chronological Release Rate L6g (see Attachment 5.1).
Page 4 EPIP-EPP-08 Rev 13
3.2.2 EOF Dose Assessment Staff
- a. IF at any time the initiating conditions listed in Attachment 1 are met, THEN perform the actions listed in that attachment.
- b. Perform actions as indicated in EPIP-EPP-23.
- c. Perform any actions as requested by the ODAM, including:
"* Obtaining meteorological data (Attachment 3)
"* Obtaining release rate data (Attachment 4)
"* Performing dose assessment and protective action recommendations (Attachment 5) 4.0 DEFINITIONS 4.1 CDET. Committed dose equivalent to the thyroid for the child.
4.2 EDAMS. Emergency Dose Assessment Modeling System. A PC-based computer program that calculates release rates, doses and protective actions, and obtains meteorological data for emergencies.
4.3 MMS. Meteorological Monitoring System. Consists of the dedicated computer, main, backup and inland towers and software. Stores and edits site meteorological data.
4.4 RADDOSE. A subprogram of EDAMS, it performs the-dose assessment functions during emergencies.
4.5 SHELTERING. A protective action whose benefit is to bring the public to a heightened state of awareness. No dose reduction is assumed for sheltering.
4.6 TEDE. Total Effective Dose Equivalent.
5.0 REFERENCES
/COMMITMENTS 5.1 Technical Specifications None Page 5 EPIP-EPP-08 Rev 13
5.2 Licensee Documentation 5.2.1 NMP Unit 1 FSAR,Section XV
- a. Table XV-32
- b. Table XV-28
- c. Table XV-29
- d. Table XV-23
- e. Table XV-29d
- f. Section 1.3.1
- a. Table 15.6-15b
- b. Table 15.4-12
- c. Table 15.7-11 d., Table 15.6-8
- e. Table 15.7-4
- f. Table 15.6-3
- g. Table 16.6-19 5.2.3 SEP, Nine Mile Point Nuclear Station Site Emergency Plan 5.2.4 NMPC Correspondence 96-MET-O01 (Backup Tower Wind Speed Correction Factor) 5.2.5 NMP Correspondence 96-MET-002 (Main Tower Wind Speed Cor rection Factor) 5.2.6 NMP Correspondence 96-MET-004 (Backup Tower Wind Directiion Concerns) 5.2.7 NMP Correspondence 96-MET-003 (Discussion at DER C-95-06'93) 5.2.8 NMP Correspondence 96-MET-005 (Main Tower 30' Sigma Thet a Concern) 5.2.9 NMP Correspondence 97-MET-002 (Main Tower Wind Obstructi ons)
Page 6 EPIP-EPP-08 Rev 13
5.3 Standards, Regulations, and Codes NUREG-0654, FEMA-REP-1, Rev 1, Supp 3, Criteria for Protective Action Recommendations for Severe Accidents 5.4 Policies, Programs, and Procedures 5.4.1 EPIP-EPP-07, Downwind Radiological Monitoring 5.4.2 EPIP-EPP-15, Health Physics Procedure 5.4.3 EPIP-EPP-23, Emergency Personnel Action Procedures 5.5 Commitments DER C-95-0693 (for Attachment 3) 6.0 RECORDS REVIEW AND DISPOSITION 6.1 The following records generated by this procedure shall be maintained by Records Management for the Permanent Plant File in accordance with NIP-RMG-01, Records Management:
NOTE: For records generated due to an actual declared emergency only.
- Attachment 1, Initial Dose Assessment and Protective Actions
- Attachment 4, Release Rate Determination
- Figure 5.1, Chronological Release Rate Log
- Figure 5.2, EDAMS Data Entry Form 6.2 The following records generated by this procedure are not required for retention in the Permanent Plant File:
NOTE: For records generated NOT due to an actual declared emergency only.
- .Attachment 1, Initial Dose Assessment and Protective Actions
- Attachment 4, Release Rate Determination
- Figure 5.1, Chronological Release Rate Log
- Figure 5.2, EDAMS Data Entry Form Page 7 EPIP-EPP-08 Rev 13
ATTACHMENT 1: INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS Sheet 1 of 4
- Use this formula if release has a ground AND elevated source:
K Ground Release Rate (Ci/s)
Table 1.1 Ground Release Rate (Cils) L Table 1.1 Elevated release rate Elevated (Cl/s)
Release Rate (Ci/s) I IF >_Ž1, A General Emergency Exists Li Page 8 EPIP-EPP-08 Rev 13
ATTACHMENT 1: (Cont)
Sheet 2 of 4 TARLE 1.1-- GENERAL EMERGENCY RELEASE RATES Ground Release [Cilsi Elevated Release (Clis)
Wind Speed Stability Class Wind Speed Stability Class (milh) A - B/C D E/F/G (mi/h) A B/C - D E/F/G 0-3 2041 1124 3030 769 0-3 1333 213 119 38' 4-6 3703 909 769 769 4-6 3226 286 143 48 7-9 5882 1515 1075 1250 7-9 5556 526 250 83 10-13 7692 2083 1388 1724 10-13 7692 769 357 117 14-17 11494 2857 1818 2273 14-17 10753 1075 500 164 18-21 14286 3704 2273 2778 18-21 13514 1389 667 213
>21 17241 4348 2632 3226
>21 16393 1667 833 256 TABLE 1.2 - AFFECTED ERPAs Lake Breeze Adjusted
-Wlnd Direction From';: ::5 Miles D(;wnwind
. Miles krDuown wiin ... l (15 MileR adius) 214to 222 1, 2;3, 26, 27 4*ý 7 .:;. ..:-..
223 to 233 1, 2, 3, 26,:Z7:. . .... 4 234 to 240 1,2, 3, 7, 26,27 241 to 254 .... , 2, 2 3,4,7, 26-7.. .. 9 9
255 to 262 1, 2, 3, 4, 7, 26, 27 263 to 278 !, 2, 3, 4, 7, 9, 26, 27 10 279 to 292 1, 2, 3, 4, 5,77,9, 26, 27 293 to 305 1, 2, 3, 4,.5; 7. 9,%10, 26, 27 306to 311 1, 2, 3, 4, 5, 7, 9, 10, 26, 27 6, 1 1 312to 332 ., ,-2,3,4,5,7. 9, 10,26,27 4 6, 7, 12 333 to 340 1, 2, 3, 4, 5, 9, 10, 11, 26, 27 .
C5 6,7,12 341 to.349 .. 1,2, 3,4, 5, 9,10, 11, 26,. 27 1.
4, 7 350 to'356 1, 2, 3, 5, 6, 9, 10, i1, 26, 27 357 to0 1 2,3,5,6,9,-10; 11, 26,27 4 0 to '12 4,9 13to 20 1,2,3,5,6, 10, 11,26,27 CD 9 .1..::-:!. .:: * .
0 2!to~l 15 3,2, 35, 6,*0, 11,26, 27 52 to 56 ... 1,,,2, 3, 5, 6,'11,26,27 1,2, 3,,5, 6, 11, 26, 27;! !. . , i SJ- 10 57 t :. 6!!. ...*
10>
10 ...
62 to 70 to 1, 2, 3, 6, 11, 26, 27 : : .
71 ..... 89 ::.1, 2, 3, 6;*-2,
"::::. 7 *'-
7 to1 89 . ,
-,26,, ;
2* ,,,,, , '"i
, 5, 1,12 90 to 95 1, 2, 3, 6, 26, 27 6, 12 115to 146 1,2,3,26,27 I_:2*
- I*
ý.)b ZI .,&- ,. -. ,--% .,
I A -7 J +ý '7 1 7 .-,.
TABLE 1.3 - EPA 400 Protective Action Guidelines (EPA PAGs)
" PAR . . I . EDE Irem) I CDET (rem)
Evacuate > 1 > 5 Page '9 EPIP-EPP-08 Rev 13
ATTACHMENT 1: INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS Sheet 3 of
-- FIGURE 1.4 - Site Boundary Ma p_
Site Boundary Map LAKE ONTARIO James A.Fitzpatrick Nuclear Power Plant Page 10 EPIP-EPP-08 Rev 13
ATTACHMENT 1: INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS Sheet 4 of 4 FIGURE 1.5 - ERPA Map
""Emergency Response Planning Areas (ERPA) with 1991 Population Estimates Page 11 EPIP-EPP-08 Rev 13
ATTACHMENT 2: USE OF THE EDAMS COMPUTER Sheet 1 of 2 1.0 CONTROL ROOM EDAMS 1.1 If necessary, turn the system on: Turn on-the power to the EDAMS computer, monitor, and printer. After the computer boots:
- a. Select the "EDAMS" icon.
- b. Select the "Login" icon.
- c. Select "Continue" or hit the enter key.
- d. Select "Direct Connect to Met Data".
- e. Once Login is successful/complete, select "OK".
- f. Select appropriate icon.
1.2 Computer or Connect Problems
- a. If "Direct Connect to Met Data" fails repeat Step 1.1 and then, select "Automatic Dial-In to Met Data".
- b. If "Automatic Dial-In to Met Data" fails, select "Manual Dial-In to Met Data", and select "number to dial" from the drop down box.
Repeat with different number if necessary.
- c. If at any time problems are experienced with the computer, depress the eject button on the side of the computer. This will eject the laptop computer. Continue this procedure with the laptop.
- d. If the laptop should fail, have Chemistry Tech from the unaffected Unit-go to the unaffected Control Room and bring the EDAMS laptop back to the affected Control Room and continue with this procedure.
NOTE: In this case, meteorological data will have to be obtained manually.
2.0 EOF EDAMS 2.1 If necessary,-turn-the system on: Turn on the p6wer to the EDAMS computer, monitor, and printer. After the computer boots:
- a. Select the "EDAMS" icon.
- b. Select the "Login" icon.
- c. Select "Continue" or hit the enter key.
- d. Select "Automatic Dial-In to Met Data"
- e. Once Login is successful/complete, select "OK".
- f. Select appropriate icon.
Page 12 EPIP-EPP-08 Rev 13
ATTACHMENT 2: (Cont),
Sheet 2 of 2 2.2 Computer or Dial-In Problems
- a. If "Automatic Dial-In to Met Data"-fails, select "Manual Dial-In to Met Data", and select "Number to Dial" from the drop-down box.
Repeat with a different number if necessary.
- b. If at any time problems are experienced with the computer,
- 1. Re-boot the computer
- 2. Reset the modem by toggling the power switch
- 3. Repeat step 2.1
- 4. If problems are still evident, use the duplicate computer in the EOF.
3.0 EDAMS DOSE'MODEL LIMITATIONS 3.1 A calculational limitation of the dose assessment model occurs when an extreme wind (direction) shift takes place. The model may not calculate'doses in sectors that the plume skips over entirely within a single'15 minute calculation step.
3.2 EDAMS only allows the operation of one application at time.
3.3 Dose rates and deposition rates reported by the model are the maximum for the sector, not necessarily the dose rate or deposition rate at the center of the sector. This avoids the situation of a narrow (stable) plume slipping between receptor points and being missed.
3.4 Deposition data reported is not intended for an environmental evaluation; its intent is to indicate areas of potentially high ground level concentrations.
Page 13 EPIP-EPP-08 Rev 13
ATTACHMENT 3: METEOROLOGICAL DATA ACQUISITION 1.0 OBTAINING METEOROLOGICAL DATA NOTE: The Meteorological Advisor may use the following steps or skills of the trade to obtain meteorological data.
1.1 Obtain ground/elevated meteorological data appropri'ate to the radiological release point in the order listed below. If no release is in progress, or the release path is unknown obtain the elevated data.
A. EDAMS (see Section 2.0 of this Attachment)
B. Strip, chart recorder (see Section 3.0 of this attachment)
C. Manual input from alternate sources (see Section 4.0 of this attachment) 1.2 EOF only - Determine if Lake Breeze or Land Breeze is a possibility in accordance with Figures 3.2 and 3.3.
1.3 EOF only - If using the main tower and wind direction is between 0° and 100' or if using the backup tower and wind direction is between 2200 and 2700 notify the ESSTC and ODAM that the plume may arrive sooner than the wind speed would indicate.
1.4 Repeat Section 1.0 every 15 minutes.
2.0 USING EDAMS TO OBTAIN METEOROLOGICAL DATA 2.1 Log in the EDAMS computer in accordance with Attachment 2 of this procedure.
2.2 Select "Emergency Meteorological Report" to obtain meteorological data.
2.3 Select affected unit.
2.4 Select "Continue" or hit "enter" key.
2.5 Requery, if necessary.
2.6 Select "Print Met Data" to print the data, as required.
2.7 Determine whether to use ground or elevated data in accordance with Step 1.1.
2.8 Use data as obtained; data may be recorded in Table 3.7.
2.9 If data is not available through the EDAMS computer, proceed to Section 3.0.
Page 14 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont) 3.0 USING STRIP CHART RECORDERS TO OBTAIN METEOROLOGICAL DATA CAUTION Do not use the LED readouts associated with the strip chart recorders.
- * * * * * * * * * * * * * * *-'* *i* * * * * * * *
- NOTE: Use this method only if the method described in Section 2.0 of this attachment is unavailable. If the strip chart data is unavailable, proceed to Section 4.0.
3.1 Locate the chart recorders in the Unit 1 or 2 Control Rooms or the TSC.
NOTES: 1. Figure 3.4 shows a sample strip chart trace of air tempe'rature, 100' AT, 200'AT, and uO'and Figure 3.5 shows a sample of wind speed and wind direction data.
- 2. The Meteorological Advisor may use the following steps or skills of the trade to obtain meteorological data.
3.2 Apply the hierarchy in accordance with Table 3.1 to determine what data to obtain.
TARI F 3_1
-Parameter .Hierarchy Elevated Release Ground .Release, Primary 200' Main 30' Main 100' Main Wind Speed & Direction JAF Backup Substitutes 30' Mai 200' Main
,'nI'T rI in AT trimary P -r£ u- l?
200' AT 100' AT 30' o0 L, 200' ae"'
Stabil . . Substitute JAF Backup aO 200' aiO" 30' oO"'
If using 30', 100' or 200' oO stability, AND the wind is form a direction listed is Step 3.13, THEN substitute the next source of data in accordance with this step.
Page 15 EPIP-EPP-08 Rev 13
I ATTACHMENT 3: (Cont) 3.3 If substitute data is to be used consult the meteorological advisor if available; otherwise use the data as obtained.
3.4 Determine wind direction as follows:
- a. Locate the wind direction trace
- b. Estimate the average wind direction over the last 15 minutes; data may be recorded in Table 3.7.
3.5 Determine wind speed as follows:
- a. Locate the wind speed trace
- b. Estimate the average wind speed over the last 15 minutes; data may be recorded in Table 3.7.
3.6 Determine AT as follows:
- a. Locate the AT
- b. Estimate the average AT over the last 15 minutes.
- c. Compare AT values to the Stability Classification chart (Table 3.6).
- d. Select the appropriate stability class o(For,200' AT use column 6 and for 100' AT use column 4); data may be recorded in Table 3.7.
3.7 If AT values are not available, then locate the co from the main or backup tower recorder.
3.8 If using 30", 100', or 200' uG stability and the wind is reading from a direction listed below, substitute the next stability source in accordance withTable 3.1.
Main Tower uG Stability Wind Direction 200' 0300 to 0960 100' 0300 to 0770 30' 035* to 0760 3.9 Compare the value of uo to Table 3.6 (Column 5) 3.10 Select the appropriate stability class (Column 3); data may be recorded in Table 3.7.
3.11 If using JAF Backup aO stability, the following adjustments should be made:
JAF Backup Tower Wind Direction JAF Backup a8 Stability Adjustment Add one stability class, such that:
A-B 232° to 246° B-C or C-D 270° to 2810 D*E E-F F or G-G Add two stability class, such that:
A-C B-D 2470 T 2690 C-E D-F E,, F or G-G Page 16 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont) 3.12 If neither AT or qe is available, observe the wind direction trace (200' for elevated data or 30' for ground data or substitute per Table
,3.1) over the last 15-minute period.
3.13 Estimate ue from the trace by dividing the horizontal deviation of the wind direction trace (over the last 15 minutes) by 6. To make reading the chart easier, you may want to- advance the chart.
3.14 Compare this calculated value to Table 3.6 (Column 5).
3.15 Select the appropriate stability class (Column 3); data may be recorded in Table 3.7.
4.0 MANUAL INPUT FROM ALTERNATE SOURCES NOTE: Use this data only if the methods described in Section 2.0 and 3.0 unavailable.
CAUTION Data obtained by the following methods may not be site-representative and may introduce errors into dose assessments. The Meteorological Advisor should be consulted regarding the use of all substitute data.
Use the data as obtained if the Meteorological Advisor is not available.
4.1 To obtain National Weather Service (NWS) Meteorological Data
- a. Telephone the NWS in Buffalo'at 800-462-7751 or 716-565-9001.
- b. Request the current wind speed, direction, stability class, and temperature.
- c. Use the data as follows:
- 1. Wind speed = elevated and ground wind speed
- 2. Wind Direction = elevated and ground wind direction
- 3. Stability Class = elevated'and ground stability classes
- 4. Temperature = ambient temperature 4.2 EOF Only - (Directions for the following may be found at the EOF at the Meteorological Advisor Station.)
