ML20066C541
| ML20066C541 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/13/1982 |
| From: | Begor R, Blind A, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17319B646 | List: |
| References | |
| PROC-821013-01, NUDOCS 8211100041 | |
| Download: ML20066C541 (81) | |
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. PMP EPP INDEX O INDIANA & MICHIGAll POWER COMPANY DONALD C. COOK NUCLEAF PLANT PLANT MANAGER PROCEDURE Index Identification Title Revision No.I Comments Number And Date l PMP 2081 EPP.014 Off-Site Dose Assessments Revision +1 >-
10-12-82 EPP.015 Sampling and Analysis of ~
Revision 0 Waterborne Releases. 4-1-81 EPP.016 Collection and Analysis of Revision 0 Liquid and Gaseous Samples 4-1-81 EPP.017 Interpretation of Liquid Revision 0 and Gaseous Samples 4-1-81 h EPP.018 Transportation Accidents Involving Radioactive Revision 1 6-24-82 Material EPP.019 AEP Emergency Response Revision 0 Organization Activation and 4-1-83 Management EPP.020 Activation and Operation of Revision 1 TP-1,9-9-82 Exp NA the Technical Support Center 8-24-82 (TSC)
EPP.021 Activation and Operation of Revision 1 the Operations Stagins Area 5-25-82 (0SA) and Perscanel Accountabili ty EPP.022 Activation and Operation of Revision 1 the Emergency Operati.ons 6 4-82 Facility EPP.023 Activation and Operation of CANCELLED the Emergency Control Center 6-4-82 (ECC) (An Emergency Operations Facility) h EPP.024 Activation and Operation of the Joint Public Infonnation Revision 1 6-24-82 i
Center (JPIC) (An Emergency Operations Facility) pg 3 8211100041 821028
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(f INDIANA & MICHIGAN POWER COMPANY 00NALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE Index Identification Ti tle RevisionNo.l Ccmr. ants Numcer And Data i PMP 2080 EPP.001 Emergency Plan Activation Revision 3 and Condition Classification 10-12-82 EPP.002 Unusual Event CANCELLED 10-29-81 EPP.003 Alert CANCELLED 10-29-81 EPP.004 Site Emergency CANCELLED O7 .
10-29-81 EPP 005 General Emergency CANCELLED 10-29-81 EPP.006 Initial Dose Assessment Revision 3 (Gaseous) 8-27-82 EPP.007 Initial Release Assessments Revision 0 TP-1,2-23-82 Exp NA (Liquid) 4-1-81 EPP.008 Initiating Manning of Emer- Revision 3 gency Response Facilities 10-12-82
& Calling Off-Duty Personnel EPP.009 Fire Emergency Guidelines Revision 1 6-15-82 EPP.010 Toxic Gas Release Guidelines Revision 1 6-2-82 EPP.011 Natural Emcrgency Guidelines Revision 0 4-1-81 EPP.012 Initial Off-Site Notificatior Revision 1 [TP-1,8-13-82ExpNA 4-27-82 n
(1) 1 Rev. Ca 3 IChla- 22,
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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure No. PMP 2080.EPP.008 Revision No. 3 TITLE INITIATING MANNING OF EMERGENCY RESPONSE FACILITIES AND CALLING 0FF-DUTY PLANT PERSONNEL SCOPE OF REVISION Revision 1 - Added Graphical Phone Tree. Clarified assembly and call in, activate call list on TSC manning not Nuclear Emergency Alarm.
Revision 2 - Changed procedure title, revised and updated procedure body and Exhibit A. Incorporated Temporary Change Sheet i'
O Revision 3 - Revised call list, -
SIGNATURES ORIGINAL Rev.I REV.2 Rev.3 PREPARED BY e K. Baker P. Craig QUALITY ASSURANCF J. Stietzel J. Stietzel T. Beilman /
INTERFACING DEPARTMENT V M CONCURRENCE NA NA R. Becor Ib[d[h -
DEPARTMENT HEAD (.)
NA NA NA MA PLANT NUCLEAR S CO M E R. Keith A. Blind A. Blind PLANT MANAGER -
M RO M B. Svensson E. Townley W. Smith (ON tw /[ -
O
- AE FISSUE 03-31-81 04-29-82 08-27-82 l NM Form No. PMI 2010 may 2
PMP 2080 EPP.008 O LIST OF EFFECTIVE PAGES Page Number Revision Number And Date Page 1 of 2 Revision 3, Oct.12, 1982 Page 2 of 2 Revision 3, Oct.12, 1982 Page 1 of 6 EXHIBIT A Revision 3, Oct.12, 1982 Page 2 of 6 EXHIBIT A Revision 3, Oct.12, 1982 Page 3 of 6 EXHIBIT A Revision 3, Oct.12, 1982 Page 4 of 6 EXHIBIT A Revision 3, Oct.12,1982 Page 5 of 6 EXHIBIT A Revision 3, Oct.12,1982 Page 6 of 6 EXHIBIT A Revision 3, Oct.12,1982 Page 1 of 1 EXHIBIT B Revision 3, Oct.12,1982 Page 1 of 1 EXHIBIT C Revision 3, Oct.12,1982 0
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Page I of 1 Revision 3 Oct.12, 1982
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, PMP 2080 EPP.008 h INDIANA & MICHIGAN EIICTRIC COMPANY DONALD C. COOK NUCLEAR PLANT _
INITIATING MANNING OF EMERGENCY RESPONSE FACILITIES AND CALLING OFF-DUTY PLANT PERSONNEL 1.0 OBJECTIVES The objective of this procedure is to provide the information that is necessary to summon plant personnel during emergency conditions to staff the Emergency Response Facilities. '
2.0 RESPONSIBILITIES 2.1 The Shift Supervisor (SS)/On-Site Emergency Coordinator (OSEC) is responsible for initiating the actions required to staff the Emergency Response Facilities and to provide the required information to the parties called. Individual Department Heads are responsible for maintaining the call lists current.
2.2 Exhibit A* will be verified correct at least quarterly by the Operations Department. Where Exhibit A* requires initiation of (j) Section or Departmental call lists the applicable Department Head is responsible for maintaining these lists current.
NOTE: TO PROVIDE RAPID NOTIFICATION OF DEPARTMENTAL PERSONNEL, \
DEPARTMENT SUPERVISORS MAY ESTABLISH DEPARTMENTAL CALL TREES OR DELEGATE NOTIFICATION TO OTHER DEPARTMENTAL PERSONNEL.
3.0 APPLICABILITY 3.1 This procedure applies to any plant emergency event which requires plant personnel notification for purposes of staffing Emergency Response Facilities.
3.2 The procedure may be implemented anytime the SS/0SEC determines that it is necessary that on-site emergency personnel resources be augmented by off-duty plant personnel.
3.3 The TSC and OSA will be activiated for any event classified as an alert or higher.
3.4 The EOF will be activated for any event classified as a Site I Emergency or higher. )b l
- Exhibit A included in in plant copies of procedures only.