Other sources of meteorological data that may be utilized are:
- 1. SODAR
- 2. Other Meteorology towers
- 3. Commercial weather services
- 4. Meteorological Advisor only - Characterization tables
- 5. Meteorological Advisor only - Skills of the trade 4.3 Once the data is obtained Table 3.7 may be used to record the values.
Page 17 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont)
Lake Breeze/On-Shore FIGURE, 3.2 Flow and Fumigation Flow Chart EOF only - Refer to the following step and the flowchart below to determine if a lake breeze is a possibility.
- 1. Obtain meteorological data in Section 1.0 of this attachment.
- 2. Obtain lake temperature from Unit 1 or 2 process computer, control rooms, EDAMS, or meteorological advisor (if available).
- 3. Follow the flowchart answering the appropriate questions.
Is a release possible INO between dawn and dusk? I IYES .. A Is the intake water temperature less than INO the air temperature?
I YES Is the elevated wind LNO I sDeed less than 22 moh? I IYES Is the elevated wind direction out of the NO Is the elevated wind NO sector from 2700 - speed less than 10 throuqh 360° to 090'? mph?
I YES IYES
,Potential. for .lonshore Potential for-Lake.
flow or fumigation existsii:i *:: ;:i Breeze-exi sts:* Stop Analysis.
Use "lake breeze Use "lake breeze No adjusted ERPAs" for adjusted ERPAs" for modi fications PARs (Table 1.2 or PARs (Table 1.2 or to PARs EDAMS) EDAMS) requi red
- NOTE: There is a potential for a shift in wind direction to 245° through to 065' if the lake breeze has not already formed.
Page 18 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont)
FIGURE 3.3 LAND BREEZE FLOW-CHART if a land breeze is a EOF only - Refer to the flowchart below to determine possibility.
Section 1.0 of
- 1. Obtain meteorological data in accordance with this Attachment.
computer,
- 2. Obtain lake temperature from Unit 1 or 2 process (if available).
control rooms, EDAMS or meteorological advisor questions.
- 3. Follow the flowchart answering the appropriate to 090° through 1800 to 2700.
- NOTE: There is a potential for a shift in wind direction Page 19 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont)
FIGURE 3.4 Sample Air Temperature, Delta Temperature and Sigma Theta Trace Control Room Scale/Trace A - Temperature Scale/Trace B - 100' AT Scale/Trace C - 200' AT Scale/trace D - Sigma Theta Delta temperature (AT) scales in OF.
z I 15-minute data segment Ambient temperature scale in OF.
> (Multiply by 10 for data points below 0Q and above 900).
SSigma Theta (o-G) scale.
Page 20 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont)
FIGURE 3.5 Sample Wind Speed and Wind Direction Trace Control Room and TSC Scale/Trace A - Wind Speed Scale/Trace B - Wind Direction
-*- Wind direction scale (0-3600) 2 31 i0 Wind speed and direction r (Cardinal points) scale
- 1n D Pr*cD.1
> Wind speed scale (0-100 mph) 20 46 60 I0 u
- 1 I
} 15-minute data segment T i1BThYViTiE Iii 4. L 4.
10 -ie S. ..
i-7[!-
D ..
.LrJ kLYj 20 mph 20 mph 90° 5 mph/drtsion - 7 mph/division 300/dmslon Page 21 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont)
TABLE 3.6 - Stability Classification Chart 2 3 4 5 6 PASCAL TEMP CHANGE a, DEGREES TEMP CHANGE STABILITY TURBULENCE STABILITY WITH HEIGHT, RANGE OF WITH HEIGHT, CLASSIFICATION CLASS CLASS oFI72ftf" VALUES' 2' oF/168fte3' (100 ft. AT)
Extremely Unstable A AT/AZ <-0.75 22.5 _<.7 ATIAZ < -1.75 Moderately Unstable II B -075 < AT/AZ < -0 67 17.5<_ o < 22.5 -1.75 < ATIAZ <-1.57 Slightly Unstable Il C -067 < AT/AZ < -0.59 12.5 < a, 17.5 -1.57 < AT/AZ < -1.38 Neutral IlI D -0.59 < AT/AZ < -0.20 7.5 < o,, < 12.5 -1.38 < AT/AZ <-0.46 Slightly Stable IV E -0 20 < AT/AZ < 0 59 3 8 _< , < 7.5 -0.46 < ATIAZ < 1.38 Moderately Stable IV F 059 < AT/AZ < 1.58 2.1 _<a < 38 1.38 < AT/AZ < 3.69 Extremely Stable IV G 1.58 < ATIAZ I , < 2.1 3.69 < AT/AZ (1) Adjusted to correspond to the AT measured between the 30-foot and 100-foot levels on the main tower.
7 5 degrees (2) Note on symbol convention "3.8 <oG<7.5" means that oa is greater than or equal to 3 8 degrees but less than (3) Adjusted to correspond to the AT measured between the 30-foot and 200-foot levels on the main tower.
ATMOSPHERIC STABILITY CHARACTERIZATION A. (I) Mid-afternoon only, with clear skies or skies with very few thin clouds; late spring to early fall, winds usually are below 6 miles per hour.
B. (II) Late morning to mid-afternoon only, with clear or partly cloudy skies; mid spring to mid-fall, winds are usually below 9 miles per hour.
C. (II) Late morning to late afternoon only, with partly cloudy skies; spring through fall, wind usually are below 11 miles per hour.
D. (Ill) All daytime, with overcast or partly cloudy skies or early morning and late afternoon with clear or partly cloudy skies, all night time with overcast skies or partly cloudy year round, winds are moderate to high (greater than 6 miles per hour).
E. (IV) Typically night time only, with thin overcast or partly cloudy skies, all year round, winds less than 10 miles per hour.
F. (IV) Typically night time only, with clear to partly cloudy skies, all year round, winds less than 7 miles per hour.
G. (IV) Typically night time only, with clear skies or very few thin clouds all year round, winds less than 5 miles per hour.
Page 22 EPIP-EPP-08 Rev 13
ATTACHMENT 3: (Cont)
Table 3.7: MANUAL MET DATA WORKSHEET Date/Time Release Source of Data Wind Wind Stability Height (circle one) Direction Speed Class (circle one) (degrees) (mph)
Elevated!Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/G round EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMSIStrip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Elevated/Ground EDAMS/Strip Chart/Other Page 23 EPIP-EPP-08 Rev 13
ATTACHMENT 4: RELEASE RATE DETERMINATION Sheet 1 of 8 1.0 METHOD
- a. Access-the EDAMS Computer using Attachment 2 of this procedure.
- b. Select the "EDAMS" Icon.
- c. Select "Release Rate Calculations"
- d. IF Unit 1 was selected, go to Section 2.0 of this Attachment.
- e. IF Unit 2 was selected, go to Section 3.0 of.this Attachment.
- f. Assess all calculated release rates against Tech Spec limits by implementing Attachment 4a.
2.0 UNIT 1 METHODS 2.1 OGESMS
- a. Select monitor (7, 8, lOa or lOb)
NOTE: Monitor 7 = indicator 112-07A
- Monitor 8 = indicator 112-08A Monitor lOa = indicator RN1OA Monitor lOb = indicator RN1OB
- b. Enter time that reading was obtained (using 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format)
- c. Enter monitor reading (cpm for monitors 7 or 8, cps for monitors lOa or lOb). Use J panel readings or the following computer points:
- monitor 7, use E334
- monitor 8,*use E335
- monitor 10a,'-use E488
- monitor lOb, use E489
- d. Enter process computer calibration factor. If unavailable, use default values below:
- 4.4E-8 for 7 or 8
- 4.4E-7 for 10a or lOb
- e. Enter Stack Flow (kcfm). Use J Panel OR computer point C320 or calculate from Table 4.1.
- f. Hit the "F9" key.
- g. Print results.
Page 24 EPIP-EPP-08 Rev 13
ATTACHMENT 4: (Cont)
Sheet 2 of 8 2.t Stack Teletector
- a. Enter the time that the readi'ng' was obtained (24-hour format).
- b. Enter the monitor reading (mrem/hr):
- c. Enter the calibration factor. If unavailable, use default value of 0.5.
- d. Enter Total Stack Flow (kcfm). Use computer point C320 or calculate from Table 4.1.
- e. Hit the "F9" key.
- f. Print the results.
2.3 Grab Sample-(Noble Gas)
CAUTION In,using grab samples to determine release rate, the results may be invalid if significant-changes in source terms have occurred since the sample was taken.
- a. Enter the time that the reading was obtained (24-hour format).
- b. Enter total Noble Gas concentration (juCi/cc) (for EDAMS) OR the concentration of each isotope (tiCi/cc)(for Raddose).
- c. Enter Total Stack Flow (kcfm). Use computer point C320 or calculate from Table 4.1.
- d. Hit the "F9" Key.
- e. Print the results.
Page 25 EPIP-EPP-08 Rev 13
ATTACHMENT 4: (Cont)
Sheet 3 of 8 2.4 Back Calculation NOTE: Use back calculation of downwind survey team data to determine releise rate when no other method is available, AND to verify calculated release rates.
- a. If this method is to be used to make an initial determination of release rate, then back calculate using EDAMS (not Raddose). This value can then be input into Raddose in accordance with Attachment 5 of this procedure.
- b. Enter the time that the reading was obtained (24-hour format).
- c. Enter the wind speed (mi/hr). Use the method described in Attachment 3.
- d. Enter "E" for elevated/stack or "G"for ground/vent release.
- e. Enter the stability class (A-G).
- f. Enter the three foot closed window reading from the ion chamber (mrem/hr). If readings are in CPM, then convert using 3500 CPM = 1 mrem/hr, or other appropriate conversion constant for the detector being used.
- g. Enter the downwind distance that the above reading was obtained.
- h. Hit the "F9" key.
- i. Print the results.
2.5 UFSAR CAUTION This selection is only appropriate if no other sources of data are available (including downwind survey data) AND the accident conditions are identical to those described in the UFSAR for the accident selected.
NOTE: Input from the Control Room, TSC or EOF Technical Staff may be necessary to select the FSAR accident type that most closely describes the conditions being experienced.
- a. Select the accident being experienced or projected (Use Attachment 5, Table 5.1).
- b. Print results.
Page 26 EPIP-EPP-08 Rev 13
ATTACHMENT 4: (Cont)
Sheet 4 of 8 2.6 Containment High Range Monitor NOTES: 1. This method is only valid'if the monitor is able to "see" the
-release. Therefore, consult Operations personnel on the validity of monitor readings.
- 2. The following may be used for this calculation:
ft 3
- Unit 1 primary containment free-air volume = 314,000
- Tech Spec leakage from primary containment = -1%/day
- a. Enter the monitor ID or number.
- b. Enter the time that the reading was obtained (24-hour format).
- c. Enter the date that the reading was obtained.
- d. Enter the time of reactor shutdown (24-hour format).
e.- Enter the date that the reactor was shutdown.
- f. Enter the monitor reading (rem/hr). Use computer point E467 or E468.
- g. Enter the expected flow rate (kcfm) to the environment. Consult with Operations personnel if needed.
- h. Hit the "F9" key.
- i. Print results.
2.7 For liquid releases, consult N1-CSP-M204 2.8 Severe Accident Source Team (SAST)
NOTE: SAST assumes 20% fuel damage.
- a. Select "Containment Leak Rate"
- 1. Enter the estimated leak'rate from containment.
- b. Select "ThroughI Filters" option.
- 1. If the source-team travels through any filters, select "Y".
Otherwise select "N".
Page 27 EPIP-EPP-08 Rev 13
ATTACHMENT 4: (Cent)
Sheet 5 of 8 2.8 (Cant)
- c. Select the "Sprays On" option.
- 1. If containment sprays are in use, select "Y". Otherwise select "N".
- d. Select the "Hold-Up Time"
- 1. Enter the estimated time that the source team remained in containment before release.
3.0 UNIT 2 METHODS 3.1 GEMS
- a. Enter the time that the reading was obtained (24-hour format).
- b. Enter "S" if this is a stack reading or "V" if it is a vent reading.
- c. Enter monitor reading (gCi/s). Use GEMS readings from SPDS display or the 882 panel. If offscale, use GEMS computer.
- d. Hit the "F9" key.
- e. Print results.
3.2 Grab Sample (Noble Gas)
CAUTION In using grab samples to determine release rate, the results may be invalid if significant changes in source terms have occurred since sample was taken.
- a. Enter the time that the reading was obtained (24-hour format)
- b. Enter total Noble Gas reading (/pCi/cc) (for EDAMS) OR the concentration of each isotope (pCi/cc)(for Raddose).
- c. Enter total stack or vent flow (kcfm). Calculate from Figure 4.2 or 4.3.
- d. Hit the "F9" Key.
- e. Print the results.
Page 28 EPIP-EPP-08 Rev 13
ATTACHMENT 4: (Cont)
Sheet 6 of 8 3.3 Back Calculation "Use Section 2.4 of this Attachment.
3.4 USAR Use Section-2.5 of this Attachment.
3.5 'Containment High Range Monitor NOTES: 1. This method is only valid if the monitor is able to "see" the release. Therefore, consult Operations personnel on the validity of monitor readings.
- 2. The following may be used for this calculation:
3 497,000 ft
"* Unit 2 primary containment free-air volume
"* Tech Spec leakage from primary containment =-1%/day the Use Section 2.6 of this Attachment. Monitor readings are available on DRMS system (RMS1a,b,c or d),-the SPDS-display or the 880 panel.
3.6 For liguid releases, consult N2-CSP-LWS-M203 3.7 Severe Accident SourceTeam See Section 2.8 of this Attachment.
Page 29 EPIP-EPP-08 Rev 13
ATTACHMENT 4: (Cont)
Sheet 7 of 8 TABLE 4.1 UNIT 1 STACK: FAN CONFIGURATION Fan Nominal Computer Workspace Flow Point (KCFM)
Drywell Vent, Purge, and Fill Line 10 Turbine Building High Speed Fan 170 Turbine Building L6w Speed Fan 120 Reactor Building High Speed Fan 70 Reactor Building Low Speed Fan 35 Waste Building 8 Waste Building Extension 5.3 Offgas Building 6 Reactor Buildirng Emergency Ventilation 1.6 RSSB Extension 10.25 Total. Stack Flow C320 TABLE 4.2 UNIT 2 STACK: FAN CONFIGURATION Fan Nominal Computer Workspace Flow Point (KCFM)
CST Room 2.2 Stack Substructure 1.4 Turbine Building - 1 fan 40 Turbine Building - 2 fans 80 Standby Gas Treatment 4 T-*tat Sthack F16 N..
Page 30 EPIP-EPP-08 Rev 13
ATTACHMENT 4: (Cont)
Sheet 8 of 8 TABLE 4.3 UNIT 2 VENT: FAN CONFIGURATION Fan Nominal Computer Workspace Flow Point (KCFM)
Turbine Building 250' and 306' Decon 3.3 Rm Fan Radwaste Liner Fan 0.8 Radwaste Tank Fan 4.9 :.::::.. .
Radwaste Building - 1 fan 47.8 Radwaste Building - 2 fans 95.6 Aux Boiler -23 .
Refueling Floor Above 70 Refueling Floor Below 70
.Total Vent Flow ."
Page 31 EPIP-EPP-08 Rev 13
ATTACHMENT 4A: DETERMINATION OF PERCENT OF TECHNICAL SPECIFICATION RADIOLOGICAL RELEASE Procedure:
- 1. Determine release rate in accordance with Attachment 4 of this procedure.
- 2. Complete the following as applicable:
- a. Unit 1 Stack release:
- 1. assume calculated stack release rates represent Noble Gas release rates
- 2. calculate:
% Tech Spec =
Noble Gas release rate (Ci/sec) x 8850 = % Tech Spec
- b. Unit 1 Emergency Condenser (EC) Vent release:
- 1. calculate:
% Tech Spec-=
EC Vent monitor reading (mr/hr) x 5 = % Tech Spec =
- c. Unit 2 Stack release:
- 1. assume calculated stack release rates represent Noble Gas release rates
- 2. calculate:
% Tech Spec =
Noble Gas release rate (Ci/sec) x 1042 = % Tech Spec =
- d. Unit 2 Vent release:
- 1. assume calculated stack release rates represent Noble Gas release rates
- 2. calculate:
% Tech Spec =
Noble Gas release rate (Ci/sec) x 3704 = % Tech Spec =
- 3. IF any % Tech Spec from any source is > 100% Tech Spec, THEN advise the SSS/ED or the ODAM that a release that exceeds Tech Specs has taken place.
Page 32 EPIP-EPP-08 Rev 13
ATTACHMENT 5: REFINED DOSE ASSESSMENT AND PROTECTIVE ACTIONS Sheet 1 of 6 1.0 DOSE ASSESSMENT 1.1 General Considerations 1.1.1 The dose assessment program is called RADDOSE.
1.1.2 Meteorological data is automatically sent to RADDOSE by the Meteorological Monitoring System (MMS). The user can use this data or manually inputdata.
1.1.3 Source term and release rate determination is identical to that described in Attachment 4.
1.2 Dose Assessment Procedure NOTE: The dose assessment model has many capabilities beyond those used in this procedure. Use the 'EDAMS Operators Manual" (available in the EOF) for further reference.
1.2.1 Log on to EDAMS computer using Attachment 2.
1.2.2 Select the affected Unit "Dose Assessment Model."
1.2.3 Utilize "EDAMS Data Entry Form", Attachment 5.2, or equivalent.
1.2.4 Select "Begin New Incident" at the options.
1.2.5 Select "Yes" to erase all previous data when prompted.
1.2.6 Enter the following at the Accident Scenario Definition screen:
- a. Reactor Trip Date. This is the date that the reactor scrammed or was manually tripped. IF the reactor is not shut down, enter tomorrow's date.
- b. Reactor Trip Time (24-hour format). This is the time that the reactor scrammed or was manually tripped.
- c. Release Date. This is the date that the release to the atmosphere began, or is projected to begin.
- d. Release Time (24-hour format). This is the time that release to atmosphere began or is projected to begin.
- e. Enter the lake temperature (degF) If unknown, hit "Enter" and historical data will be entered.
- f. Enter the initials of the user (two or three initials).
- g. accepT entrieso Verif make-any necessary changes, and select to continue.
Page 33 EPIP-EPP-08 Rev 13
ATTACHMENT 5: (Cont)
Sheet 2 of 6 1.2.7 Select "Enter/Edit Source Term Data" from the EDAMS main menu.
NOTES: 1. Use Attachment 4 t6 obtain the information needed to complete this section.
- 2. The preferred source of release rate data is the actual isotopic distribution, if available.
- a. Select "Accident Type" by choosing the accident that most suits the current conditions. Use Table 5.1 in making the choice.
- b. Select "Y" for elevated releases OR "N" for ground releases when asked, "Is this release Elevated?".
NOTE: "Elevated" releases are releases from the stack. "Ground" releases are from any other release point.
- c. Select the "Method" used to determine the release rate by selecting the highlighted cell or by hitting the "F2" key and selecting.
- 1. Utilize Attachment 4 Section 2.0 for Unit 1 releases.
- 2. Utilize Attachment 4 Section 3.0 for Unit 2 releases.
- d. Select the Iodine release rate "Method" by selecting the highlighted cell or by hitting "F2" key. Utilize one of the following:
- 1. Grab Sample: This section can be used if concentrations (liCi/cc) by isotope, and associate flow rate are available
- a. obtain sample analysis results from TSC
- b. enter concentration of each isotope
- c. enter flow rate (cfm) associated with sample NOTE: This method will override previously input Total Release Rate method
- 2. Direct: This selection utilizes direct entry of the release rate (in Ci/Sec) obtained by any method, including the following Page 34 EPIP-EPP-08 Rev 13
ATTACHMENT 5: (Cont) 1.2.7d (Cont) Sheet 3 of 6
- a. Use of downwind survey team data
- 1. determine the representative I/NG ratio using field data and the methodology described in EPIP-EPP-07 2.' multiply the NG or total release rate (obtained from Attachment 4) by the I/NG ratio
- 3. enter the Iodine release rate in the appropriate col umn
- 3. Ratio: This selection utilizes the UFSAR/USAR
'I/NG ratio and multiplies it by the Total Release Date
- 4. UFSAR: CAUTIONS:
- 1. This selection should only be used if none of the above methods are not currently or projected to be available.
It'is appropriate to wait for field data
- 2. This selection will override any previously input Total Release Rate
- e. Up to three Accident Types (and therefore three release paths) can:be entered. To enter additional release paths,"repeat Steps a - d above. When all applicable accident types have been entered, proceed to the next step.
- f. Upon completion of this screen, verify data and make any necessary changes'bbefore "Accept".
1.2.8 The user will bequeried only for the meteorological data required. Enter meteorological, data as required:
- a. Select "Enter/EditMeteorological Data", Elevated or Ground as appropriate.
- b. If the MMS is available, the data will be automatically displayed for the current time step.
- 1. Select "Ieque`ry"MMS".
- 2. Select "Accept" as necessary.
- c. If thee MMS Jis -una'vailable, then enter both ground and elevated met data obtained from alternate sources, as outlined in Attachment 3 of this procedure and select "Accept" Page 35 EPIP-EPP-08 Rev 13
ATTACHMENT 5: (Cont)
Sheet 4 of 6 1.2.9 Select "Perform Calculations" from the EDAMS main menu.
NOTE: The purpose of the following steps is to determine the projected avoidable dose resulting from the incident.
CAUTION Any calculations performed on actual data shall be verified. The ODAM may act as the checker-for calculations performed by the Rad Assessment Staff.
- a. The map of the 10 mile Emergency Planning Zone (EPZ) will appear with centerline dose rates when the calculation is complete.
- b. Select- "Continue" to go to the output menu.
- c. Select "Continue Calculations" from the output menu.
- d. Select "Perform Forecast" from the RADDOSE main menu.
- e. Verify meteorology and source term data as required.
- f. Enter "Forecast Period" (i.e. - release duration). Use 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as a default value.
- g. Select "OK".
- h. After the forecast map appears "Continue" to go to the output menu.
- i. Select "Go to Report Menu".
- j. Select "Print 10-Mile ERPA Map".
- k. Select "Print Complete Dose/Dose Rate Report".
Q. Attach results ofStep 1.2.9.j and k to EDAMS Data Entry Form, Attachment 5.2 or equivalent.
M. Verify ,that any results are supported by radiological and plant conditions. Consider:
- Core-damage
"* Drywell high range monitor readings
"* Effluent monitor readings
"* Inplant radiological conditions
"* Containment hydrogen monitor readings
- n. Document the verification of the calculation using the signature lines on Figure 5.2 or equivalent.
Page 36 EPIP-EPP-08 Rev 13
ATTACHMENT 5: (Cont)
Sheet 5 of 6 1.3 If it is desired to utilizeEDAMS to track near real-time doses, then perform' the following steps:
CAUTION The results of this step shall NOT be utilized to determine PARs.
1.3.1 Enter accident, source term and meteorological data in accordance with Steps 1.2.1 through 1.2.8 of this attachment.
1.3.2 Select "Perform Calculations" from the EDAMS main menu.
1.3.3 ;Enter meteorological and source term data at 15 minute intervals.
1.3.4 Determine dose at any time by viewing displayed 10 mile ERPA
,map.
2.0 REFINED PROTECTIVE ACTIONS 2.1 These actions are initiated for the purpose of verifying the adequacy of PARs made using Attachment I of this procedure OR to develop PARs using projected doses obtained from Attachment 5, Step 1.2.9 of this procedure.
2.2 In determining PARs based on dose assessment, carefully consider factors such as release duration and'Evacuation Travel Time Estimates (ETTE). (For example, puff releases may yield doses in excess of
'Protective Action Guidelines for an evacuation, but the plume will pass before an evacuation could be completed). ETTEs are available in the EOF.
NOTE: County and State PARs take many factors into account that NMP procedures do not (i.e. - road conditions, special population needs, evacuation scenarios, and shelter'vs evacuation doses). tTherefore, differences in PARs may occur. The ODAM must account for differences in PARs, when those differences exist.- This can be accomplished via consultation with County~and State representatives in the EOF as to the assumptions used in their dose calculations and PAR development.
2.3 Obtain dose projection for each ERPA.
2.3.1 PARs are listed on the 10 mile ERPA map obtained per Attachment 5, Step 1.2.9. j.
Page 37 EPIP-EPP-08 Rev 13
ATTACHMENT 5: (Cont)
Sheet 6 of 6 2.3.2 The following criteria are used in determining the PAR for each ERPA.
Evacuate > I > 5 2.3.3 Record the PAR for each ERPA on the Part 1 Notification Form and give to the ED/RM for approval.
2.3.4 PARs that have been made previously must be accounted for when PARs are revised. For example, if a PAR to evacuate an ERPA was previously made to the State/County and that PAR does not appear on a revised map from 1.2.9.j, that PAR must still be included on the revised recommendation to the State/County.
2.3.5 If projected doses exceed values listed in Attachment 5 Step 2.3.2 for distances greater than 10 miles, PARs shall be made using convenient geographic boundaries (such as townships).
TABLE 5.1 - FSAR/USAR ACCIDENT TYPE Noble. Go oine Anayze "Icc*ciun*Ltype*e : Release Rate (Ci/S) Release Rate (Cils) Release Point Unit 1:
DBA Loss of Coolant 5.50E+O 4.53E-3 Elevated Control Rod Drop 2.51E + 1 6.03E-5 Elevated Refueling Accident 3.78E-2 3.84E-5 Elevated Steam Line Break 6.36E+0 4.86E+ 1 Ground Loss of Coolant (Realistic) 1.79E-3 1.00E-6 Elevated Unit 2:
DBA Loss of Coolant 1.03E + 1 2.03E-1 Elevated Control Rod Drop 4.22E-2 4.70E-4 Ground Refueling Accident 1.77E + 1 1.65E-1 Ground Steam Line Break 3.64E + 0 1.22E+2 Ground Rad Gas Waste System Leak 4.06E+O 0.00 Ground Instrument Line Failure 0.00 2.17E-2 Ground Fuel Cask Drop 2.06E+0 2.68E-3 Ground Loss of Coolant (Realistic) 1.05E-2 2.38E-5 Elevated Page 38 EPIP-EPP-08 Rev 13
ATTACHMENT 5.1: CHRO._' GICAL RELEASE RATE LOG
.... LOG'.......................................................
Survey Location:eted By:
Release Log Effluent M onitor DataAsi EnEnvironmental Sampling Data
,, ! .... n dTime Assigned T m Assigned Interval Gamma Wind Transit Est. Time of Release Release Time of Release Duration Dose Rate of Survey Rate Distance Speed 'Time Release Rate Rate rn Monito Monitor from Site (Cilsec) Ci/sec) 0 Time Location (mR/hr) (MI) (mph) (min)
Readin System (Ci/sec) Release
- Est. Time of Release Survey Time - Transit Time Notes: 4* Transit Time (min) = (Distance/Wind Speed) x 60 min/hr EPIP-EPP-08 Rev 13 Page 39
ATTACHMENT 5.2: EDAMS DATA ENTRY FORM "What If" Actual Data (Checker Requiredl)
Release:
Rx Trip: Date: _ Time: Release Duration (Hr):
0] Unit 1 El Unit 2 Accident Tvoe o Release Point (Circle One)
Rees Poin X f One)
Acdn Containment DBA Elev/Grd Flow Rate Control Rod Drop Elev/Grd Refueling Accident Elev/Grd Method Steam Line Break Elev/Grd Loss of Coolant Elev/Grd Monitor Reading Rad Gas Waste System Elev/Grd Inst. Line Failure Elev'/Grd Iodine Method Fuel Cask Drop Elev/Grd Severe Accident Elev/Grd Iodine Monitor Met Data: El Automatic El Manual (Below) Lake Temp _F or Default SElevated [FGround II
'1 lWind Speed (mi/hr) __
Wind Direction (from- degrees), __
Stilty (A-G) I _______________ _______________
Temperature (OF) II 1Precipitation (in/15 min) II Attach:
- Map from color printer 0 "Complete Dose/Dose Rate" report Misc:
Calculations Performed By:
Calculations Verified By:
Page 40 EPIP-EPP-08 Rev 13
NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-EPP-09 REVISION 03 DETERMINATION OF CORE DAMAGE UNDER ACCIDENT CONDITIONS Approved by: 2D3te 2 G. L.Detter Generta'ager Support Services Date THIS IS A FULL REVISION Effective Date: 09/30/2002 PERIODIC REVIEW DUE DATE: SEPTEMBER, 2003
LIST OF EFFECTIVE PAGES Page No. Changie No. Page No. Chanae No. Page No. Change No.
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Page i EPIP-EPP-09 Rev 03
"I TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE........................................................................................................................................ 1 2.0 RES PO NSIB ILITIES ........................................................................................................................ 1 3.0 ESTIMATION OF CORE DAMAGE ............................................................................................ 1 4.0 DEFIN ITIONS .................................................................................................................................. 4
5.0 REFERENCES
AND COMMITMENTS ...................................................................................... 5 6.0 RECO RD DISPO SITIO N.................................................................................................................. 6 ATTACHMENT 1: CORE DAMAGE ESTIMATE USING RELEASE INTO CONTAINMENT AND ASSOCIATED RADIATION LEVELS WITH SPRAYS ON ......................................... 7 ATTACHMENT 2: CORE DAMAGE ESTIMATE USING RELEASE INTO CONTAINMENT AND ASSOCIATED RADIATION LEVELS WITH SPRAYS OFF ....................................... 8 ATTACHMENT 3: PERCENTAGE OF H2 INCONTAINMENT RELATIVE TO CORE DAMAGE .................. 9 ATTACHMENT 4: CORE DAMAGE DETERMINATION ..................................................................... 10 ATTACHMENT 5: PARAMETERS FOR REFERENCE PLANT AND NMP ........................................... 14 ATTACHMENT 6: CORE INVENTORY OF MAJOR FISSION PRODUCTS INA REFERENCE PLANT OPERATED AT 3651 MWT FOR THREE YEARS ................................................... 16 ATTACHMENT 7: REFERENCE PLANT FISSION PRODUCT CONCENTRATIONS INREACTOR WATER AND DRYWELL GAS SPACE DURING REACTOR SHUTDOWN UNDER NORMAL CONDITIONS ......................................................................................... 17 ATTACHMENT 8: REFERENCE PLANT RATIOS OF ISOTOPES INCORE INVENTORY AND FUEL GAP .............................................................................................................................. 18 ATTACHMENT 9: REFERENCE PLANT BEST-ESTIMATE FISSION PRODUCT RELEASE FRA CTIONS ................................................................................................................. 19 ATTACHMENT 10: 1-131 CONCENTRATION INPRIMARY COOLANT .............................................. 20 ATTACHMENT 11: Cs-137 CONCENTRATION INPRIMARY COOLANT .......................................... 21 Page ii EPIP-EPP-09 Rev 03 ,
TABLE OF CONTENTS (Cont)
SECTION PAGE ATTACHMENT 12: Xe-133 CONCENTRATION INPRIMARY COOLANT .......................................... 22 ATTACHMENT 13: Kr-85 CONCENTRATION INPRIMARY COOLANT ............................................ 23 ATTACHMENT 14: TEMPERATURE CONVERSION TABLE .............................................................. 24 ATTACHMENT 15: CORE DAMAGE ESTIMATE BASED ON 1-131 AND XE-133 CONCENTRATIONS.. 25 ATTACHMENT 16: FISSION PRODUCT INVENTORY CORRECTION FACTOR FOR 1-131 .............. 27 ATTACHMENT 17: FISSION PRODUCT INVENTORY CORRECTION FACTOR FOR XE-133 .......... 28 Page iii EPIP-EPP-09 Rev 03
1.0 PURPOSE The purpose of this procedure is to provide an initial estimate of core damage (e.g. percent clad failure or percent of fuel melted) by using containment radiation monitor readings or using containment hydrogen values or from the measured fission product concentrations ineither the reactor water or containment gas samples taken under accident conditions. Subsequent refinement of core damage estimates can be achieved by a Ba, Sr, La and Ru analyses.
2.0 RESPONSIBILITIES 2.1 The Chemistry and Radiation Protection Departments are responsible for performing sampling and analysis of reactor water and containment atmosphere as necessary to support the calculations contained within this procedure.
2.2 Reactor Engineering is responsible for performing fission product inventory correction factor calculations for calculating percent of core damage based on the isotopic data in accordance with the methodology contained within this procedure.
2.3 The TSC Reactor Analyst is responsible for performing an initial estimate of core damage.
2.4 THE STA may use this procedure to perform an initial estimate of core damage. (Attachment 1 to 2).
3.0 ESTIMATION OF CORE DAMAGE NOTE: Substantial increases (orders of magnitude) inradiation levels, as determined by radiation monitor readings (e.g., Containment High Range Monitors), can provide an early estimate of the extent of core damage and should be used. However, the following should be considered:
"* The release may bypass the monitor.
"* Monitors may be influenced by a source not intended to be monitored.
" Areas monitored may not be representative of the entire containment.
" Calibratiori assumptions rmay not match accident conditions.
- Shielding or other design factors may have been incorrectly considered.
- Monitor may show high, low, or center range ifit fails.
- Monitor may be read incorrectly. "
- Shine from low RPV level may affect ri'adings.
Page 1 EPIP-EPP-09 Rev 03
3.1 The TSC Reactor Analyst or STA may:
Perform core damage assessment using one of the following methods listed in order of preference:
3.1.1 Compare Attachment 1 or 2 as appropriate, to the actual containment high range radiation monitor readings.
3.1.2 Compare Attachment 3 to the actual containment hydrogen readings (ifavailable) estimate core damage. Determine the hydrogen concentration (%)inthe primary containment by:
"* For Unit 1 Reference #11 and #12, H2/02 monitoring systems or by gas chromatographic analysis of a containment atmosphere sample.
" For Unit 2 reference HJO2 monitors CMS-66A, CMS-66B, CMS-73A and CMS-73B H2/0 2 (or use SPDS) or by gas chromatographic analysis of a containment atmosphere sample.
NOTE: The following step isto be performed by the TSC Reactor Analyst only:
3.1.3 Following receipt of chemistry reactor coolant and/or atmosphere ....sample analysis data, perform the calculations in Attachment 4 and compare results to Attachment 10 through 13 as appropriate.