O Page 1 of 2 Revision 3
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PMP 2080 EPP.008 O 4.0 INSTRUCTIONS 4.1 Normal Working Hours 4.1.1 During normal working hours if the S.S./OSEC desires to activate the TSC and Operations Staging Area (OSA), a public address (P.A.)
announcement will be made stating " Activate the TSC". Any special reporting routes will be identified in conjunction with the P.A.
announcement. Assigned personnel will report to the TSC and 03A upon hearing the P.A. announcement. If sufficient personnel do not report directly to the TSC or OSA, they will be contacted via telephone by personnel in the TSC and OSA.
4.1.2 For site or general emergencies, personnel are to report directly to their assigned Emergency Plan duties upon hearing the Nuclear Emergency Alarm (NEA) unless the P.A. announcement following the NEA restricts their. route to their assigned station. Then they should report to the OSA and request guidance as to a safe route.
4.2 Off-Duty Hours 4.2.1 During off-duty hours, the S.S./OSEC will initiate calling of off-duty plant personnel to staff the Emergency Response Facilities by activating the Emergency Call List (Exhibit A*)
([) and provide any specific reporting restrictions by completing the Off-Duty Notification Information Sheet (Exhibit B).
4.2.2 When notified, others will accomplish their assigned portion cf Exhibit C. Personnel contacted should report directly to their assigned locations unless directed otherwise.
4.2.3 Security should set up for Lamediate processing of arriving off-duty personnel and establish an Assembly Area for reporting at the I-94 Guard House, if directed.
4.2.4 If additional staffing is required they will be contacted by phone by the responsible department.
- Exhibit A included in in plant copies of procedures only.
O Page 2 of 2 Revision 3
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PMP 2080 EPP.008 EXHIBIT A O SHIFT SUPERVISOR CALL-0UT LIST Perform the following:
- 1. Contact the Security Shift Supervisor on ext. or via the page.
State - We have initiated the Emergency Plan at a level of ,
please initiate the appropriate Emergency Plan Call-Out List 3 (Exhibit A Page 2 of 6). Provide any restriction which may require alternate reporting routes
- 2. Cont'act the NRC via the NRC Red Phone. (Continuous contact will be required for an alert or higher.) Provide Information on Exhibit B.
- 3. Contact the Operations Superintendent . . . . K. R. Baker -
or l Assistant Operations Superintendent . . H. M. Chadwell - ,
or O Production Supervisor Unit 1. . . . . D. R. Campbell /
l or /
'I Production Supervisor Unit 2 . . . . . C. E. Murphy - '
State-WehaveinitiatedtheEmergencyPlanataleveToT ,
please initiate the Operations Department Call-Out List. Provide 3 information on Exhibit B.
- 4. Contact the Plant Manager . . . . . . . . W. G. Smith, Jr. -
or Assistant Plant Manager Operations . . . B. A. Svensson - f I
or I I
Assistant Plant Manager Maintenance . . . E. L. Townley _
State - We have initiated the Emergency Plan at a level of please initiate the Managers Call List and report to the TSC.
3 Provide information on Exhibit B. .
Page 1 of 6
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PMP 2080 EPP.008 EXHIBIT A h SECURITY SHIFT SUPERVISOR CALL LIST A. Contact the Central Alarm Station (CAS), Second Alarm Station (SAS), and Guard Island and instruct them to initiate the appropriate Emergency Plan 2$
Call List Event is classsified at a (Exhibit A, page 3, 4, and 5 respectively).
B. Contact the following in the order listed:
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- 1. Maintenance Superintendent - R. L. Dudding . .. . ....
or Maintenance Production Supervisor - F. W. Wenman . ...
or Maintenance QCIC - D. G. Wizner . ........ . ...
State - We have initiated the Emergency Plan at a level of please initiate the Maintenance Department Call-Out for staffing the OSA
}3 and report to the OSA.
- 2. Performance Engineer - A. A. Blind . . . . . . . . . . .
or Performance Engineer - R. L. Simms .
....... . ... \
__.._m State - We have initiated the Emergency Plan at a level of ,
please report to the TSC. 3
- 3. Training Supervisor - D. D. Nelson . ...... . . ..
or ,
Training Instructor - J. D. Dickson . . . .... . .
or Training Instructor - W. A. Nichols . ..... . . ..
i
' State - We have initiated the Emergency Plan at a level of ,
please initiate the Training Department Call-Out List. Personnel are to 3 report to the (TSC and Berrien County Sheriff for an alert) or (EOF, Ber-rien County Sheriff, and JPIC for site or general emergency).
- 4. Assistant Plant Manager Oper. - B. A. Svensson . . . ... .
or Assistant Plant Manager Maint. - E. L. Townley . . . . .
-~ _ _ _ _ ,
State - We have initiated the Emergency Plan at a level of , j3 please notify the other Assistant Plant Manager and report to the Plant.
u C. If directed or if the event is classified as site emergency or higher ~~
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([) dispatch guards to activate the EOF.
Page 2 of 6 Revision 3
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. . l PMP 2080.EPP.008 EXHIBIT A k) '
CENTRAL ALARM STATION CALL-0UT LIST Call the following in the order listed, the event is classified as .
3 i 1. R. L. Simms . ......'..........
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or R. Hennen . ..... . .. . . . . . . . . .
or A. Verteramo ................
State-WehaveinitiatedtheEmergencyPlan,pleasereportto$keTSC.
- 2. C&I Supervisor - D. Duncan . . . . . . . . .
or C&I Foreman - C. Miles . . . . . . . . . . .,
i or C&I Foreman - D. Sammons . . . . . . . . . .
State - We have initiated the Emergency Plan, please contact two C&I Technicians to report to the OSA and you report to the TSC. l3 (h) ~~
4
- 3. V. D. Vanderburg . . . . . . . . . . . . . 1 or E. A. Abshagen . .. . . . . . . . . . . . .. -
or T. A. Kriesel . . . . . . . . . . . . . . . .
State - We have initiated the Emergency Plan, please report to the TSC. 3 (TSC for an Alert) (EOF for Site or General Emergency) i 4. PET (Electrical)
- W. Pauls . . . . . . . . . . . . . . . . . . ' 3 or i D. Sudkamp . ..... . . . . . . . . . . }
I or ,
R. Hannigan . ..... . . . . . . . . . i State - We have initiated the Emergency Plan, please report to the TSC.
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. PMP 2080 EPP.008 EXHIBIT A SECONDARY ALARM STATION CALL-0UT LIST Call the following in the order listed', the event has been classified as 3 an . i
- 1. Duty Maintenance Foreman.- Obtain name and number from Maintenance Depts.
.. Weekly Callout list.
or ,
Maintenance Production Supervisor - F. Wenman . . . . ...
, State - We have initiated the Emergency Plan, please contact 2 electricians ly and 1 mechanic to report to the OSA and you are to report to the OSA also. t
- 2. A. Tetzlaf . .................... ...
or W. Stoner . . .................... ..
or A. Might . ..................... . .
or J. Piotrowski . . . . . . . . . . . . . . . . .'. . . . .. i
((g or .
C. Wi1 son . . .................... . .; 3 State - We have initiated the Emergency Plan, please report to the (TSC 3 for an Alert) (EOF Site or General Emergency) d
- 3. Chenical Superintendent - J. Wojcik . . . . . . . .. . .
or Chemical Foreman - R. Looker . . . . . . . . . . . . . . !
or Chemical Foreman - W. Lentz . . . . . . . . . . . .. .
j or Chemical Foreman - J. Ersland . . . . . . . . . . . . . .
State - We have initiated the Emergency Plan, please initiate the Chemical Section Call-Out and report to the TSC.
- 4. Contact 6 of the following:
R. Krieger . ................. . . . . .. f or !
R. Hennen . . .......... . . . . . . . . .. . . 3 or 4 . ;
W. Gillette . .................... . .
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G. Haganiers . ... . . . . . . . . . . . . . . . . . . 1 o
or -
Page 4 of 6 Revision 3
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PMP 2080 EPP.008 EXHIBIT A SECONDARY ALARM STATION CALL-0UT LIST
- 4. Continued W. Pauls . . ............... . . . ...
or D. Sudkamp . ......................
., or l C. Rocs .............. . . . . . . ... r l
or l J. Piotrowsky . . . . . .. . . . . . . . . . . ...
or f C. Wilson ......................
or V. Vukorpa . ......... . . . . . . . . . ...
State - We have initiated the Emergency Plan, please report to the (TSC Alert) (EOF Site or General Emergency)
- 5. Contact 2 of the following:
R. Palmer . . . . . . . . . . . . . . . . . . . . . . . I or J. Rischling . . . .. . . . . . . . . . . . . . . ..:
On. or S. Delong ........... . . . . . . . . . . .i 3 or .
A. Might . ............. . . . . . . . ..
-___._ .I.
State - We have initiated the Emergency Plan, please report to the (TSC ,
Alert) (EOF Site or General Emergency) -
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Page 5 of 6 Revision 3
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PMP 2080 EPP.008 EXHIBIT A GUARD ISLAND EMERGENCY PLAN CALL-0UT LIST Call the following in the order listed:
- 1. R. P. Foreman:
J. Hoss . . . . .,. . . .' . . . . . . . . . . . . ..
or .
D. Schroeder . ...... . . . . . . . . . . . .. I, or J. Fryer . . .. ..... . . . . . . . . . . . . . :'
State - We have initiated the Emergency Plan, please initiate the R.P.
Emergency Plan Call-Out List. .
- 2. Dose Assessment:
D. Palmer . . .... . . . . . . . . . . . . . . . k or '
W. Ketchum . ..... . . . . . . . . . . . . . . .
or J. Nelson . ...... . . . . . . . . . . . . . .,
J3 or
/~ M. Glissman . . ..... . . . . . . . . . . . . ..
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State - We have initiated the Emergency Plan, please report for dose ;3 assessment duties at the (TSC for Alert) (EOF for Site or General Emergency). Contact dose assessment support personnel.
- 3. J. Fryer . . ....... . ... . . . . . . . . . . \
or k D. Schroeder . ...... . ..... . . . . . . . . \
State - We have initiated the Emergency Plan, please report to the Plant.
- 4. PET (Mech.)
'K. Chapman . .. ..... . . . . . . . . . . . .. s3 or M. Lester . . . ..... . . . . . . . . . . . . .
or W. Golden . . . ..... . . . . . . . . . . . . .
or \
i C. Flis . . . .. .... . . . . . . . . . . . . .
i or i C. Wilson . . . . . . . . . . . . . . . . . . . .
or J. Piotrovski . ..... . . . . . . . . . . . . .. - '
- d'"
,cy . .. -
k) i State - We' have initiated the Emergency Plan, please report to the TSC. . . , , ,
Page 6 of 6 Revision 3
t Y PMP 2080 EPP.008 EXHIBIT B O
OFF-DUTY NOTIFICATION INFORMATION SHEET Plant Manager or Operations Superintendent notified of the following information:
Information given to responding personnel:
- 1. Emergency was declared at .
(Classification) (Time) 2.
(Nature of incident and status of plant)
- 3. A release to the environment has not occurred ; has occurred ; is occurring _ _; may occur .
- 4. Projected Dose Rates at or near the site boundary are 0 -
Page 1 of 1 Revision 3
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. INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT O
PROCEDURE COVER SHEET Procedure No.PMP 2081 EPF.014 Revision No. 1' I ! TITLE OFF-SITE DOSE ASSESSMENTS SCOPE OF REVISION Revision 1 - Complete revision to include use of hand-held calculators as back-up assessment tools. SIGNATURES ORIGINAL Rev.I REV.2 Rev.3 PREPARED BY q fy.4 QU ASSURANCE OI [f/h.I INTERFACING DEPARTMENT / / HEAD CONCURRENCE b /'N.A. ( . DEPARTMENT HEAD U APPROVAL N.A. y PLANT NUCLEAR SAFETY COMMITTEE . - PLANT MANAGER APPROVAL h - l j V
/
DATE OF ISSUE 3-31-81 [C -/8-76
- 8) PER TELECOPY 3/27/81 ran. no. m 2o:o-i . nav. :
PMP 2081.EPP.014 LIST OF EFFECTIVE PAGES Page Number Revision Number and Date 1 of 7 Revision 1 - Oct.12,1982 2 of 7 Revision 1 - Oct.12,1982 3 of 7 Revision 1 - Oct.12,1982 4 of 7 Revision 1 - Oct.12,1982 5 of 7 Revision 1 - Oct.12,1982 6 of 7 Revision 1 - Oct.12,1982 7 of 7 Revision 1 - Oct.12,1982 EXHIBIT A, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT B, Page 1 of 1 Does not Exist EXHIBIT C, Page 1 of 1 Does not Exist EXHIBIT D, Page 1 of 1 Revision 1 - Oct.12,1982-EXHIBIT E, Page 1 of 4 Revision 1 - Oct.12, 1982 Page 2 of 4 Revision 1 - Oct.12,1982 Page 3 of 4 Revision 1 - Oct.12,1982 Page 4 of 4 Revision 1 - Oct.12,1982 (]~ EXHIBIT F, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT G, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT H, Page 1 of 2 Revision 1 - Oct.12,1982 Page 2 of 2 Revision 1 - Oct.12,1982 ATTACHMENT I, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT I, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT J, Page 1 of 2 Revision 1 - Oct.12,1982 Page 2 of 2 Revision 1 - Oct.12,1982
- EXHIBIT K, Page 1 of 1 Revision 1 - Oct.12,1982 l EXHIBIT L, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT M, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT N, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT 0, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT P, Page 1 of 1 Revision 1 - Oct.12, 1982 l EXHIBIT Q, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT R. Page 1 of 1 Revision 1 Oct.12, 1982 O Page 1 of 2 i
l Revision 1
o PMP 2081.EPP.014 LIST OF EFFECTIVE PAGES -- Page Number Revision Number and Date EXHIBIT S, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT T, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT U, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT V, Page 1 of 1 Revision 1 - :0ct.12,1982 EXHIBIT W, Page 1 of 1 Revision 1 - Oct.12,1982 O 1 l O Page 2 of 2 Revision 1 I
> a PMP 2081.EPP.014
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INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT OFF-SITE DOSE ASSESSMENTS 1.0 OBJECTIVES This procedure is to be used for manual dose calculations (with hand calculator program) of off-site doses fran plant releases. It is intended to provide conservative dose rates and projected doses at specified points in the emergency planning zone. This procedure shall be perfonned under direction of the RAD (Radiological Assessment Director). Provisions are included for:
- 1) Detennining the Atmosphere Dispersion-Factor (x/Q) based on the Atmosphere Stability Class (i.e., Pasquill Category) and distance fran the point of release to the point of projected dose.