3.1.4 Following performance of one of the above three methods, the TSC Reactor Analyst or STA should provide an initial estimate of core damage to the Technical Data Coordinator or to the SSS/ED as appropriate.
3.2 During event recovery, the TSC Rx Analyst should provide for damage assessment refinement by performing:
3.2.1 Ba, Sr, La and Ru Analyses
- a. Obtain Gamma Isotopic analysis of reactor water from Chemistry.
- b. Determine the concentration (Cm 1 inpCi/g) of those less~volatile elements which are indicators of core melt (i.e., Ru-1 03, Sr-91, Sr-92, Ba-1 40, La-1 40) from the isotopic analysis printout and which can be determined from the isotopic.
- c. Calculate the normalized concentration of each isotope, i, inthe reference plant in accordance with Attachment 4, Step 2.8.
ref Page 2 EPIP-EPP-09 Rev 03
3.2.1 (Cont)
- d. Calculate the fraction of each isotope released from the core, FRI (approximately equal to the fraction of core meltdown) using the equation:
Ref Fri = C*, x ( 3.920 E9g/lI) where 3.920 E9 = Total primary coolant mass (g), reference plant, and Ref I,= Total core inventory of isotope i in the reference plant (see Attachment 6)
- e. Provide results of refined assessment to the Technical Data Coordinator.
3.2.2 Continually, assess the status of the critical safety functions by answering the following questions:
"* Is the plant sub-critical (shutdown)? How is this confirmed?
"* Isthe core covered now and will it be inthe long term? How is this confirmed?
"* Isthe amount of water being injected into the primary or secondary system sufficient to remove the decay heat? Use Method A.1 to confirm that there is sufficient injection of water.
"* Is decay heat being removed to the environment? How is this confirmed?
"* What is the status of the vital auxiliaries? DC power? AC power?
3.2.3 Ifany of the critical safety functions are not being met or are degraded, estimate when the core may be uncovered.
3.2.4 Ifthe core is projected to be uncovered, inform the Technical Data Coordinator. Continue to monitor containment parameters for indications of core damage.
3.2.5 Additionally, the TSC Reactor Analyst should monitor the following indications for detecting imminent uncovering of the reactor core.
"- I Page 3 EPIP-EPP-09 Rev 03
NOTE: Consider the reliability of the indications or instrument readings during accident conditions as discussed below.
Water level can be used under some accident conditions to confirm that insufficient water isbeing injected to protect the core and to estimate the time at which the core will be uncovered. Consider the following limitations:
"* The lower limit of the water measurement system is at or above the level at which core heat-up begins (20% uncovered).
"* High drywell temperature (e.g., LOCA) can cause the reactor water level to read erroneously high.
"* During low pressure accidents, the water level can read erroneously high.
"* Mechanical Yarway instruments may indicate a false on-scale water level at about 1 ft above the top of core ifthe actual water level fell below the lower end of the instrument range.
3.2.6 Ifthere are indications of imminent uncovering of the core, inform the Technical Data Coordinator. Continue to monitor containment parameters for indications of core damage.
3.2.7 Ifthere are no indications of imminent uncovering of the core, provide an assessment of critical safety functions and core status to the TSC Tech Data Coordinator 3.2.8 When provided with a reactor coolant sample analysis, the TSC Reactor Analyst should use Attachment 4, Core Damage Determination, to provide a more complete analysis of core damage.
4.0 DEFINITIONS 4.1 Reference Plant The estimation of core damage will be calculated by comparing the measured concentrations of major fission products ingas and/or liquid samples, after appropriate normalization, with reference plant data from a BWR-6/238 with Mark Ill containment. Fission product inventories inthe primary system were calculated based on postulated design basis loss-of-coolant accident conditions after three years (1095 days) of continuous operation at 3651 Mwt or 102% of rated power by using a computer code developed at Los Alamos and adopted to the GE computer system.
4.2 Gap release The release into containment of all the fission products inthe fuel pin gap (see Attachment 9) after the fuel cladding has failed from being uncovered for more than 15 min.
Page 4 EPIP-EPP-09 Rev 03
4.3 Spiked coolant release The release into containment of 100 times the non-noble gas fission products normally found in the coolant.
4.4 Typical (normal) coolant release The release into containment of the fission products normally found in the coolant (see Attachment 6 and 7).
5.0 REFERENCES
AND COMMITMENTS 5.1 Technical Specifications None 5.2 Licensee Documentation 5.2.1 Lin, Chien C, Procedure for the Determination of Core Damage Under Accident Conditions, General Electric Co., NEDO 22215,1982 5.2.2 Nuclear Services Department, Post-Accident Sampling System Evaluation, General Electric, 1983 5.2.3 Stone and Webster Calculation, 12/77, PR (c), 21-V, Attachment C (NMPNS Document Control No. 01457-0869) 5.2.4 DRF 268-DEV-009, unpublished document, General Electric 5.2.5 NMPC Engineering Calculation #S0.0-RX-VOL01, Calculation of Unit 1 Secondary Containment Volume 5.3 Standards, Regulations, and Codes RTM-96, Response Technical Manual 5.4 Policies. Programs, and Procedures None 5.5 Commitments None Page 5 EPIP-EPP-09 I Rev 03
6.0 RECORD DISPOSITION The following records generated by this procedure as the result of an actual declared emergency shall be maintained by Records Management for the Permanent Plant File in accordance with NIP RMG-01:
"* Any calculations or other paperwork generated as the result of performance of this procedure.
"* Attachment 15, Core Damage Estimate Based on 1-131 and Xe-1 33 Concentrations
"* Attachment 16, Fission Product Inventory Correction Factor for 1-131
"* Attachment 17, Fission Product Inventory Correction Factor for Xe-133 Any records generated by this procedure that are not the result of an actual declared emergency are not required for retention inthe Permanent Plant File.
Page 6 EPIP-EPP-09 Rev 03
ATTACHMENT 1:-CORE DAMAGE ESTIMATE USING RELEASE INTO CONTAINMENT AND ASSOCIATED RADIATION LEVELS WITH SPRAYS ON 1 E+06 Release
%Oo rr 1E+04" .5 - "7-- e ........ - -----
.se S 1E+0 4. . .
o0<* 1 + 0 . . . .. . . ... 50. . ... ". ....
100
.<1+O - M25 IE-05 -
50 100 z 1 E-02 -------------- ------------- --E 575 ------- *---
LLI 50% Release 1-E-0 4-------------------- 50 - 75 o E-05---- ----- ----- _ ___ --- ---- --- 22 I I I I _
1E-06I I 1h 24 h 1h 24 h 1h 24 h 1h 24 h In-Vessel Melt* Gap* Spiked Coolant* Normal Coolant*
CORE DAMAGE AND TIME AFTER REACTOR SHUTDOWN NOTE: In-line check source readings should be considered when determining monitor readings.
- NUREG/BR-0150, Vol. 1, RTM-96, Response Technical Manual, Revision 4, March 1996 Page 7 EPIP-EPP-09 Rev 03
__JL_
ATTACHMENT 2: CORE DAMAGE ESTIMATE USING RELEASE INTO CONTAINMENT AND ASSOCIATED RADIATION LEVELS WITH SPRAYS OFF ti 0
I-z 0
IL z
w z-.1 0
0--
1h 24h 1h 24h 1h 24h 1h 24h In-Vessel Melt* Gap* Spiked Coolant* Normal Coolant' CORE DAMAGE AND TIME AFTER REACTOR SHUTDOWN NOTE: In-line check source readings should be considered when determining monitor readings.
- NUREG/BR-0150, Vol. 1, RTM-96, Response Technical Manual, Revision 4, March 1996 Page 8 EPIP-EPP-09 Rev 03
AT[ACHMENT 3:
Percentage of H2 in containment relative to core damage 50 4
Cu 40 60*
C 30 U
20 10 01 I*L* -in Containment Page 9 EPIP-EPP-09 Rev 03
ATTACHMENT 4: CORE DAMAGE DETERMINATION Sheet 1 of 4 1.0 Description Gas/water samples taken from the Post-Accident Sampling System are analyzed for major fission product concentrations with a Jupiter Gamma Spectroscopy System or equivalent. After incorporation of appropriate decay and normalization correction factors to the isotopic analysis results for 1-131, Cs-1 37, Xe-1 33 and Kr-85, the extent of fuel or cladding damage can be determined by reference to Attachment 10 through 13. The ratios of isotopes released from either the fuel gap or from the molten fuel are significantly different as shown inAttachment 9.
Inorder to use the correct curve on Attachment 10 through 13, the release mode must be determined. Using the ratios of noble gas concentrations to Xe-1 33 concentration and the ratios of iodine isotopes to 1-131 concentration, either a fuel melt or cladding failure can be determined.
(Refer to Step 3.0) 1-131 and Cs-1 37 samples are obtained from reactor water and Xe-1 33 and Kr-85 samples are obtained from primary containment atmosphere. Measurements of Cs-137 and Kr-85 activities are not likely until the reactor has been shut down for longer than a few weeks and most of the shorter-lived isotopes have decayed. This procedure requires only the Xe-1 33 or 1-131 sample results. Long lived Cs-137 and Kr-85 activities may be analyzed ina similar manner when sample results are available.
Furthermore, some less volatile fission products (e.g., Sr, Ba, La and Ru) may also start to migrate from the core as fuel melting starts. Ifthese less volatile elements are found to have unusually high concentrations inthe water sample relative to baseline reactor water concentrations, some degree of fuel melting may be assumed. The isotopes Sr-92 (t 1/2= 2.71h /1.388 MeV) and La-140 (t 1/2= 40.2h/1.597 MeV) ina mixture of fission products should be relatively easy to identify and measure from a gamma spectrum.
2.0 Estimation Procedure 2.1 Obtain samples from the Post-Accident Sampling System in accordance with Unit 1 or Unit 2 Chemistry procedures.
2.2 Using a Jupiter Gamma Spectroscopy System or equivalent, determine the concentrations of fission products, namely 1-131 and Xe-133. (Cwi inwater, Cgi in gas) 2.3 Correct the measured concentrations for sample dilution.
Page 10 EPIP-EPP-09 Rev 03
ATTACHMENT 4: (Cont)
Core Damage Determination Sheet 2 of 4 2.4 Note: Use Attachment 5 for reference plant values.
Correct the measured gaseous activity concentrations for temperature and pressure difference between the sample vial and the containment atmosphere as follows:
Cgi = Cgi (vial) x (P2 T1)/(Pi T2) where:
Cg, (vial) = Sample vial isotopic concentration Cg, = Containment isotopic concentration _
P1 ='Absolute atmospheric pressure (i.e.,14.7 psig)
Ti = Absolute atmospheric temperature (i.e., 2980 K)See Attachment 14 P2 = Absolute containment pressure at time of sample T2 = Absolute containment temperature at time of sample 2.5 Calculate the fission product inventory correction factor, F,, as follows:
Fi, = Inventory inreference plant
- Inventory inoperating plant 3651Mwt [1 -exp(-1 095 A,)]
0 Z[Pj(1 -exp(-AjTj))exp(A-Tj)]
where:
Pj = Steady reactor power operated in period j (Mwt)**
Tj = Duration of operating period j (day)**
0 Tj = Time between the end of operating period j and time of the last reactor shutdown (day of accident) h, = Decay constant for isotope i (day -1)
- In each period, the variation of steady power should be limited to + 20%.
- NOTE: For 1-131 and Xe-1 33, ifoperating steady state for greater than 50 days:
F,= 3651/core thermal power inMW.
Page 11 EPIP-EPP-09 Rev 03
ATTACHMENT 4: (Cont)
Core Damaqe Determination Sheet 3 of 4 2.6 To assist incomputing the fission product inventory correction factor, F11 (Step 2.5), use Attachment 16 and 17. Each worksheet will guide you through the calculation for fission product inventory of the following isotopes:
Attachment 16 = 1-131 Attachment 17 = Xe-133 2.7 Calculate the plant parameter correction factors (FR and Fg), as follows:
Fw = Operating plant coolant mass (g!)*
Reference plant coolant mass (3.920E9g)
Fg = Operating plant primary containment gas volume (cc)*
Reference plant primary containment gas volume (4.OE1Occ)
- Assumes torus down comer submergence of 3 ft. (570,000 gal total). Adjust if necessary to account for HPCI or Containment Spray raw water additions.
Ref 2.8 Calculate the normalized concentrations, C,* or Ret Cgi by using the correction factors as follows:
Ref Cm = (Cw) (F,) (Fw) or Ref Cgi = (Cgi) (F) (Fg) where:
Ref CW, = Concentration of isotope i inthe reference plant coolant (pCi/g)
Ref Cg, = Concentration of isotope i inthe reference plant containment gas (pCi/cc)
C, = Measured concentration of isotope i inthe operating coolant at time, t (PCi/g)
Cgi = Measured concentration of isotope I inthe operating containment gas at time, t (pCi/cc)
Fn = Inventory correction factor for isotope i Fg = Containment gas volume correction factor R= Primary coolant mass correction factor Page 12 EPIP-EPP-09 Rev 03
ATTACHMENT 4: (Cont)
Core Damace Determination Sheet 4 of 4 2.9 Determine the concentrations of the shorter-lived isotopes shown in Attachment 8 (e.g: with a Jupiter Gamma Spectroscopy System or equivalent).
2.10 Correct the measured fission products to the time of reactor shutdown.
2.11 Calculate isotopic ratios where Noble Gas Ratio = Noble aas isotope concentration
- Xe-133 concentration Iodine Ratio = Iodine isotope concentration 1-131 concentration 2.12 Determine release source by comparing results obtained in Step 2.11 to the noble gas and iodine ratios supplied in Attachment 8.
Ref Ref 2.13 Utilize Cw or Cg, to estimafe the extent of fuel or cladding damage from Attachment 10 through 13.
3.0 Sample Concentration (Cwi or Cqi) Averacging Ifthe fission product concentrations are measured separately for the reactor water and suppression pool water or the drywell gas and the suppression chamber gas, the measured concentrations -Cwj of Cgi would be averaged from the separate measurements:
Ci = (Rx water conc)(Rx water mass)+(Pool conc)(Pool water mass)
Reactor water mass + Pool water mass Cgi = (Drywell conc)(Drnwell gas vol)+(Supp chain conc)(Supp chain gas vol)
Drywell gas volume + Suppression Chamber Gas Volume Page 13 EPIP-EPP-09 Rev 03
ATTACHMENT 5: PARAMETERS FOR REFERENCE PLANT AND NMP Sheet 1 of 2 The pertinent plant parameters for the reference plant and the Nine Mile Point plant are given below:
Ref. Plant NMP-l NMP-ll Rated reactoir thermal power 3579 Mwt 1850 Mwt 3467 Mwt Number of fuel bundles 748 532 764 Ref. Plant NMP-I NMP-II**
Reactor wate r mass (g) 2.46E8 2.17E8 2.74E8 Suppression pool water mass (g) 3.67E9 2.16E9
- 4.12E9 Total primary coolant (reactor plus suppression pool) mass (g) 3.92E9 2.38E9
- 4.39E9 Reactor Bldg. Volume, ft3 2.14E6 3.88E6 (Secondary Containment)
Drywell gas volume (cc) 7.77E9 5.10E9 8.59E9 Suppression pool gas/containment 3.25E10 3.70E9
- 5.44E9 gas volume (cc)
Total primary containment and drywell gas space volume (cc) 4.03E10 8.80E9
- 1.40E10
- Assumes torus downcomer submergence of 3 ft. (570,000 gallons total). Adjust ifnecessary to account for HPCI or Containment Spray raw water additions.
- Data and calculations used for NMP2 Page 14 EPIP-EPP-09 Rev 03
ATFACHMENT 5: (Cont)
Parameters for Reference Plant and NMP Sheet 2 of 2 NMPNS Unit 11Data From Unit IIFSAR: conversion factor: 2.832E4 cc/ft 3 Suppression Pool gas volume = 192,028 ft3 or 5.44E9 cc Drywell gas volume = 303,418 ft3 or 8.59E9 cc Suppression Pool water = 145,495 ft3 @24 ft, or a mass of 4.12E9 grams Estimation for reactor water mass:
Reference plant is BWR-6 with diameter of 238 inches and a mass of 2.46E8 grams Unit 2 has a diameter of 251 inches. A ratio of diameters was used to estimate NMP2 water mass:
251 2 x 2.46E8g = 2.74E8g 238 Data from Stone &Webster calculation 12/77, PR (c), 21-V, Attachment Con Unit IIsecondary containment volume:
- a. Recirculation volume for accident conditions = 3,876,630 Ft3 or 1.098E1 lcc
- b. Other areas not included in secondary containment volume:
N. Auxiliary Bay El. 240'= 69,200 Ft3 or 1.960E9cc S. Auxiliary Bay El. 240' = 62,300 Ft 3 or 1.764E9cc Page 15 EPIP-EPP-09 Rev 03
ATTACHMENT 6: CORE INVENTORY OF MAJOR FISSION PRODUCTS INA REFERENCE PLANT OPERATED AT 3651 MWT FOR THREE YEARS Isotope Half-Life Inventory
- Major Gamma Ray Energy 101 2pCi (Intensity)
KeV (y/d) 39.4 d 155 497(0.89)
Ru-1 03 Sr-91 9.5 h 115 750(0.23), 1024(0.325)
Sr-92 2.71 h 123 1388(0.9)
Ba-140 12.8 d 173 537(0.254)
La-140 40.2 h 184 487(0.455), 1597(0.955)
- At the time of reactor shutdown.