- 2) Correcting the dose to account for the time after shutdown that the source data is taken. -
- 3) Accounting for the results of measurements made by survey teams in the field.
~O 2.0 RESPONSIBILITIES The Radiological Assessment Director in the TSC or EOF is responsible for calculating dole body and thyroid dose projections. The Radiolo-gical Assessment Director and the On-Site Emergency Coordinator are to use these calculated values in detennining possible off-site conse- '
quences fran a release of radioactivity and for evaluating protective actions. 3.0 APPLICABILITY This procedure shall be use to calculate dose rates to the whole body and thyroid at the site boundary and at specified points within the emergency planning zone. It shall also be used to determine projected doses within the emergency planning 2cne integrated over the duration of the release and to correlate calculated and projected doses with actual field measurenents. If MIDAS and/or CPM 002 conputer programs are available, use them to calculate the dose rate and projected doses, or to provide an entry point into the hand calculator program. O Page 1 of 7 Revision 1
, , PMP 2081 EPP.014
> 4.0 INSTRUCTIONS NOTE: Initial dose estimates may be made by PMP 2080.EPP.006 or by the h use of the AEPSC conputer programs CPM 002 or f1IDAS. 4.1 The RAD shall perfonn the following functions and record all data on the appropriate exhibits: 4.1.1 Detennine the Pasquill Category and record meteorological data on Exhibit C.I 4.1.1 -1 If meteorological data is available fran the computer, obtain and record Pasquill Category, wind speed and direction, AT and precipiptation on Exhibit C. 4.1.1 -2 If meteorological data is not available fran the canputer, obtain it fran Exhibit 8, the Technical Infonnation Sheet. 4.1.1 -3 To detennine Pasquill Category using AT infor-mation, use the following guide: Pasquill AT=(T,180f t-T,30f t) ,'C *C/100m Ca tegory '
-0.87 -1.9 A
-0.87 to -0.78 -1.9 to -1.7 B
-0.78 to -0.68 -1.7 ' to -1.5 C
-1.5 to -0.5
-0.68 to -0.23 D
-0.23 to 0.68 -0.5 to 1.5 E 0.68 to 1.83 1.5 to 4.0 F 1.83 and above 4.0 and above G 4.1.1 -4 If infonnation about AT is unavailable fran meteorological tower or Exhibit B, Pasquill
- Category may be estimated using this c%rt:
Sunny Cloudy Cloudy Clear Day Day Night Night light wind or calm (<9.8 mph) B C E F moderate, strong l wind (>9.8 mph) C D D D 4.1.2 Canplete the lower two-thirds of infonnation on Exhibit C (fran Basis for Projected Dose onward). This includes calculation of dose rates and projected doses to whole body and thyroid as well as making recanmendations for support or energency actions based on this data. I References to Exhibit 8 and Exhibit C refer to those exhibits as found in l O eMe 2081.EPP 020. Page 2 of 7 l Revision 1 l
PMP 2081.EPP.014 ) . 4.1.3 Coordinate infomation being used to canplete Exhibit C
@ in the TSC and EOF as the transition from TSC to EOF is
- made using Exhibit A, Off-Site Dose Assessment: EnF/TSC Coordination Checklist. i y 4.2 Calculation of dose rates and, projected doses to the sole body and thyroid is performed using the method outlinea below: NOTE: Reference for details of using the . hand calculator pro-gran is Exhibit E, Off-Site Dese Program. Flow sheet for this progra:a is Exhibit F, 'Jff-Site Dose Program Flow Sheet. 4.2.1 Load both sides of both program cards. - 4.2.2 Enter the progran by specifying the Pasquill Category. 4.2.3 When 610 appears, specify boundary distance in meters. R/S 4.2.4 When 0.01 appears, specify wind speed in mph. R/S 4.2.5 When 0. appears, enter release rete in Cf/sec. R/S (For details on calculating release rates, see Exhibit E). , 0 425 wa a 2 PP rs. at r r 1 = ciassificatiaa (as d - fined in Exhibf t G). If classification is 7, Isotopic Mixture program, Exhibit H, should be used. R/S 4.2.7 Read whole body (thyroid) dose rate at site boundary. R/S 4.2.8 After site boundary distance flashes, read whole body- - (thyroid) dose rate at site boundary. Record this value for Dose Rate. P/hr, on Exhibit C, Accident Infomation Reporting Data Sheet. Record values to three significant figures; if valu:s are <0.001, record as "<0.001". R/S 4.2.9 After 2 (representing 2 miles), flashec, read and record values as described in 4.2.8. R/S 4.2.10 Repeat step 4.2.9 for distances of 5 and 10 miles. R/S ,
~
4.2.11 Wen 15. appears, specify exposure time in minute,s. R/S 4.2.12 Read sole body (thyroid) boundary dose for this case. R/S 4.2.13 Read whole ob' dy (thyroid) dose at boundary integrated fran beginning of event. Record values on Exnibit D. Integrated Dose and Projected Dose Worksheet. R/S O .
' Page 3 of 7 a Revision 1 i
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s 5 O PMP 2081.EPP.014 4.2.14 When 60. appears, enter projected time of release, in
@ minutes. R/S 4.2.15 After site toundary distance flashes, read total (inte-grated plus projected) whole body (thyroid) dose at site boundary. Record this dose under Integrated Dose, R, on Exhibit C, Accident Infomation Reporting Data Sheet.
R/S 4.2.16 After 2 (representing 2 miles) flashes, read and record values as described in 4.2.15. R/S 4.2.17 Repeat setp 4.2.16 for distances of 5 and 10 miles. 4.2.18 R/S. This will return the program to step 4.2.5. Use step 4.2.5 as the entry point for subsequent calculations
, unless:
4.2.18-1 Pasquill Category changes. If this occurs, return to step 4.2.2. 4.2.18-2 A measured dose rate obtained by a sampling team at the site boundary is the new basis for cal culations. If this is the case, go to step 4.2.19. 4.2.18-3 A measured dose obtained by a samplirg team at h the site boundary is the new basis for cal-culations. In this case, go to step 4.2.20. 4.2.18-4 Concentrations of noble gases and radiofodines fran isotopic analysis are the new basis for cal culations. If this is the case; go to step 4.2.22 and use Exhibit H, Isotopic Mixture , prog ram. 4.2.19 If give a dose-rate obtained by a sampling team at the site boundary, enter values in X and t registers (whole j body in X, thyroid in t). Press B. 4.2.19-1 This takes the program to step 4.2.8. Follow
- procedure through to step 4.2.18.
l l 4.2.20 If given a dose obtained by a sampling team at the site i boundary, enter values in appropriate X and t registers l (whole body in X, thyroid in t). Press D. 4.2.20-1 This takes the program to step 4.2.13. Follow l procedure through to step 4.2.18. 4.2.21 A reset of integrated doses to zero may be perfomed in i case of mistake or significant change in wind direction. h Page 4 of 7 Revision 1
i .e PMP 2081.EPP.014 b To reset integrated doses to zero in both registers, press GTO, then CLR. When numbers appear in the display, l press D and go to step 4.2.13. 4.2.22 If classification in 4.2.6 is entered as 7, the number 0.04249 will appear. The program. Isotopic Mixture (Exhibit H and I), is to be used according to instruc-tions contained therein. For more details, refer to Exhibit E. NOTE: If meteorological conditions change, the pro-gram can be restarted at step 4.2.2 without losing any integrated dose data. Any time the calculator is not computing, the program may be redirected or restarted by pressing any of the user-defined keys (A-E or A'-E') without-losing integrated dose totals.- 4.3 Definition of Exhibits NOTE: Other pertinent informatie6 that may be required for analysis or decision makini may be found in the Radia-tion Assessment Director (RAD) Data Book. 4.3.1 Exhibit A: Off-Site Dose Assessment: EOF /TSC Coordina-g tion Checklist This is for use during the transition of operations from the TSC to the EOF. It is used to ensure that the same information is being used as the basis for calculations of dose rate and dose in both the TSC and the EOF. 4.3.2 Exhibit B: Technical Information Sheet . The Oose Parameters section of this sheet is used to obtain meteorological and release data essential for use with the hand calculator and/or CPM 002 programs for dose rate calculation. 4.3.3 Exhibit C: Accident Information Reporting Data Sheet The information in the top section of this sheet is to be filled out and supplied by sources supporting the RAD. The remaining portion is used for recording the basis for projected dose; the meteorological conditions; the dose rates and projected doses to whole body and thyroid at the site boundary 2, 5 and 10 miles; and recommendations for support and emergency actions. This form is in triplicate. 4.3.4 Exhibit D: Integrated Dose and Projected Dose Worksheet This is to function as a worksheet for recording the
^
values for whole body and thyroid dose at the cite boundary integrated from the beginning of ever.t. Page 5 of 7 Revision 1
PMP 2081.EPP.014 4.3.5 Q Exhibit E: Off-Site Dose Program This document is meant to provide detailed instructions for use of the hand calculator program for off-site dose assessment, including manipulating raw data for use in the prograin and implementing the program in varying si tuations. 4.3.6 Exhibit F: Off-Site Dose Program Flow Sheet This is the flow sheet for use with Exhibit E when specific details of the program need not be reviewed. I 4.3.7 Exhibit G: Off-Site Dose Program Attachment 1 This lists the various release pathways with their associated possible release mixtures, conversion factors and release classifications. It is design:d for use with Exhibit E. 4.3.8 Exhibit H: Isotopic Mixture Program For use with the hand calculator when concentrations of noble gases and radioiodines are available from isotopic analysi s. 4.3.9 Exhibit I: Isotopic Mixture Program Flow Sheet This is the flow sheet for use with Exhibit H when specific details of the program need not be reviewed. 4.3.10 Exhibit J: x/0 Dispersion Factors Program This program is for use with the hand calculator when dose calculations are based on non-standard distances. 4.3.11 Exhibit K: x/0 Dispersion Factors Program Flowsheet This flowsheet is for use with Exhibit J when specific details of the program need not be reviewed. 4.3.12 Exhibit L: Graph of monitor cpm vs. release rate, Ci/ sec 01 cfm for R-15 (Steam Jet Air Ejector). 4.3.13 Exhibit M: Graph of monitor cpm vs. release rate, Ci/sec 01 cfm for R-26 (Unit Vent Radiogas). 4.3.14 Exhibit N: Graph of monitor cpm vs. release rate, Ci/ sec 01 cfm for R-33 (Gland Saal Exhaust). 4.3.15 Exhibit 0: Graph of radiation levels at 6 inches fran Unit Vent sample line, R/hr, vs. release rate, Ci/sec 0 1 cfm. 4.3.16 Exhibit P: Graph of radiation levels at 6 inches from Unit 1 SJAE line, R/hr, vs. release rate, Ci/sec at 1 h c fm. Page 6 of 7 Revision 1 L
o , , , PMP 2081.EPP.014 4.3.17 Exhibit Q: Graph of radiation levels at 6 inches from Q Unit 1 Gland Seal Exhaust line, R/hr, vs. release rate. C1/sec 01 cfm.. 4.3.18 Exhibit R: Graph of radiation levels at 6 inches from Unit 2 SJAE line, R/hr, vs. release rate, Cf/sec 01 cfm. 4.3.19 Exhibit S: Graphs of radiation levels at 6 inches from Unit 2 Gland Seal Exhaust line, R/hr, vs. release rate, C1/sec 01 cfm. - 4.3.20 Exhibit T: Reconmended Protective Actions for Popula-tion and Workers For use with Exhibit C for detennining recommended pro-tective actions. 4.3.21 Exhibit U: Map of Donald C. Cook Nuclear Plant Site For use with Exhibits J and K for detennining sampling site locations. 4.3.22 Exhibit V: Description of Sampling Site Locations For use with Exhibit U for obtaining geographical data of sampling sites. 4.3.23 Exhibit W: Main Steam System Emergency Release O Detemination For use in detemining release rate den given a reading in R/hr at a sampling location. Use in conjunction with Exhi bi t E. O Page 7 of 7 Revision 1 1
- , ._ - .= .. _.- . . .. . . _ _ _ _ . _ _ _ . # 4 i
PMP 2081.EPP.014 , EXHIBIT A DATE: 0FF-5ITE 005E ASSESSMENT: EOF /TSC C0000!NAft0N CHECKt!$T l UNIT: TIME: 0 Estimated Duration of Release i l Basis for Projected Dose Information Wind Speed WindDirection(From) aT.'c Pasquill Category __ Site Boundary Distance _ Release Type (path & incident) , Graph Data: Curve Used Value Obtained Nomograph Used: _ Iodine Factor Release Rate. C1/sec Release Classification (f) Dose Rates. WB and Thyroid Integrated Doses from Beginning of Event (WB ar.d Thyroid) Projected Doses for Duration of Event Sectors Involved 8 Support & Emergency Actions Fill in appropriate time across too; check off items down list or record values to correlate information used in TSC and EOF. Data Verified By Page 1 of 1 chara.,,_3
- PMP 2081.EPP.014 EXHIBIT D i INTEGRATED DOSE AND PROJECTED DOSE WORKSHEET Q DATE:
. Integrated Dose: Notes or Scratch Margin Time : Site Boundary
_ . _ _ Thyr, R .. .. Sectors Involved I Time : W.R Thyr, R Sectors Involved Time : WB, R Thyr, R Sectors Involved - Time : WB, R , Thyr, R I Sectors Involved Time : WB, R Thyr, R Sectors Involved Time : g WB, R Thyr, R Sectors Involved Data Verified By . Page 1 of 1, Revision 1
PMP 2081.EPP.014 . EXHIBIT E !