Page 16 EPIP-EPP-09 Rev 03
ATTACHMENT 7:- REFERENCE PLANT FISSION PRODUCT CONCENTRATIONS INREACTOR WATER AND DRYWELL GAS SPACE DURING REACTOR SHUTDOWN UNDER NORMAL CONDITIONS Reactor Water (pCi/g) Drywell Gas (pCi/cc)
Isotope Upper Limit Normal Upper Limit Nominal 1-131 29 0.7 Cs-137c 0.3a 0.03b Xe-1 33 1E-4a 1E-5b Kr-85 4E-5a 4E-6b a Observed experimentally, in an operating BWR-3 with MK I containment, data obtained from GE unpublished document, DRF 268-DEV-0009.
b Assuming 10% of the upper limit values.
C Release of Cs-1 37 activity would strongly depend on the core inventory which is a function of fuel burnup.
Page 17 EPIP-EPP-09 Rev 03
ATTACHMENT 8: REFERENCE PLANT RATIOS OF ISOTOPES INCORE INVENTORY AND FUEL GAP Isotope Half-Life Activity Ratio* in Activity Ratio* in Core Invbentory Fuel Gap Kr-87 76.3 m 0.233 0.0234 Kr-88 2.84 h 0.33 0.0495 Kr-85m 4.48 h 0.122 0.023 Xe-133 5.25 d 1.0 1.0 1-134 52.6 m 2.3 0.155 1-132 2.3 h 1.46 0.127 1-135 6.61 h 1.97 0.364 1-133 20.8 h 2.09 0.685 1-131 8.04 d 1.0 1.0
- Ratio Noble gas isotope concentration for noble gases Xe-1 33 concentration Iodine isotooe concentration for iodines 1-131 concentration NOTE: Measured concentrations must be corrected for decay from time of reactor shutdown till sample time for comparison to activity ratios.
Page 18 EPIP-EPP-09 Rev 03
ATTACHMENT 9: REFERENCE PLANT BEST-EL .ATE FISSION PRODUCT RELEASE FRACTIONS 2'
Page 19 EPIP-EPP-09 Rev 03
AFIACHMENT 10 105 FUEL MELTDOWN UPPER RELEASE LIMIT BEST ESTIMATE ,2 104 LOWER RELEASE LIMIT~
//
0=L /E
//
//
//
z /" /
-J 103 0 /
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/
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w T 10 UPPER RELEASE LIMIT zT 0 BEST ESTIMATE 0 /
LOWER RELEASE LIMIT
/
1.0 /
NORMAL SHUTDOWN
/
CONCENTRATION
/'
K
/ IN REACTOR WATER UPPER LIMIT 29.0 g,Ci/g NOMINAL 0.7 pCi/g 0 .1 ,1 I 1 1 1 11 1 1 1 1111l I I I I [ I I I 0.1 1.0 10 10)0 I % CLADDING FAILURE 1 1.0 10 100
% FUEL MELTDOWN - ',
Relationship between 1-131 Concentration in the Primary Coolant (Reactor Water + Pool Water) and the extent of Core Damage in Reference Plant.
Page 20 EPIP-EPP-09 Rev 03
ATTACHMENT 11
-104 FUEL MELTDOWN UPPER RELEASE LIMIT BEST ESTIMATE LOWER RELEASE LIMIT,,
103 /" / ,/
S/
o0
,/
, /
I- / ,
z 102 / /
0 / /
0 IL10 zI-z . j/ .
0 z
Lu CLADDING FAILURE o- 1.0 UPPER RELEASE LIMIT z
0 "BESTESTIMATE LOWER RELEASE LIMIT 0
/
/
0.1 NORMAL SHUTDOWN CONCENTRATION IN REACTOR WATER UPPER LIMIT, 0 3 l.Ci/g NOMINAL 0 03 I.Ci/g 10-2r 0.1 1.0 10 100 1 4- % CLADDING FAILURE 1.0 10 100 1*4 o%FUEL MELTDOWN -*
Relationship between Cs-1 37 Concentration in the Primary Coolant (Reactor Water +4 Pool Water) and the extent of Core Damage in Reference Plant.
Page 21 EPIP-EPP-09 Rev 03
ATTACHMENT 12 104 FUEL MELTDOWN UPPER RELEASE LIMIT ,,.
BEST ESTIMATE LOWER RELEASE LIMIT,
,/#
103 I'
0
=L // ,
z '/
5 102 /
0 ,, /
0 /
/
/ /
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/
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/
/
z /
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0 a
z CLADDING FAILURE W 1 .0 0 UPPER RELEASE LIMIT z
0 / BEST ESTIMATE 0 /
Co) LOWER RELEASE LIMIT co T,
0.1 Z/ NORMAL OPERATION CONCENTRATION IN DRYWELL UPPER LIMIT 104 CiCVcc NOMINAL 10i gCi/cc I I * . *.I 10-2 *, u, , ,,,,, ,, , ,, , * *
- I I I I I I I I
! ! V i I I . . 11 .1 1 I 0.1 1.0 10 100
% CLADDING FAILURE 0 1.0 10 100
% FUEL MELTDOWN -*0 Relationship between Xe-133 Concentration in the Containment Gas (Drywell + Torus Gas) and the extent of Core Damage in Reference Plant.
Page 22 EPIP-EPP-09 Rev 03
ATTACHMENT 13 102 FUEL MELTDOWN UPPERESTIMATE*
BEST RELEASE LIMIT " /
LOWER RELEASE LIMIT\ "
10 /-/ ,z ,
0C.
, /.
C-z , ,, ,
< 1.0 ,,/
0 ,,
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_10 z "NQ BEST ESTIMATE 0 NO
/ LOWER RELEASE LIMIT LO
/
10-3 NORMAL OPERATION' CONCENTRATION IN DRYWELL
/
UPPER LIMIT,4 x 10-5 j.CVcc NOMINAL '4 x 10.6 g.CVcc
. I I I I 1 1 I... 1! ILLL 10-4 . . . -.., ,
A m I II I I I I II I I III I I I A I I*1 A
I I 0.1 1.0 10 100
% CLADDING FAILURE 1.0 10 100 1 % FUEL MELTDOWN -1 Relationship between Kr-85 Concentration in the Containment Gas (Drywell + Torus Gas) and the extent of Core Damage in Reference Plant.
Page 23 EPIP-EPP-09 Rev 03
ATTACHMENT 14: TEMPERATURE CONVERSION TABLE DEGREES: FAHRENHEIT / KELVIN OF °K_ OF °K OF °K 50 283 235 385 420 488 55 285 240 388 425 491 60 288 245 391 430 494 65 291 250 394 435 496 70 294 255 396 440 499 75 296 260 399 445 502 80 299 265 402 450 505 85 302 270 405 455 508 90 305 275 408 460 510 95 308 280 410 465 513 100 310 285 413 470 516 105 313 290 416 475 519 110 316 295 419 480 521 115 319 300 421 485 524 120 321 305 424 490 527 125 324 310 427 495 530 130 327 315 430 500 533 135 330 320 433 505 535 140 333 325 435 510 538 145 335 330 438 515 541 150 338 335 441 520 544 155 341 340 444 525 546 160 344 345 446 530 549 165 346 350 449 535 552 170 349 355 452 540 555 175 352 360 455 545 558 180 355 365 458 550 560 185 358 370 460 555 563 190 360 375 463 560 566 195 363 380 466 565 569 200 366 385 469 570 571 205 369 390 471 575 574 210 371 395 474 580 577 215 374 400 477 585 580 220 377 405 480 590 583 225 380 410 483 595 585 230 383 415 485 600 588 Page 24 EPIP-EPP-09 Rev 03
ATTACHMENT 15: CORE DAMAGE ESTIMATE BASED ON 1-131 AND XE-133 CONCENTRATIONS Sheet 1 of 2 NOTE: Follow Attachment 4 Step 2 of procedure text while completing this worksheet.
- 1) List the radionuclide concentrations (C, or Cg) decayed to the time of reactor shutdown as determined from Chemistry analysis. Attach Sample Analysis Data Sheets.
Cw(1-131) = pCilml(from reactor water) uncorrected Cg(xe-133) = pCilcc at 14.7 psig, 2981K (from Containment Gas)
- 2) Correct the measured gaseous activities for T, P differences between the sample vial and containment atmosphere per step 2.4 in Attachment 4 uncorrected Cgl X P2 (298) = Cg, "T2 (14.7)
For Xe-1 33: X (298) = pCi/cc (14.7)
- 3) Calculate the Fission Product Inventory Correction Factor for 1-131 and Xe-133. Use Attachment 16 and 17. If steady state operation for greater than 50 days: Fi (1-131) and F, (Xe-133) = 3651 DCore Thermal Power.
Fi(I-131) =
Fl(xe-133 ) =
- 4) Calculate the Plant Parameter Correction Factors per step 2.7 of Attachment 4. Ifdowncomer submergence equals 3 feet:
NMP1 NMP2 F, (Torus water diluted sample) = 0.607 Fw (Suppression Pool Water Fw (No mixing of Torus water diluted sample) = 1.12 with sample) = 0.055 Fw (no mixing of suppression Fg = 0.22 pool water with sample) =0.070 Fg = 0.35 Page 25 EPIP-EPP-09 Rev 03
ATTACHMENT 15 (Cant)
Sheet 2 of 2
- 5) Calculate the Normalized Concentrations of the isotopes as shown below:
Ref Ref Cw, or Cg, = C. or Cg, x F1, x F, or Fg Ref For 1-131: Cw(I-131) = - X X C, FI(I.131) F, pCilml Ref For Xe-1 33: Cg(xe-133) = X X =
Cgi Fi(Xe133) Fg pCil/cc
- 6) Refer to Attachment 10 and 12 to determine the best estimate of the extent of core damage.
Best Estimates:
1-131: % clad failure (From Attachment 10)
= % fuel melt Xe-1 33: = % clad failure (From Attachment 12)
S% fuel melt Ave: %clad failure
= % fuel melt
- 7) As necessary, confirm and/or refine the core damage estimate by applying the parameters found in Step 3.0 of Attachment 4.
- 8) Submit all data sheets/worksheets for independent review.
Technical Review Performed by:
- 9) Completed worksheet(s) forwarded to the Technical Data Coordinator for disposition.
Worksheet forwarded by:
Page 26 EPIP-EPP-09 Rev 03
ATTACHMENT 16: FISSION PRODUCT INVENTORY CORRECTION FACTOR FOR 1-131 FI(;.l31F Inventory of 1-131 in reference plant Inventory of 1-131 in operating plant F1(I-1 31) = 3651 + Core Thermal Power - (ifsteady state greater than 50 days)
(1) EQUATION FOR: Inventory of 1-131 in operating plant 0
.j[(Pi) (1-0-nj ) (e4'7,))]
WHERE: Inventory of 1-131 in Reference Plant = 3651 A= 1-131 decay constant in days = 0.0862 Pj = Average Power in Mwt for operations period j Tj = Numbers of days operated in period j Tj = Number of days between the shutdown date of period j and last shutdown date (accident date).
(2) Operating Period* Days Decay Ave. Power S/U Date SID Date Operated Days (MP) 0 j (YY,MM,DD) (YY,MM,DD) Tj Tj Pi 1
2 3
4
- Operating Period need only extend back 50 days prior to sample date (Six Halflives of 1-131)
(3) Calculate Fission Product Inventory Correction Fact6r For 1-131:
FI(I-131)= 3651
'j [Pj (I-e(-00862'D) (e(-0862rTD)]
CALCULATION PERFORMED BY:
CALCULATION REVIEWED BY:
DATE: / I MM DD YY TIME: (24 hr.)
Page 27 EPIP-EPP-09 Rev 03
ATTACHMENT 17: FISSION PRODUCT INVENTORY CORRECTION FACTOR FOR XE-133 Fi(xe-133) = Inventory of Xe-133 in reference plant Inventory of Xe-133 inoperating plant Fi(Xe-133) = 3651 + Core Thermal Power- (ifsteady state greater than 50 days.)
(1) EQUATION FOR: Inventory of Xe-133 in operating plant 0
Zi [(Pj)(1-e-TD) (eVOTD))]
WHERE: Inventory of Xe-133 in Reference Plant = 3651 A= Xe-133 decay constant indays = 0.132 (2) Operating Period' Days Decay Ave. Power SIU Date S/D Date Operated Days 0
j (YY,MMDD) (YY,MM,DD) Tj Tj Pj 1
2 3 )
4
- Operating Period need only extend back 50 days prior to sample date (3) Calculate Fission Product Inventory Correction Factor For Xe-1 33:
FI(Xe-133)= 3651 =
0 Xj [PI Ie. 3 O (e(-.l32 Th)]
CALCULATION PERFORMED BY:
CALCULATION REVIEWED BY:_
DATE: / /
MM DD YY TIME: (24 hr.)
Page 28 EPIP-EPP-09 Rev 03
SI' NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-EPP-20 REVISION 15 EMERGENCY NOTIFICATIONS TECHNICAL SPECIFICATION REQUIRED Approved by:
G. L. Detter ces Date 09/30/2002 Effective Date:
PERIODIC REVIEW DUE DATE: OCTOBER, 2002
LIST OF EFFECTIVE PAGES Page No. Change No. Page No. Change No. Page No. Change No.
Coversheet 23 . . . .
24 . ...
2 .....
25 . . . .
26 . . . .
3 . .
27 . . . .
28 . ...
4 . ...
10 . . . .
12 . . .
13 . . . .
14 . ...
15 . . . .
16 . . . .
17 . .
18 . . . .
19 . . .
20 . ..
21 . . .
22 . . . .
Page i EPIP-EPP-20 Rev 15
TABLE OF CONTENTS SECTI ON PAGE 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 RESPONSIBILITIES ............. ........................... 1 3.0 PROCEDURE . ... . . . .. . . . . 1 3.1 Notifications of an Emergency Event From the Control Room (SSS/ED) Including Updates/Reclassifications ............
3.2 Notifications for Transitory Event ........... .... 3 3.3 Notifications of an Emergency Event From the EOF (ED/RM)
Including Updates/Reclassifications ............ 4 3.4 Notifications of an Emergency Event From the Technical Support Center(TSC) Including Updates/Reclassifications ...... 5 3.5 RECS Line Notifications to the Control Room (incoming call) 6 oo. ........... F.............. ....;. . ... .:....... .. . ........... 7 4.0 DEFINITIONS . . . . . . . . . . . . . . . . . . 7
5.0 REFERENCES
AND COMMITMENTS ........... 8 6.0 RECORD REVIEW AND DISPOSITION ......... 9 ATTACHMENT 1A: NINE MILE POINT NUCLEAR STATION S.. . . . 11 NOTIFICATION FACT SHEET - PART 1 .......
NINE MILE POINT NUCLEAR STATION ATTACHMENT IB:
NOTIFICATION FACT SHEET - PART 2 ....... S. . .. . 13 ATTACHMENT 1C: PART III - UNIT I PLANT STATUS BOARD ..... S. . .. . 14 ATTACHMENT ID: PART III - UNIT 2 PLANT STATUS BOARD ..... S. . .. . 15 ATTACHMENT 2: CONTROL ROOM COMMUNICATIONS AIDE FLOWCHART . . . S. . .. . 16 ATTACHMENT 3: COMMUNICATIONS COORDINATOR CHECKLIST (EOF) . . . 17
\TTACHMENT 4fii::EMERGENCY CONTACT FORM ..... .............. S. . .. . 19 ATTACHMENT 5: EMERGENCY RESPONSE DATA SYSTEM (ERDS) ACTIVATION S. . .. . 24 ATTACHMENT 6: NRC EVENT NOTIFICATION WORKSHEET "EXAMPLE" . . . 26 ATTACHMENT 7: LOSS OF COMMUNICATIONS CAPABILITY FROM THE CONTROL ROOM 28 Page i i EPIP-EPP-20 Rev 15
1.0 PURPOSE To provide instructions for prompt initial notification and appropriate follow-up notification of emergency conditions at Nine Mile Point Nuclear Station (NMPNS) to offsite authorities, emergency response agencies, and selected NMPNS personnel.
2.0 RESPONSIBILITIES 2.1 Station Shift Supervisor/Emergency Director (SSS/ED) maintains overall control of emergency notifications until relieved by the Emergency Director/Recovery Manager (ED/RM).
2.2 Emergency Director/Recovery Manager (ED/RM) maintains control of notifications to offsite authorities at the Emergency Operations Facility.
2.3 The Technical Data Coordinator (TDC) ensures continuous communication with the NRC from the Technical Support Center.
3.0 PROCEDURE 3.1 Notifications of an Emergency-Event From the Control Room (SSS/ED)
Including Updates/Reclassifications NOTES: 1. Initial notificatfons to State and County officials shall be commenced within 15 minutes of event declaration.