. . i 0FF-SITE DOSE PROGRAM INTRODUCTION:
This program is designed to calculate dose rates, integrated doses and pro-jected doses for both whole body (from immersion) and adult thyroid (fran '- inhalation) at the site boundary and at 2, 5 and 10 miles using hand calcula-tor programs. It takes into consideration meteorological conditions, Pasquill categories A through G and wind speeds in mph (except 0). The following options are available: - - -
- 1) Calculation of dose rates to whole body and thyroid for either the 610 -
meter or 1200 meter site boundary and for 2, 5 and 10 miles given a re-lease rate in Cf/sec.
- 2) Given the exposure time and information about dose rates as in Option 1),
calculate the dose to the whole body and thyroid at the site boundary.
- 3) Given the boundary dose to whole body and thyroid, and an estimated dura-tion of release, calculate total (i.e., integrated dose and projected dose) dose to whole body and thyroid at the site boundary, and at 2, 5 and 10 miles.
- 4) Given a specific measursent of dose rate at either side boundary, calcu-lata dose rates, doses and total (i.e., integrated plus projected) doses to the whole body and thyroid at site boundary, 2, 5 and 10 miles.
O 5) Given concentrations of ncble gases and radiciodines from isotopic analy-sis, calculate the effective energy and thyroid dose functions of a mixture of noble gases and radiotodines using the Isotope Mixture Program Option (Exhibit H).
- 6) Given a specific measurenent of dose rate at any point in the Emergency Planning Zone, calculate dose rates to the whole body and thyroid at any specified distance fran this point.
I INSTRUCTIONS FOR USE (HAND CALCULATOR PROGRAM): t 1) Load both sides of both program cards (select off-site dose data program card with the range of Pasquill categories most likely to be encountered under current wather conditions).
- 2) Enter the program by specifying the appropriate Pasquill category, as follows :
O eese 1 of 4 Revision 1
PMP 2081.EPP.014 EXHIBIT E ] Card with Pasquill Range Card with PasgJill Range A-F B-G Pasquill Category User Defined Key User Defined Key A A' - B B' A' C C' B' D D' C' E E' D' F E E' G - E
- 3) Read 610. Enter site boundary distance in meters, if different fran 610 (if /610m, program will assume 1200m, no matter what other value is put in). R/S
- 4) Read 0.01. Enter wind speed in mph (0.01 mph is the default value). R/S
- 5) Read O. Enter gross release rate in Ci/sec. R/S (The release rate may be detemined fran attached graphs (Exhibits J-Q) by first selecting the release pathway of greatest importance (usually highest cpm) fran the Technical Infonnation Sheet, Exhibit B, and then selecting the appropri-ate graph fran Exhibits J-Q. Use the cpm value to obtain the release rate in Ci/sec at 1 cfm. Fran Exhibit B, find the cfm for the release in question. Multiply the value obtained fran the graph by the flowrate in Q c fm. This will yield the release rate in Ci/sec which is to be entered into the hand calculator program.)
- 6) Read 2. Enter the appropriate release classification, if other than 2.
See Exhibit G for description of release pathways and mixtures and how they relate to release classification (case f). R/S (NOTE: If classi-fication is 7, go to step 22.)
- 7) Read sole body and thyroid dose rate at site boundary. (Whole body dose rate is in the X register (i.e., display). To see thyroid dose rate, press Xst. After reading it, press Xst again to restore whole body dose to the X register. Always operate the program with whole body figures in the X register.) If an additional release pathway is to be included in the calculation, press user defined key A and return to step 5. Other-wise, R/S.
- 8) Site boundary distance will flash (610 or 1200). Read total whole body and thyroid dose rates at site boundary and record them in the appropri-ate space for Dose Rate, R/hr, on Exhibit C, Accident Infonnation Reporting Data Sheet. Record values to three significant figures; if values of less than .001 are obtained , record them as "<.001". R/S
- 9) 2 (representing 2 miles) will flash; read and record total whole body and thyroid dose rates as described in step 8. R/S
- 10) Repeat step 9 for dose rates to whole body and thyroid at 5 and 10 miles.
O R/S Page 2 of 4 Revision 1
r , I
', PHP 2081.EPP.014 EXHIBIT E Q 11) Read 15. Enter time of exposure, in minutes, if other than 15. R/S l 12) Read whole body and thyroid dose at site boundary for this case. R/S
- 13) Read dole body and thyroid dose at site boundary integrated from the beginning of the event. Record these values on Exhibit D. Integrated Dose and Projected Dose Worksheet. R/S
- 14) Read 60. Enter the projected time of release, in minutes. R/S
- 15) Site boundary distance will flash. Read the total (i.e., integrated plus projected) whole body and thyroid dose at the site boundary and record
, under
- Integrated Dose, R, on Exhibit C, Accident Infomation Reporting Data Sheet. R/S
- 16) 2 (representing 2 miles) will flash; read and record the total (i.e.,
integrated plus projected) whole body and thyroid dose as described in step 15. R/S
- 17) Repeat step 16 for total dose to whole body and thyroid at 5 and 10 mil es.
- 18) R/S. Display will now read 0., indicating a return to step 5 in the program and readiness to begin another series of calculations. Use step 5 as the entry point for subsequent calculations unless:
O a) Pasquill category changes. program. If this occurs, return to step 2 in the b) A measured dose rate obtained by a sampling team at the site boun-dary is the new basis for calculations. If this is the case, go to step 19 in the program. c) A measured dose obtained by a sampling team at the site boundary is the new basis for calculations. In this case, go to step 20 in the prog ram. d) Concentrations of noble gases and radioiodines from isotopic analysis are the new basis for calculations. If this is the case, go to step 22.
- 19) What to do if given a dose-rate obtained by the sampling team at the ,
site boundary: i Enter values in appropriate X and t registers (whole body in X, thyroid in t) and press B. R/S (NOTE: If the measurenents were taken at a boundary other than the one used in calculations, go back and reset Pas-quill category and go through steps 3 through 5. When 3ou read 0, at step 5, follow instructions listed here in step 19.) R/S a) You are now at ste.p 8. Follow procedure through from step 8 through step 18. Page 3 of 4 Revision 1 t
PMP 2081.EPP.014 EXHIBIT E . 20) What to do if given a dose obtained by the sampling team at the site boundary. Enter values in appropriate X and t registers (whole body in X, thyroid in t) and press D. R/S (NOTE: If measurenents were taken at a boundary other than the one used in calculations, go back and reset Pasquill cate-gory and go through steps 3 to 5. When you read O. at step 5. follow in-structions listed here in step 20.) R/S a) You are now at step 13. Follow procedure through from step 13 through step 18.
- 21) To reset integrated doses to zero in both registers, press GTO, then CLR.
When numbers reappear on the screen, press D and go to 13. A reset of integrated doses to zero might be done if a mistake were made or if the wind made a significant change in direction.
- 22) If isotopic sample analysis results are given, when 0. appears in the register after going back through A, go to step 1 of Exhibit H, the Isotopic Mixture program. Usually, the program Isotopic Mixture, Exhi-bits H and I, will be run to detemine the effective energy and thyroid dose factor fran the isotopic mixture. (If this is not done, enter the thyroid dose factor in the t register and the effective energy in the display (i.e., X register). R/S.) If Isotopic Mixture program is selected, go to Exhibit H and follow the instructions therein.
NOTE: If meteorological conditions change, the program can be restarted at step 2 without losing any integrated dose data. Any time the calculator is not canputing, the program may be redirected or re-started by pressing any of the user defined keys ( A-E or A'-E') without losing integrated dose totals. O Page 4 of 4 Revision 1
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- PMP 2081.EPP.014 EXHIBIT F hhhhhh (Specify Pasquill Category)
(GotoCLR)
,, s e y v v v v 510. ( Specify bour:dary distance ) (R/S) v 0.01(Specifywindspeed) Reset W.B. and thyroid integrated doses te zero is Calculate dispersion factors V
< (CalcD/2) v o 0.
(Enterreleaserateh.............1 If isotopic concentrations
- are known, use isotopic j
,, mixture program ;
- 2. ( Specify release classification ) !
e
,, j Read W.B. (thyroid) dose-rate at .. 3 l the bourdary l If other release pathways are ;
- to be calculated repeat dose .-..-
calculation vi A Flash boundary Read total W.B. (thyroid) dose. rate di stance, 2.5.10 at boundary, 2,5 and 10 miles j @(W/0.R) t v
- 15. ( Specify uposure time )
3, No Yes Read W.B. (thyroid) boundary dose Have any doses been for this case integrated? i
< @(W/D) i/
Add to integrated doses v ReadW.B.(thyroid)doseatboundary integrated from beginning of event Read value(s) at flash bounda n boundary, 2.5.10 di stance, 2.5.1 ,jj,3
- 50. ( Enter projected time of release )
V h(off. site) Read total (integrated plus projected) d nc 5 10
'd B yroid) dose at boundary, 2.5, jf (w, OFF. SITE 00SE PROGRAM FLOW SHEET Revision . 11 June, 1982 Goto A Page 1 of 1 Revision I
PMP 2081.EPP.014
. . EXHI8IT G CONVERSTION FACTORS O^. -
PATMlAY MIXTURE g THY CASE # R12 Fresh Fission Gas .14685 45.398 1 Primary Coolant .05888 3.9388 _ 2 _ NUREG-0578 .2444 .2723 3 R15 Primary Coolant Leakage .051964 .08077 ~ 4 NUREG-0578 Leakage .2453 .54256 5 R26 Old Fission Gas .04249 0 6 Fresh Fission Gas .14685 45.398 1 Primary Coolant Leakage .05888 3.9388 2 NUREG-0578 .2444 .2723 3 R33 Primary Coolant Leakage .051964 .08077 4 NUREG-0578 Leakage .2453 .54256 5 SGPORV Primary Coolant Leakage .051964 .08077 4 h NUREG-0578 Leakage .2453 .54256 5 SGSV Primary Coolant Leakage .051964 .08077 4 NUREG-0578 Leakage .2453 .54256 5 Any Sample Analysis Results as detennined fram analysis 7 NUREG-0578 Assumes Fuel Damage Effects. O Page 1 of 1 Revision 1
PMP 2081.EPP.014 EXHIBIT H ISOTOPIC MIXTURE PROGRAM . . _ The program is designed to operate in conjunction with the Off-Site Dose Pro-gram to calculate the effective energy and thyroid dose functions of a mixture of nobel gases and radioiodines for which concentrations are available from isotopic analysis. It will calculate the functions as well as the flow rate and transfer the infomation to the Off-Site Dose Program without any loss of data from that program. The following options are available:
- 1) Any mixture of identified nobel gases and radioicdines may be analyzed.
- 2) If the release rate of nobel gases is known, but not the camposition, pre-established isotopic mixtures of nobel gas are available, assuming nomally contaminated primary coolant or NUREG-0578 (fuel damage) contam-inated coolant off-gasing through either the primary or secondary system.
- 3) Predetemined isotopic mixtures are available for radiofodines, if only gross radiofodine concentration is known. The mixtures may be specified for 1, 4, 24 hour or 4 day decay.
- 4) Predetemined isotopic mixtures are available for radiciodines with 1, 4, 24 hour or 4 day decay based on a known concentration of I-131 (such as the results of a single channel analyzer set up to measure I-131).
INSTRUCTIONS FOR USE t l NOTE: The program is intended to be used after the Off-Site Dose Program l has been loaded and run. To load this program without losing impor-tant data, process for loading this program and subsequent reloading of the Off-Site Dose Program must be carefully followed.
- 1) With zero showing on the calculator display, load side one of the first card. Read "1".
- 2) Initialize the program by pressing A. When "2" flashes, load side two of the first card. When "3" flashes, read in the third side, found on the second card. Read "0" (the fourth side is not loaded or used).
- 3) Enter the isotope (or mixture) number fran Attachment 1. x.-it to store i n " t" .
l 4) Enter the concentration of that isotope (or mixture) in uCi/cc. R/S (
- 5) Read the concentrations of the last isotope entered. Repeat steps 3 and l 4 until all isotopes (or mixtures) that you wish analyzed have been l
added. I
- 6) When all isotopes (or mixtures) you wish to analyze have been entered, O ar'" c-Page 1 of 2 Revision 1
. . PMP 2081.EPP.014 EXHIBIT H h 7) Read 2.16 (the maximum release flow fran Containment when it is isolated successfully) . Enter the flow rate in CFM. R/S l 8) Read total (Nobel Gas plus Iodine) release rate. Iodine release rate is stored in "t". R/S
- 9) Read the effective energy of that conbination. The thyroid dose rate factor is in "t". Use x*t to observe the value of the thyroid dose factor. These numbers have already been stored for use by the Off-Site Dose Progran.