- 2. If a GENERAL EMERGENCY is declared, Protective Action Recommendations (PARs) shall be transmitted to offsite officials within 15 minutes:
3.1.1 The SSS/ED.shall direct Communications Aides report to the Control Rooms.
3.1.2 The SSS/ED shall direct the Communications Aide to perform actions contained in the Communications Aide Flowchart (Attachment 2).
Page I EPIP-EPP-20 Rev 15
3.1.3 The SSS/ED shall:
- a. Complete Part I Notification Fact Sheet (Attachment 1A) using the instructions on the back of the form.
NOTE: Notification must be started within 15 minutes from event declaration.
- b. Complete the Community Alert Network Form (Attachment 4E).
NOTES: 1. Notifications should be completed as soon as possible after Part 1 Notification Fact Sheets.
- 2. The Dose Assessment Advisor should be consulted to determine if Alternate Emergency Reporting Locations may be appropriate due to offsite doses.
- 1. Provide appropriate information in steps 2 and 4C of Attachment 4E.
- 2. If the site becomes inaccessible for any reason, and response is required, indicate response required to Alternate Emergency Duty Location (Volney Service Center, Howard Rd.).
- 3. Sign the CAN contact form.
- 4. Provide to Communications Aide.
- c. Complete the NRC Event Notification Worksheet (Attachment 6).
NOTES: 1. NRC shall be notified as soon as practical, but in all cases within I hour of event declaration.
- 2. If any Emergency Response Facility is less than 100% operational, then provide ERF status information in the event description block.
- 1. Complete all applicable sections.
- 2. Provide brief description.
- 3. Provide completed form to Communications Aide.
Page 2 EPIP-EPP-20 Rev 15
3.1.4 The SSS/ED should complete the Part I Notification Fact Sheet (Attachment 1A) every 30 minutes for as long as notifications remain in Control Room OR as requested by NY State Emergency Management Office and/or Oswego County Emergency management Office.
3.1.5 The SSS/ED shall ensure followup notifications are made to off-site officials,(NYS and Oswego County) approximately every 30 minutes OR as requested by NY State Emergency Management Office and/or Oswego County Emergency management Office.
3.1.6 The SSS/ED shall ensure the Communications Aide:
- Completes turnover of communications duties to the EOF Communications Coordinator when directed by ED/RM.
Transfers ENS communications-to the TSC when appropriate.
3.1.7 For termination of Unusual Events only, the SSS/ED shall complete the Part I - Notification Fact Sheet (Attachment 1A) through line 5 and:
- a. Sign where appropriate.
- b. Provide to Communications Aide.
- c. Direct Communications Aide to notify-the NRC upon event termination..
3.2 Notifications for TransitorY Event 3.2.1 .Completing a Part 1 Notification Fact Sheet for a Transitory Event:
- a. IF a transitory event has occurred (as defined in EPIP EPP-01 or 02), AND NO emergency classification currently exists, the SSS/ED shall:
- 1) Complete a Part 1 Notification Fact Sheet, Items 1 5, and Item 8, using :appropriate instructions on back of-form.
- 2) Circle the-emergency classification met during the transitory event AND theo"Emergency Terminated" selection on Item 4.
- 3) Ensure RECS linenotifications are completed within one hour in,accordance with Attachment 2, Communications Aide-Flowchart.
Page, 3 EPIP-EPP-20 Rev 15
3.2.1 (Cont)
- b. IF a transitory event has occurred (as defined in EPIP EPP-01 or 02), AND emergency classification currently exists, the SSS/ED shall:
- 1) Complete a Part 1 Notification Fact Sheet (Attachment 1A) using instruction provided on back of form and;
"* On Item 4, circle the emergency classification that currently exists.
" Note the emergency classification met during the transitory event and the time and date of termination in Item 8,"
- 2) Implement emergency notifications in accordance with Step 3.1 of this procedure.
3.2.2 If appropriate, make notifications to the NRC in accordance with 10CFR50.72.
3.2.3 No other notifications are required for transitory events that do not result in a continued emergency classification.
3.3 Notifications of an Emergency Event From the EOF (ED/RM) Including Updates/Reclassifications NOTES: 1. If emergency event is reclassified, State and County official notification shall be commenced within 15 minutes of each reclassification.
- 2. If a GENERAL EMERGENCY is declared, Protective Action Recommendations (PARs) shall be transmitted to offsite officials within 15 minutes.
3.3.1 The ED/RM shall direct transfer of communications responsibilities from the Control Room to the EOF when the EOF Communications Coordinator is prepared to accept duties.
3.3.2 The ED/RM shall verify updates are made to offsite officials (NYS and Oswego County) approximately every 30 minutes.
NOTE: Initial notification should already have been completed from the control room.
3.3.3 The ED/RM shall ensure the EOF Communications Coordinator performs notifications specified on Communications Coordinator Checklist (Attachment 3).
Page 4 EPIP-EPP-20 Rev 15
3.3.4 The ED/RM shall ensure the following documents are provided to the EOF Communications Coordinator:
- a. Updated Part I - Notification Fact Sheet (Attachment 1A) from the EOF Administrator for every emergency classification upgrade and/or approximately every 30 minutes.
- b. When appropriate, completed Part II - Dose Assessment Fact Sheet (Attachment 1B) from the ODAM.
- c. Part III - Plant Status Board (Attachment 1C Unit 1 or Attachment ID Unit 2) from Tech Assessment.
3.3.5 When the event is terminated, the ED/RM shall:
- a. Obtain a Part 1 Notification Fact Sheet from the EOF Administrator, completed through Line 5
- b. Sign where appropriate.
- c. Provide to the EOF Communications Coordinator.
3.3.6 The ED/RM shall specify any specific or additional instructions for site faci ities'such as the Nuclear Learning Center (NLC), 'Energy Information Center SEIC), P Building, etc. to appropriate personnel (i.e.
ýecurity Unaffected Control Room, Communications Coordinalor, etc.).
3.4 Notifications of an Emerqency Event From the Technical Support SCenter(TSC) Including Updates/Reclassifications 3.4.1 The Technical Data Coordinator (TDC) shall assign a person from the Technical Assessment Group to act as Emergency Notification System (ENS) Communicator.
3.4.2 The TDC shall direct the ENS Communicator to:
- a. Activate the Unit 2-Emergency Response Data System (ERDS) per.Attachment 5.
NOTE: For Unit 1, ERDS is activated by the Control Room
- b. Call the Communications Aide in the Control Room and transfer ENS communications from the Control Room to the TSC.
- c. Monitor ERDS every 60 minutes (If link is lost, restart per Attachment 5)
- d. Continuously staff the ENS telephone. ,If a backup phone is required because the ENS line (Red Phone) is inoperable, the NRC shall be notified (via commercial telephone) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> that the ENS line is inoperable.
Page 5 EPIP-EPP-20 Rev 15
3.4.3 For each emergency reclassification' The TDC shall complete the NRC Event Notification Worksheet (Attachment 6)
NOTE: NRC shall be notified as soon as practical, but in all cases, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of event declaration.
3.4.4 The TDC shall direct the ENS Communicator to:
- a. Read NRC Event Notification Worksheet (Attachment 6) information to NRC Headquarters.
- b. Fax NRC Event Notification Worksheet (Attachment 6) to NRC Headquarters per Attachment 4, F.
3.4.5 The TDC shall ensure the Radiological Assessment Manager continuously staffs the Health Physics Network (HPN) telephone, as required.
3.5 RECS Line Notifications to the Control Room (incoming call) 3.5.1 Upon receipt of a notification on the RECS line (incoming call), the CSO (or designee) should:
- a. Complete a Part I Notification Fact Sheet (Attachment 1A) using the information provided.
- b. Inform the SSS/ED of the notification and provide the completed Part 1 Notification Fact Sheet (Attachment 1A).
3.5.2 The SSS/ED should:
- a. Review the information contained in the completed Part 1 Notification Fact Sheet (Attachment 1A).
- b. Evaluate any events or conditions against EPIP-EPP-01/02 and, if necessary, declare the emergency.
- c. If JAFNPP declares a General Emergency or initiates a site evacuation, implement EPIP-EPP-05C, "Exclusion Area Evacuation. (Unit I SSS/ED takes the lead.)
- d. If necessary, implement appropriate Emergency Plan Implementing Procedures.
Page 6 EPIP-EPP-20 Rev 15
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4.0 DEFINITIONS 4.1 Community Alert Network (CAN) An automated computer callout system used to assist with notification of NMPNS emergency response personnel.
4.2 NRC Emer.fency Telecommunication Syst bem (EM, -- A dedicated'tlephone toacommunicate psystem important plant information to the NRC during an emergency. This includes the'Emergency Notifica'tion System (ENS) known as the "red phone", the Health Physics Network (HPN), and other lines for NRC use.
4.3 Normal Hours - Normal work hours between 0700 and 1530 Monday through Friday excluding holdidays.
4.4 Off-Hours - All hours not considered normal hours.
4.5 COsweio County Warning Point -,(Oswego County 911 Center). The 911 Center in Oswego, New
"'communications-center uYork serves as a notification point County at theý Oswego for messages from the utilities to appropriaten'officiTlsmini the county. The center caA communicate directly to the State Warning Point and also has a radio to communicate directly with the Nine Mile Point and James A. Fitzpatrick NuclFear Stations.
Page 7 EPIP-EPP-20 Rev 15
4.6 Radiological Emergency Communication System (RECS) - A dedicated telephone system used to provide initial notification of an emergency, and continuing emergency information to New York State, Oswego County, JAFNPP, and the unaffected unit Control Room.
4.7 State Warning Point (SWP) - New York State's center for receipt and dissemination of warnings of an attack upon the United States as well as actual or impending natural or man-made disasters. The SWP is located in Albany, New York.
5.0 REFERENCES
AND COMMITMENTS 5.1 Technical Speci fi cations None 5.2 Licensee Documentation Nine Mile Point Site Emergency Plan 5.3 Standards. Requlations. and Codes 5.3.1 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 5.3.2 IOCFR50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors 5.3.3 10CFRSO, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities 5.4 Policies, Programs, and Procedures 5.4.1 EPIP-EPP-01, Classification of Emergency Conditions at Unit 1 5.4.2 EPIP-EPP-02, Classification of Emergency Conditions at Unit 2 5.4.3 EPIP-EPP-05B, Protected Area Evacuation 5.4.4 EPIP-EPP-05C, Exclusion Area Evacuation 5.4.4 EPIP-EPP-18, Activation and Direction of Emergency Plans 5.4.5 EPIP-EPP-23, Emergency Personnel Action Procedures Page 8 EPIP-EPP-20 Rev 15
5.5 Commitments Sequence NCTS Number Number Description 1 DER NM-2001-4708 To allow determination of % tech specs by any means available.
2 DER NM-2001-4714 To specify Part III is to be sent.
3 504473 NRC Order dated 2-25-2002 6.0 RECORD REVIEW AND DISPOSITION 6.1 The following records generated by this procedure shall be maintained by Records Management for the Permanent Plant File in accordance with NIP-RMG-01, Records Management:
NOTE: This only applies if records are generated as the result of an actual declared emergency at the Nine Mile Point Nuclear Station.
Attachment 1A NINE MILE POINT NUCLEAR STATION NOTIFICATION FACT SHEET
- PART I Attachment 1B NINE MILE POINT NUCLEAR STATION NOTIFICATION FACT SHEET
- PART 2 Attachment IC PART III - UNIT 1 PLANT STATUS BOARD Attachment ID PART III - UNIT 2 PLANT STATUS BOARD Attachment 2 CONTROL ROOM COMMUNICATIONS AIDE FLOWCHART Attachment 3 COMMUNICATIONS COORDINATOR CHECKLIST (EOF)
Attachment 4 EMERGENCY CONTACT FORM Attachment 5 EMERGENCY RESPONSE DATA SYSTEM (ERDS) ACTIVATION Attachment 6 NRC EVENT NOTIFICATION WORKSHEET 6.2 The following records generated by this procedure are not required for retention in the Permanent Plant File:
NOTE: This only applies when records are not the result of an actual declared emergency. (Such as for training or drills)
Attachment IB NINE MILE POINT NUCLEAR STATION NOTIFICATION FACT SHEET
- PART 2 Attachment IC PART III - UNIT I PLANT STATUS BOARD Attachment ID PART III - UNIT 2 PLANT STATUS BOARD Attachment 2 CONTROL ROOM COMMUNICATIONS AIDE FLOWCHART Attachment 3 COMMUNICATIONS COORDINATOR CHECKLIST (EOF)
Attachment 4 EMERGENCY CONTACT FORM Attachment 5 EMERGENCY RESPONSE DATA SYSTEM (ERDS) ACTIVATION LAST PAGE Page 9 EPIP-EPP-20 Rev 15
THIS PAGE INTENTIONALLY LEFT BLANK Page 10 EPIP-EPP-20 Rev 15
ATTACHMENT 1A: NINE MILE POINT NUCLEAR STATION NOTIFICATION FACT SHEET - PART 1 (Do not-say items in italics) Sheet 1 of 5 Pick up phone, press A*, wait about 10 seconds, then say, "THIS IS / IS NOT (as appropriate)A DRILL. THIS IS TO REPORT AN INCIDENT AT NINE MILE POINT NUCLEAR STATION, STAND BY FOR ROLL CALL."
Conduct roll call to include the following:
Notification No. I New York State i 0Warning Oswego Couno I JA Fizatrzck 0IUnfected I Warning Point Point Power Plant 9MP Unit PART 1 - GENERAL INFORMATION (Read step number, and information, example: -number 1, This message...)
- 1. This message is being transmitted on: VIA: A. RECS (Date) at (Time)_I B. Other
- 2. This is: 3. The facility providing this information is:
A. NOT an Exercise B. An Exercise D. Nine Mile Point Unit 1 E. Nine Mile Point Unit 2 F. J.A. Fitzpatrick
- 4. The Emergency Classification is: A. Unusual Event C. Site Area Emergency E. Emergency F. Recovery B. Alert D. General Emergency Terminated G. Transportation Incident
- 5. This Emergency Classification declared on:
(Date)_ at (Time)
- 6. Release of Radioactive Materials A. No Release due to the classified event. B. Release below federa-lly approved operating limits (Technical Specifications) 0 To Atmosphere 0 To Water C. Release above federally approved operating limits (Technical Specifications)
"1To Atmosphere 0 To Water D. Unmonitored release requiring evaluation
- 7. Protective Action Recommendations:
A. No need for Protective Actions outside the site boundary.
B. EVACUATE the following ERPAs:
1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 AND C. SHELTER all remaining ERPAs
- 8. EAL #: Additional Information
- 9. The Plant status is: A. Stable B. Improving C. Degrading
- 10. Reactor Shutdown: A. Not Applicable B. (Date) at: (Time)
- 11. Wind Speed: 12. Wind Direction:
Miles/hr at elevation feet - (From) - Degrees at elevation __ feet
- 13. Stability Class: , 14. Reported By:
A B C D , E F G -_ (Comrunicalor Name) at Tel. No. (315)
Ask: "DOES OSWEGO COUNTY OR NEW YORK STATE NEED CLARIFICATION ON ANY INFORMATION?
(Provide as appropriate)
THIS IS THE END OF THE MESSAGE. STANDBY FOR VERIFICATION ROLL CALL."
E Check those involved in termination roll call.
I D New York State Warning Point l0Oswego County I Warning Point Then say, "NINE MILE POINT UNIT 1 OR 2 (as appropriate)OUT" AT TIME (24 hr dock):
Li JA Fitzpatrick Power Plant i Unattectec 9MP Unit I Approved By (SSS/ED or EDIRM)
Page 11 EPIP-EPP-20 Rev 15
ATTACHMENT lA INSTRUCTIONS COMPLETING THE NOTIFICATION FACT SHEET - PART 1 Sheet 2 of 5 NOTE: Complete all applicable sections.
BLOCK # INSTRUCTIONS
- 1. Communications Aide completes this block using date and time that number was dialed (A then ).
- 2. Indicate not an exercise(real event) or exercise(drill) by circling as appropriate.
- 3. Indicate facility providing information by circling as appropriate.
- 4. Indicate by circling as appropriate the:
- Classification Level, or
- If event is terminated, or
- If recovery is entered, or
- If this is for a transportation accident
- 5. Indicate the date and time the event was classified.
- 6. Indicate the status of any releases of radioactive materials by circling as appropriate, request Chemistry Technician provide release information then indicate:
NOTE: (This section applies to release of radioactive materials that took place DUE to the classified event. IF a radioactive material release is taking place and it is unknown if it is related to the event, THEN assume the release is the result of the event)
- a. No Release: Circle this selection if there is no release related to the declared event.
(Cl) b. Release below federally approved operating limits (Technical Specifications): Circle this selection if a release is in progress due to the event AND the release rate has been determined (by any means available) to NOT exceed Technical Specifications.
(Cl) c. Release above federally approved operating limits (Technical Specifications): 'Circle this selection if a release is in progress due to the event AND the release rate has been determined (by any means available) to exceed Technical Specifications.
- d. Unmonitored release requiring evaluation: Circle this selection if evidence exists of a release from a pathway from which a release cannot be readily determined (examples: Emergency Condenser vents, blowout panels)
- 7. Indicate Protective Action Recommendations by circling as appropriate:
- No need for protective actions
- Evacuate the following ERPAs (indicate appropriate ERPAs as recommended by Dose assessment Advisor/ODAM)
- 8. Write the EAL # that the event was classified as in the box provided for Item #8. Under Additional Information exampleE information that should be provided include:
- Do not repeat the EAL description here.
- Other conditions if present that could have an effect on future classifications.
- Other EALs that are applicable to present conditions, ie... if in more than one EAL has been met, indicate additional EAL numbers here.
- If the EAL requires no additional explanation, the Additional Information section may be left blank.
- 9. Indicate the following by circling as appropriate:
- Stable: No escalation in emergency classification expected. Plant conditions are not degrading.
- Improving Plant conditions are such that mitigative actions have been successful and termination is likely.
0 Degrading: Plant conditions are such that mitigative actions have been unsuccessful, escalation of emergency classification is likely. If already at a General Emergency, release may be anticipated or is ongoing.
- 10. Indicate not applicable by circling as appropriate or indicate the time the reactor is shutdown (per EOP Definition).
NOTES: 1. Meteorological Data to be recorded on the Part I Notification Fact Sheet is the 15 minute average data in accordance with EPIP-EPP-08.
- 2. Meteorological Data need not be completed for initial notification if the data is not readily available.
- 11. Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record.
12 Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record.
- 13. Obtain 15 minute average meteorological data from the Dose Assessment Advisor and record
- 14. Communications Aide completes this block listing name and the commercial telephone they use.
THEN: Sign the Part 1 Notification Fact Sheet.
AND: Provide to Communications Aide.
For termination of Unusual Events only,
- 1. Complete Part I - Notification Fact Sheet (Attachment 1A) through Line 5 and:
- a. Sign where appropriate
- b. Provide to the Communications Aide Page 12 EPIP-EPP-20 Rev 15
ATTACHMENT 1B: NINE MILE POINT NUCLEAR STATION NOTIFICATION FACT SHEET - PART 2 Sheet 3 of 5 RADIOLOGICAL ASSESSMENT DATA THIS IS / IS NOT A DRILL (circle appropriate)
- 15. Message transmitted at:
Date Time Location/Facility Transmitted From:
- 16. General Releasd Information A. Release > Tech Specs started: Date Time B. Release > Tech Specs expected to end: Date Time _ OR 0 Unknown 0 Intermittent C. Release > Tech Specs ended: Date _ _ Time _ _
D. Reactor Shutdown: N/A OR Date Time E. Wind Speed: __ miles/hour OR __ meters/second at elevation feet or meters (Circle one)
F. Wind Direction from: _ degrees at elevation _ feet or meters (Circle one)
G. Stability Class: PASQUIL A B C D E F G OR Other _ _
17.Atmospheric Release Information, A. Release from: 0 Ground 0c Elevated D. Noble Gas Release Rate- Ci/sec B. Iodine/Noble Gas Ratio E. Iodine Release Rate __ Ci/sec C. Total Release' Rate Ci/sec F. Particulate Release Rate Ci/sec 18.Waterborne Release Information A. Volume of Release gal or liters C. Radionuclides in Release B. Total Concentration _pCi/ml D. Total Activity Released
- 19. Dose Calculations (based on a release duration of __ hours)
Calculation is based on (circle one) A. Inplant Measu rements B. Field Measurements C. Assumied Source Term Table below applies to (circle one) A. Atmospheric Release . B. Waterborne Release Dose Distance TEDE (rem) CDE - Child Thyroid (rem)
Site Boundary 2 Miles 5 Miles 10 Miles
__ Miles 20.Field Measurements of Dose Rates 'or Surface Contamination/Deposition Dose Rate OR Mile/Sector OR Location OR Sampling Point Time of Reading Contamination MilelDegrees (Include Units)
Approved By: (SSSIED or ED/RM)_______________________________
Page 13 EPIP-EPP-20 Rev 15
I-ATTACHMENT IC PART III - UNIT 1 PLANT STATUS BOARD Sheet 4 of 5--
THIS IS / IS NOT A DRILL Date (MM/DD/YY) Time (24 Hour)
Parameter Description Current Value Units Pint
_ _ID Main Steam Line Radiation Monitor 111 mR/Hr. E469 Main Steam Line Radiation Monitor 121 mR/Hr. E470 Main Steam Line Radiation Monitor 112 mR/Hr. - E471 Main Steam Line Radiation Monitor 122 mR/Hr. E472 Reactor Feedwater Total Flow K#/Hr. G315 SPDS-APRM H441 SPDS-IRM H442 SPDS-SRM CPS H443 SPDS Wide Water Level Feet H446 SPDS Acurex FZWLM Level Inches H447 SPDS RPV Pressure __ PSIG H448 SPDS Drywell Pressure PSIG H449 SPDS Containment Oxygen Concentration _ H452 SPDS Drywell Temperature Degrees F H453 SPDS Torus Water Temperature Degrees F H454 SPDS Torus Water Level Feet H455 SPDS Offgas Dose Rate mR/Hr. H457 SPDS Main Stack-. _Ci/Sec. H458 SPDS Containment High Radiation-Monitor R/Hr. H460 HPCI (No=FW not in HPCI mode; YES=FW in HPCI mode W087 Page 14 EPIP-EPP-20 Rev 15
ATTACHMENT ID PART III- UNIT 2 PLANT STATUS BOARD Sheet 5 of 5 jTHIS IS /IS NOT A DRILL ~Date (MM/DD/YY) Time (24 Hour)
Parameter Description Current Units Pint ID Value Condensate Storage Tank 1A - Level KGAL CNSLAIO0 Condensate Storage Tank 1B - Level KGAL CNSLAIOI Reactor Feedwater Flow - Line A KLBH FWSFU100 Reactor Feedwater Flow - Line B KLBH FWSFUIOI Reactor Core Isolation Cooling System Flow GPM ICSFAIOO APRM - Reactor Power _ _% SPDSA1Ol Drywell Temperature Degrees F SPDSA103 SRM Output CPS SPDSA105 Reactor Water Level Inches SPDSAI07 Reactor Pressure .. PSIG SPDSAI09 Drywell Pressure PSIG SPDSA111 Containment. Oxygen Concentration _ _ % SPDSA1I3 Containment Hydrogen Concentration % SPDSA114 Suppression Pool Temperature Degrees F SPDSA115 Suppression Pool Water Level Feet SPDSA117 Main Stack Activity -lCi/S SPDSA124 Reactor-Building Vent Activity ACi/S SPDSA125 Off Gas Activity pCi/cc SPDSA126 Drywell High Radiation R/Hr SPDSA127 LPCI - A Flow GPM SPDSA136 LPCI_- B Flow GPM SPDSA137 LPCI - C Flow GPM SPDSA138 LPCS Flow GPM SPDSA139 HPCS Flow _ _ GPM SPDSA140 Main Steam Radiation Monitor mR/Hr SPDSA141 Generator Power MWE, SPGQA02 Drywell Loop A Pressure Elevation 293 Ft. PSIG CMSPA01 Drywell Loop A Pressure Elevation 261' Ft. PSIG CMSPA02 Drywell Area Temperature Elevation 307 Ft. Degrees F CMSTAO1 Drywell Area Temperature Elevation'310 Ft. Degrees F CMSTA1O Page 15 EPIP-EPP-20 Rev 15
ATTACHMENT 2: CONTROL ROOM COMMUNICATIONS AIDE FLOWCHART HOW TO USE THE RECS LINt I Ensure the Notification Fact Sheet - Part 1is completed and the Emergency Director signature line is signed
- 2. Obtain Emergency Contact Forms Packet (Attachment 4).
3 Provide the Pan I data to agencies via the RECS tine.
a Liftthe handset of RECS telephone (with yellow lace plate) and press then *
(example lie you dial a regular telephone, if you make a mistake, hang-up and redial correctly) b Wait about tO seconds for all tesponders to answer ( if no answer. or are informed no light and/or nng was received, hang-up momentarily and te-dral) c Push button in the handset to talk.
d State the following "THIS IS I IS NOT (as approprate) A DRILL ,THIS IS TO REPORT AN INCIDENT AT THE NINE MILE POINT NUCLEAR STATION.
STANDBY FOR ROLL CALL,.'.
NOTE When each organization answers, they should identiy themselves and wad ftO the Rolo Can to begin (they often do not so don t wait) e Pause to permt individuals to obtain thee copies of forms on which they will record the intormation you will read to them 4 Conduct a rot call by stating 'Roll CaIl New YorkStale Warning Point' (wad to obtain an answer) then continue to inctude Oswego County Warning Point (pause) and James A Fitzpai*ick Nuclear Power Ptant (pause), and unalfected Nine Mile Point Plant a eaatnria hs poinO ra MM uiaanu Sedatio~n enFact S to ewndd so..
- AiA.
ian*raira als Pat a F~r~ra toctiera *d S For parties that do not respond to call stale the following 'recalling (Party) ___ . If the party sill does not respond, then call NHRCE.nI s Ca IF eNRCst"Ag P-i,,M-ANRC p Ofla.g i at at NRC MA r them using the backup method specilied. after completion of RECS *, C~wg~u a 3ý
- Nd~oeL" " Sgl 9I176 5935'Nosamis
,V - Paecnu call. It a backup method is not specified, continue nollfcations and main, and Srat saiet -inn
" rh.-. ad .Cak
- 3. JNC RApe4Coal -3 (59238501 3 uoasassvogonNR mkast .
enlorm SSS/ED, ED/AM as soon as possible a oaýC.VocoiA00 Rec" 9t22 tsar91i76 s .SEri*0-PA d Co.aa 24 01hi45mm7 Oomoriait 6 Upon completion of rol call, read the Notiticaton Fact Sheet - Part I 1.
' i Do so by reading each tine iem number, and the assocrated 4, Inlornation Whlei,,'.
aatonqg the iaiiovaa* sas.
7 Upon completion of message state 'This is the end of the message WHEN iHEN Standby Foe Verdicathon Roll Call' "Nodied Wag1t rFO aC* cAned niI P.4 I I.-doarC
. ro-w oa CaO-orIw1adaataalc. siabi$ lMa1.593-S8751
-aI-adc 8 Conduct rot call (step 4) iS ,MA-ta noiaai .*qa.t tkiAtS30 n-0i beda.'VV.i- a0eoeaa 2 Ti.".i` n ,.svaat~hs Wri a EOF 3 kWn. SSSTO adriaaaia 9 Then ask i N Y State and Oswego County have received the message, provide corrected message intormation if necessary NoJdded .ha0, TSCe sia;hd P.da.m. t lo'ac- :
I faniwa NiC (ENS) ,aapaabt4tietort.. TSC tIaPao0 Aorana.a 2 5.aaacaaa... bAAr'"-.C-.. P-a' AýdIC a. -a-say 10 After all information is provided state "Nine Mile Point (Unit 1. Unit 1 "t,-0a,.iS. 5-0ED adan1- a ENS rtsrsadai iTSC 2 or EOF) out at lime__ "
."EQF Nf ba Coamie aFasiyaaH-nodiatHaaa ida.H.. 4 0G- I "' a) aAM
,ta pstaeo a,,ga.I ht 51 Record the time that the notification is completed FAXING DOCUMENTS II Bagsha anni ar~aim~ maarpa...
aleit NOTE If performing this portion of the procedure during a DRILL or EXERCISE.
ensure the word 'DRILL' is written across the form a'
1 Insert document in FAX machine face down.
2 Flip over plastic cover to expose Rapd Corn numbers 33-48 (C3) 3 Press button number 48 4 This ,s equrvalent to draling the rapid corn numbers below Loso(communicatiins.Gapabififut3frme -ontrol RoaIm OS EOF (593-5951) 01 TSC (349-2151) IF 13 JNC (592-3850) .* ,oIcomnT7aht1'Mems i have been disruolbe, 22 Oswego County (591-9176) tH.EN 24 NYS EMO (518 457 9930)
- - Obtan th eýe6o6satoe quipment Kit S When the FAX machine provides pnntout a , Verity FAX was sent to all agencies listed in step 4 above 6-erform.refquireaoflO UfSons nngtnesstcfonsrn.hirarni-b t not sent to allt e-send FAX to those missed Page 16 EPIP-EPP-20 Rev 15
ATTACHMENT 3: COMMUNICATIONS COORDINATOR CHECKLIST (EOF)
I NAME: I DATE: IE UNIT I El UNIT 2 NOTE: A Log should be maintained detailing times notifications made, problems encountered, etc.-- Check Complete N/A
- 1. 'Sign inon the Staffing Board............................................ 0 El El
- 2. Obtain the Emergency, Contact Forms (Attachment 4) ............................. E
- 3. Verify EOF Plant Information Coordinator position is filled El and ready to assume responsibilities ........................................ E
- 4. Verify Off-site Dose Assessment Manager (ODAM) position is filled El and ready to assume responsibilities ........................................ 0 El
- 5. Verify communications equipment/telephone lines operational ....................... E
- 6. Inform EOF Administrator or ED/RM you are staffed and ready to assume communications El duties .... .. ........... ...... ... ...... .... .... . ... ... .. . . ... .. . E
- 7. Contact Control Room Communications Aide: U-I: 349-2841, 2842, 2843 U-2: 349-2173
- a. Determine which required initial and follow-up notifications have been made .......... .E El El
- b. Request a copy of latest Part I Notification from the Control Room ................. E
- c. Advise Control Room Communications Aide you are assuming emergency notification El duties .............................................. ........... E El
- d. Document status of initial and follow-up notifications (complete as required) ......... .'DE El
- 8. Inform ED/RM when communications turn over is complete ..........................
- 9. Process Notification Fact Sheets (NFS) as follows:
- a. Obtain approved NFS as follows:
"* Part 1 NFS: Emergency Director or EOF Administrator .................. El El El El
"* Part 2 NFS: Emergency Director or ODAM ......................... El
"* Part 3 NFS: Fax in Tech Assessment Room ......................... El
- b. Transmit Part 1 NFS using the RECS line. (See CommAide flow chart for RECS instructions) ................................................... El El
- c. IF El El
- All communications systems have been disrupted ........................
THEN
- Obtain the emergency communications equipment located in the NMP Plant Assessment Room ............................................. El El
- Perform required notifications using the instructions contained on Attachm ent 7 ...............................................
FAX NFS as follows:
"* Part 1 NFS: Speed dial #10 (Oswego County EOC, New York State EOC, Joint News Center, TSC, JAFNPP Control Room) ................. El
"* Part 2 NFS: Speed dial #10 (Oswego County EOC, New York State EOC, Joint El News Center, TSC, JAFNPP Control Room) ................. El El
- e. Provide copies of all transmitted NFS to Plant Information Coordinator for posting in the El El EOF.......................................................... El El
- f. Maintain a legible copy of each NFS in a master file .........................
Page 17 EPIP-EPP-20 Rev 15
ATTACHMENT 3 (Cont)
Check Complete N/A (C2) 10. When requested by other EOF staff to distribute data to the State and/or county (e.g. Part III):
"* Fax to speed dial #20 (Oswego County EOC, New York State EOC, Joint News Center, TSC)....................................................... El El
"* Maintain a legible copy of each fax in a master file .......................... El El
- 11. Perform initial and follow-up notifications as required based on emergency classifications and previous notifications status using Attachment 4 (except NRC) .................. El El
- 12. Upon completion of initial and/or follow-up notifications, continue to make follow-up notifications at approximately 30 minute intervals as specified in Att 4 A, B, C, D ........
- 13. Keep the ED/RM and EOF Administrator apprised of notification status, problems, and questions . ....................................................... El El
- 14. If the emergency is reclassified, recommence notification activities steps 10 through 14 ..... D El
- 15. When the emergency is terminated: communicate the Part I Notification Fact Sheet for termination to notify all other parties (Attachment 4) that the event is terminated by:
- a. Obtaining Part I from EOF Administrator ................................ El El
- b. Performing cursory review for completeness to Line 5 and ED/RM signature .......... El El
- c. Performing notifications per Attachment 4 ................................ El []
Page 18 EPIP-EPP-20 Rev 15
ATTACHMENT 4: EMERGENCY CONTACT FORM Sheet I of 5 NOTE: For items A-D, use the RECS Line Instru'ctions of Attachtment 2.
A. New York State: Department of Health/State Warning Point/EOC
- 1. Notify at all emergency classifications and reclassifications
- REQUIR*EMENT 2. Notification shall be made within 15 minutes of 'event classification/reclassification
- 3. Provide follow-up information as required by checklist PRIMARY CONTACT RECS Hot Line - Yellow Face Plate METHOD BACKUP CONTACT 1. (518) 457-2200 (Warning Point)(24-hour)
METHOD 2. (518) 457-9930for Fax (Call (518) 457-2200before using this fax'number.)
MESSAGE Read Part I Notification Fact Sheet.
COMMENTS B. Oswego County 911 Center/EOC
- 1. Notify at all emergency classifications ard reclassifications REQUIREMENT 2. Notification shall be made within 15 minutes of event classification/reclassification
- 3. Provide follow-up information'as required by checklist PRIMARY CONTACT RECS Hot Line - Yellow Face Plate METHOD
- 1. '911 (Warning Point) 4. Radio (Osw. Fire) (KED-569)
BACKUP CONTACT 2. 343-1313 (Warning Point) 5.349-8500 METHOD"
- 3. 591-9189 (EOC)
MESSAGE Read Part I Notification Fact Sheet.
C. JAFNPP Control Room reclassifications REQUIREMENT 1. Notify at all emergency classifications and
- 2. Provide follow-up information as required by checklist PRIMARY CONTACT RECS Hot Line - Yellow Face Plate METHOD
- 1. Dedicated CR Line (CSO Desk) 4. 342-3840 (Switchboard)
BACKUP CONTACT 2. 349-6665 5. 349-6323 Fax
- METHOD 3. 349-6666 MESSAGE Read Part I Notification Fact Sheet.
D. Unaffected Nine Mile Control Room: 0 Unit 11/0 Unit 2 SSS
.,.'......IREM-ENT1. Notify at aLl emergency classifications and byreclassifications
- REQUIREMENT 2. Provide follow-up information as required checklist PRIMARY CONTACT RECS Hot Line - Yellow Face Plate
.,-METHOD Unit 1 SSS Unit 2 SSS BA'CKUP CONTACT 1. 349-2480 1. 349-2170 4. 349-2168 (CSO)
METHOD . 2. 342-3462 2. 342-1929
- 3. 349-2478 (CSO) 3. 342-3059 MESSAGE Read Part I Notification Fact Sheet.
Page 19 EPIP-EPP-20 Rev 15
RQ9 HI NT 4 (Cat Sheet 2 of 5 E. Community Alert Network (CAN)
REQUIREMENTS FOR CAN NOTIFICATION Notification to CAN and Pager Activation System should occur only when:
- 1. Directed by SSS/ED/ or ED/RM for event notification
- 2. It is the first notification required for any Emergency Classification, OR
- 3. The Emergency Classification is upgraded from an Unusual Event Classification.
- 4. Per EOF Communications Coordinator Checklist.
STEP 1 CONTACT THE CAN SYSTEM A. Call CAN System using one of the numbers listed below: (Remember to dial 9-1, then the number below)
- 1. (800)552-4226 2. (877)786-8478 3. (800)992-2331 B. Provide Message: "THIS IS TO REPORT AN INCIDENTAT NINE MILE POINT NUCLEAR STATION' C. Note time, date and person contacted:
Time: Date: Person Contacted:
D. When requested provide password (ONTARIO).
STEP 2 PROVIDE MESSAGE AS COMPLETED BY SSS/ED This should be read as (example: A, This # 1," is a drill") Copy #
A. This: 1. 0- is a drill checked
- 2. 0l is an actual emergency here:
A (used for step 4)
B. Involving: 1. 0 Nine Mile Point Unit 1 Copy #
- 2. O Nine Mile Point Unit 2 checked
- 3. o Both Units here:
B (used for step 4)
C. Responders: 1. 0l No response is required Copy #
report to 2. 0l Response required to all ERFs checked
- 3. El Response required to Alternate here:
Emergency Duty Location C (used for step 4)
- 6. C] Staff TSC/OSC only
- 8. 0l Precautionary staff ERFs STEP 3 VERIFY CORRECT CODE A. Ask the CAN System Operator to repeat the numerical code (as listed above):
B. When asked, provide the number you called CAN from as listed below and, check the box.
EOF: El (315) 593-5875 Unit 1: [] (315) 349-2841 El (315) 349-2842 Unit 2: E (315) 349-2172 El (315) 349-2173 Other: El (write in number)
C. Hangup the phone.
STEP 4 MANUALLY ACTIVATE THE PAGER SYSTEM Caution: Performing the following steps will result in the notification of the ERO.
A. Call Pager Activation System at 1-877-472-7874.
B. When asked to enter the pager number, enter 0017.
C. When asked to enter your numeric message, and using the three number code indicated in step 2 above, enter: (Be sure to include the Os) 0 00 ( ) ( ) ( ) THEN PRESS #
A1B C D. Hangup the phone E. Inform the SSS/ED that CAN has been notified.
Message Approval: (SSS/ED)(ED/RM) ____________________Time________
Page 20 EPIP-EPP-20 Rev 15
ATTACHMENT 4 (Cont)
Sheet 3 of 5 F. Nuclear Regulatory Commission: Emergency Operations Center
"*Normally performed from the Control Room or T.S.C.
i~i * :i~iiii*!i!!ili~i-"
- . .* No'tify at all emergency classifications and reclassifications; provide follow-up information.
REQUIREMENT NOTE: If a backup phone is required to be used because ENS line (Red Phone) is inoperable, the' "NRC shall be notified (via commercial telephone) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> that the ENS line is inoperable.
ENS Line (Red Phone) using telephone numbers listed:
CONTACT 1. (301)816-5100 (Main) .3. (301)415-0550(Second Backup)
METHOD 2. (301)951-0550(Backup)
Start Time Date ]
- 4. (301)816-5151 (Fax)
Person Contacted MESG MESSAGE Read Event Notification Worksheet (Attachment
.. 6). State that this notification is being performed under 10CFR50.72.
G. Energy Center
- ......Notifyat Alert, Site Area Emergency or General Emergency; provide follow-up information as REQUIREMENT
- " =::.requested. rqetd
- 1. 349-2637 CONTACT 2. 342-4117 METHOD Start Time Date Person Contacted
- .- :. -."This (is/is not) a drill. This is Nine Mile Point Nuclear Station Unit (1/2). A (state emergency class) has been declared. Notify tihe'Energy Center Director or designee, and make a PA announcement for Emergency Response personnel to report to their
.. .. emergency facilities." .
MESSAGE At an Alert or SAE add: "Inform the Energy Center Director (or designee) to direct all visitors
- at the Energy Center and surrounding park area to leave the site property".
At a GEadd: "Inform the Energy Center Director (or designee) to direct all visitors to go to th Reception Center at the NYS Fairgrounds".
Provide further guidance as directed by-the SSS/ED or ED/RM.
1H. General Electric BWR Emergency Support Program Notify at Alert, Site Area Emergency or General Emergency; provide follow-up information as REQUIREMENT' requested. .,
(408)971-1038 CONTACT METHOD. Start Tirnme. Date Person Contacted "This (is/is not) a drill. This is Nine Mile Point Nudle-arStition (1/2). This is to notify 'iou tha we are in a (state emergency class)." ,
- MESSAG E Provide your name, telephone number, and an alternate number t&ey may use.
I NOTE: Once communication is established with the TLAM, no further notification is necessary. (exception.is when you are tasked with event termination notifications)
Page 21, EPIP-EPP-20 Rev 15
ATTACHMENT 4 (Cont)
Sheet 4 of 5 I. INPO Emergency Response Center RQEENotify at Alert, Site Area Emergency or General Emergency; provide follow-up information as requested.
- 1. (800) 321-0614
- 2. (770) 644-8000 (switchboard)
CONTACT 3. (770) 644-8549 for FAX METHOD 4. (770) 644-8732 for FAX Confirmation Start Time Date Person Contacted "This (is~is not) a drill; This is Nine Mile Point Nuclear Station (1/2). This is to notify you thal we are in a (stateemergency class). When INPO Liaison responding to the emergency arrives in local area, they shbuld contact the Technical Liaison and Advisory Manager located in the MESSAGE EOF at (315) 593-5884 or (315) 593-5818."
NOTE: OnIrce communication is established with the TLAM, no further notification is necessary. (exception is when you are tasked with event termination notifications)
J. Oswego County Sheriff's Department REUbIREM*ENT*.. Notify at Alert, Site Area Emergency or General Emergency; provide follow-up information as requested.
1.911 3.349-3409 CONTACT 2. 343-5490 METHOD Start Time Date Person Contacted "This (isfis not) a drill. This is Nine Mile Point Nuclear Station (1/2). This is to notify you thal MESSAGE we are in a (state emergency class). (For Initial notification only) Please assign deputies to Lake Road at the east and west site boundaries to establish traffic control points."
K. DOE Federal Radiological Monitoring and Assessment Plan (FRMAP)
REQUIREMENT.. Notify at Alert, Site Area Emergency or General Emergency; provide follow-up information as requested.
- 1. (631) 344-2200 CONTACT:
METHOD Start Time Date Person Contacted MESSAGE . "This Uisis not) a drill. This is Nine Mile Point Nuclear Station (1/2). This is to notify you thai
- . we are in a (state emergency class).
L. American Nuclear Insurers Notify at Alert, Site Area Emergency or General Emergency; provide follow-up information as REQUIREMENT
- rqetd
- - :. requested.
(860) 561-3433 CONTACT, extension 304 S...
- METHOD MEHO.... :
- Start Time Date Person Contacted "This (is.'s not) a drill. This is Nine Mile Point Nuclear Station (1/2). This is to notify you thal we are in a (state emergency class).
MIESSAGE NOTE: Once communication is established with the TLAM, no further notification is necessary. (exception is when you are tasked with event termination notifications)
Page 22 EPIP-EPP-20 Rev 15
ATTACHMENT 4 (Cont)
Sheet 5 of 5 M. Oswego River Hydro Stations Notify at Alert, Site Area Emergency or General Emergency. Initial Notification only, no followup REQUIREMENT.-,",-.- required.
"1.(315) 413-2832 4. (315) 461-8671 (Fax) 2.-(315) 413-2839 CONTACT 3. (315) 413-2841 METHOD Start Time Date Person Contacted "This (is/isnot) a drill. Nine Mile Point Nuclear Station has declared a (state emergency class). Please tune in to your emergency alert system radio station for MESSAGE
.;*important it information and updates."
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ATTACHMENT 5: EMERGENCY RESPONSE DATA SYSTEM (ERDS) ACTIVATION Sheet 1 of 2 NOTES: The ERDS shall be activated within one hour of the declaration of an alert or higher.
Unit 1 ERDS console is located in the Aux Control Room, Process Computer Room.
Unit 2 ERDS Console is located in the Tech Assessment Room of the TSC.
Step 7 is required only if ERDS System is powered down.
- 1. Turn on / verify on the following:
"* Codex 2235 Modem
"* Codex 2171 Modem
"* ERDS PC (computer)
"* VAX to ERDS PC Modem Once turned on, after a short delay, the computer screen should display a screen similar to the following:
Nine Mile Point Unit 1 (2)
Emergency Response Data System (ERDS)
Authorized Access is Prohibited System name: erds 1 (2)
Console Login:
- 2. Log on the ERDS computer by entering the following keystrokes:
"* Type "erds"
"* Depress the "Enter" key
- 3. When the password prompt appears:
"* Type "erdsul for Unit 1, and erdsu2 for Unit 2, as appropriate
"* Depress the "Enter" key
- 4. When the system prompt appears ($), enter the following keystrokes 0 Type "erds" If performing a reconnection, enter the following keystrokes:
- Type "erds -r"
- 5. Verify the ERDS link is established by observing the following on the screen:
"Handshake complete. Beginning transmission" "Press DEL to "terminate program manually" Page 24 EPIP-EPP-20 Rev 15
ATTACHMENT 5 (Cont)
Sheet 2 of 2
- 6. Every 60 minutes after initial connection, verify that ERDS is still connected by time, date and sequence as displayed at the bottom center of the screen.
0 This information is contained at the end of the data packet, and should update every 60
.- seconds.
- If reconnection is necessary, go to Step 4.
- 7. When it is necessary to terminate the ERDS program, press the "DEL" key. Do not turn any equipment off. Unit I ERDS must be always "on".
"- TROUBLESHOOTING S...*.*.....
........ . . . . . . . . .. . ....i~. . . . . .
Loss of communications (after - 0 Reconnect using Steps 4, 5, 6 successful connection)
NRC host computer busy
- Contact NRC Duty Officer.(NRC red phone) for instructions NRC request you use a different
- At Step 4 enter "erdst ##########". (where phone number to call ERDS the # represent the area code and telephone number given to you by the NRC).
Following message appears Wait about 5 minutes after one of these "Timeout, remote host failed to messages first appears (this will give ERDS respond within 1 minute" time to establish a link on its own).
or "Remote host sent refused" S If no connection is made, contact the NRC Duty Officer (NRC red phone) for instructions.
Loss of source data, or any NMPC ERDS 0 Inform NRC Duty Officer (NRC red phone) of hardware problems. problems.
e Inform SSS/ED or ED/RM of problem.
0 Have SSS contact computer on call supervisor.
Computer console locks up.
- Re1boot and restart. May be accomplished by turning power Off and then back On, or by depressing "Control", "Alt", and "Delete" keys simultaneously.
Page 25 EPIP-EPP-20 Rev 15
ATTACHMENT 6: NRC EVENT NOTIFICATION WORKSHEET "EXAMPLE" Sheet 1 of 2 "This is to report an Incident at Nine Mile Point Start all NRC notifications with: Unit I / 2(as appropriate)'.
Page 26 EPIP-EPP-20 Rev 15
ATTACHMENT 6 (Cant)
Set2o RADiCLOGICAL RELEASES' CX OKORRFLLIN APPLCABLEITEMS (sr chfc d~t~jlsle=ansIfans should becvervd Intevffd mn ILIOUID RELEASE - GEOSRELEASE UNPLANED REL.EASE PLANNED RELEASE ONGOING b-RINATED ImO"JiToREo IUNMONIToRED 0 ~SITE RELEASE T. S. EXEIE RM ALARMS I kEAS EVACUATED PERSCNNE'-rL EXPOSED OR CCNTAMINATED loFFsITE PROTECTIVE AC-noNsRECOMMENDED SarIe.p v wc Release Rate (CIlsec) % T. S. LIMIT MOO GUIDE ITatarActivit (C- % T.*S. LIMIT LHOO GU'IDS Noble Gas _____________ . l/scj- 1000 C0 Iodrine ____________ ouilCsee 0.01 Gi Part~culate 1__________
t~ihcisc lmCi LUquld (excluding tritumn and dfssoloMd nobl. cases) 10____________0.10 101C LUquid (tzntlumr) __________0.2 CUmin 5C0
-To tal Activity
______________ PLANT STACK -CONDENSERIAIR EJECTOR MAIN STEAMULNE- SG BLOWDOWN OTHER RAD MAONrTOR READINGS ALARM SETPOINTS,
%T. S. UMIT ('If applkcable)
RCS OR SG TUBE LEAKS: CHECK OR FILL INAPPLICABLE ITEMS. fspecific detaflferplanaliorts should be covered in event desrculotF on)
LOCATION OFTHELEAK(a Vg.SG 2, vWe pfp,.,ate-)
LEAkK RATE LNTS W,,tcd T S&LI-MT aicce4 CR LoNGiEP-im cvOPGc LE)J(STARTDATE *)ECOOLANT ACT]VIKY PPJAAFZY SEC~ONDRY USTOF WAETY' RaEATEC ECUPTNT NOTaOPEATO~kLt Page 27 EPI P-EPP--20 Rev 15
ATTACHMENT 7: LOSS OF COMMUNICATIONS CAPABILITY FROM THE CONTROL ROOM OSWEGO COUNTY 800 MHZ RADIOC IF: You are using this radio due to a complete loss of communications from the control rooms, THEN:
- 1. Move to an outdoors location.
- 2. Select System 7(S button), Group 1 (G button).
- 3. Hold the talk button until you receive a beep; you are now clear to talk.
- 4. State "Nine Mile Point Unit _ Control Room to Dispatch".
- 5. State that normal communications systems have been disrupted.
- 6. Provide information as directed.
SATELLITE PHONE IF: You are using this satellite phone due to a loss of communications from the control rooms, THEN:
- 1. Move to an outdoors location.
- 2. Turn on the power using the RED button on the bottom left of the keypad.
- 3. Turn the antenna toward the sky and extend it.
- 4. Enter the PIN... 1111 and press the OK button.
- 5. The screen will now indicate, Searching.
- 6. If it says Check Signal, turn off the phone and move to a different location and start over.
- 7. If it says Blocked (because the PIN was entered incorrectly 3 times) then, A. Press the following key sequence: (*)(),(0+),(5),(*)
B. Enter the Unblocking code
- 1. for Unit 1 - 9599 9661
- 2. for Unit 2- 1375 4571
- 3. for EOF - 3428 9412 C. Enter the correct PIN code and press OK.
D. Re-enter the PIN code to verify
- 8. If it says Registered, wait for Iridium screen and dial out as follows:
A. To make all calls, hold 0 for approx. 2 seconds to get a plus sign (+), then 1, the area code, and the phone number, then press OK (there are no local call capabilities).
"* State that you are calling from Nine Mile Point Unit _ .
"* State that normal communications systems have been disrupted.
"* Provide information as directed.
B. To call other satellite phones, dial the satellite phone number, and then press OK.
"* Unit 1 Sat phone: 881631433584
"* Unit 2 Sat phone: 8816 3143 3583
"* EOF Sat phone: 8816 3143 3582 Note: There will be a small delay from the time you speak to the time the other party will hear you.
NINE MILE POINT RADIO IF: You are using this radio due to a loss of normal communications from the control rooms, THEN:
- 1. Move to an outdoors location.
- 2. Select Channel 16, (County Admin Channel)
- 3. Hold the talk button and state "Nine Mile Point Unit _ Control Room to 911 Center".
- 4. State that normal communications systems have been disrupted.
- 5. Provide information as directed.
Page 28 EPIP-EPP-20 Rev 15