- 10) 'If you wish to enter isotopes or mixtures, press B and go to step 3.
- 11) If you wish to start over entering isotopes and concentrations, press E' and start over at step 3..
- 12) To re-enter the Off-Site Dose Progran without losing the data stored, press D. When "3" flashes, read in the third side of the Off-Site Dose Program cards (found on the second card). When "2" flashes, read in the side two of the Off-Site Dose Progran. Read "1". Enter the side one of the Off-Site Dose Progran cards. Re ad " 1 " .
- 13) When the Off-Site Dose Program has been reloaded, press A. This brings the user back to step 7 in the Off-Site Dose Progran. The dose rates to whole body and thyroid at the site boundary will be present in the x*t registers.
- 14) If other release rates of the same mixture are desired, entering "7" in step 6 of the Off-Site Dose Program will proceed directly to step 7, using the effective energy and thyroid dose factors calculated by this progran without asking for then again. If any other number than "7" is entered in step 6, the factors will be lost.
i O Page 2 of 2 Revision 1
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- PMP 2081.EPP.014 ATTACHMENT #1 ISOTOPIC MIXTURE PROGRAM g ATTACitiENT I NlNBER ISOTOPE (Mixture) 1 Ar-39 2 Ar-41 3 Kr-83M 4 Kr-85M S Kr-85 6 Kr-87 7 Kr-88 8 Xe-131M 9 Xe-133M 10 Xe-133 11 Xe-135M 12 Xe-135 13 Xe-137 14 Xe-138 15 Mixed gases fran Primary Coolant (Case 2) 16 Mixed gases fran fresh fission (Case 1) 17 Mixed gases fran failed fuel (NUREG-0578) (Case 3) 18 Mixed gases fran Primary Coolant thru Secondary (Case 4) 19 Mixed gases fran failed fuel thru Secondary (Case 5) 20 I-129 21 I-130 22 I-131 23 I-132 24 I-133 25 I-134 26 I-135 27 Mixed Iodine at 1 hr. decay 28 Mixed Iodine at 4 hr. decay 29 Mixed Iodine at 24 hr. decay 30 Mixed Iodine at 4 day decay 31 Mixed Icdine at 1 hr. decay, based on I-131 measured 32 Mixed Iodine at 4 hr. decay, based on I-131 measured O 33 Mixed Iodine at 24 hr. decay, based on I-131 measured 34 Mixed Iodine at 4 day decay, based on I-131 measured Page 1 of 1 Revision 1
- s PMP 2081.EPP.014 EXHIBIT I (Readinside1) ,
1 (Init.) V Repartition Calculator v F1 sh (ReadinSide2) . V I SA (ReadinSide3) V Enter isotope number and 3* concentration V (Isotopes) j
~
Readconcentration.Enterisotope) ! number and concentration } I IC8IC*I l Establish "1" as
! concentration g,'
- V l jg 2.16(Enterreleaserate) !
V l
! Refst concentration, energy (Readtotal(iodine)releaserate) thyroid dose factor sumations to zero y ^
Read effective energy (thyroid dose factor) (Clear) j . .--...._ ..- ....... -. y , h(Restore) Store data for use by off. site dose program Repartition calculator Flash ( Read in side 3 of off-site dose program ) 1 F1 sh ( Read in side 2 of off. site dose program ) l v
- 1. ( Read in side 1 of off-site dose program )
Page 1 of 1 l W,K Revision 1 (off. site dose program) i
PMP 2081.EPP.014 EXHIBIT J Q x/0 DISPERSION FACTORS PROGRAM INTRODUCTION: This program will take any base distance and any five other distances and give values for dose or dose rate to the whole body and adult thyroid at those distances. It is especially useful for estimating dose or dose rates based on field measurenents taken by survey teams at various off-site locations. The program detennines a x/Q dispersion factor based on the Pasquill category as detennined by current meteorological conditions. The model assumes an infinite cloud. Measurenents taken on the center line of the plume will, therefore, yield considerably more accurate results than those taken fran lateral points on the plume traverse. However, a feature for extrapolating doses or dose rates at lateral points in the plume is part of the program, and can be called upon for any specified lateral distance. The doses or dose rates obtained using this program are good for whole body, and quite accurate for iodine. INSTRUCTIONS FOR USE (Hand Calculator Prograni): -
- 1) Load s' ides 1 through 3 of the x/Q dispersion factor program cards.
- 2) Enter the program by specifying the appropriate Pasquill category, as follows :
PASOUILL CATEGORY USER-DEFINED KEY A A' B B' C C' D D' E E' F E G D
- 3) Read 610. Enter base distance (to point where measurenents were ob-tained). Units may be in either miles or meters; the program is able to discern between the two. R/S l 4) Read x/Q dispersion factor value for that distance. R/S
- 5) Read 1. Specify a distance at which a value for dose or dose rates is desired . This distance may be less than or greater than the base dis-tance; units may be miles or meters. R/S
- 6) Repeat step 5 for distance cue numbers 2, 3, 4 and 5. If less than 5 other distance values are needed (besides base), entering 0 will abort Q the renaining distance cells and the program will work only on this trun-cated data through the rest of its current cycle. R/S Page 1 of 2 Revision 1
PMP 2081.EPP.014 EXHIBIT J
- 7) Read base distance. Enter measured dose rates in X$ t register (whole body in X register; thyroid in t register). Be sure whole body values 0, '. are in X register before proceeding. R/S - - - - -
- 8) First specified dist'.nce will flash. Read whole body dose (or dose rate) in X register, thyrrid dose (or dose rate) in t register. Be sure whole body value is retur ted to X register before proceeding. R/S
- 9) Repeat step 8 for the remaining distances specified in steps 5 and 6.
Af ter the doses (or dose rates) for the final specified distance have been obtained, several options are possible: a) To go back to step 3 for re-initiation of the progran, press A. b) To get doses, or dose rates, different points of interest, using the sane base distance as reference point, press B and return to step L. c) To obtain doses at lateral points in the plume, press C during a dose reading display. 100 will flash, and the dose at 100 meters lateral to plume center udll be calculated. If a distance other than 100m is desired, it must be given in meters. If R/S is pressed, program will continue fran same place it was left. O l r I l t i (j) Page 2 of 2 Revision 1
PMP 2081.EPP.014 EXHIBIT K O y/0 DISPERSION FACTORS PROGRAM FLOWSHEET hhhhh (Specify Pasquill Category) s/ se s/ S/ s/ s/s/ 61 0. Basedistance(wheremeasurements)f were obtained), miles or meters v (Readx/Qatthatdistance) V Flash 1; 2; Specify five distances *, ,,,,,,,,,,,,, 3; 4; 5 miles or meters Read initial distance; flash Put doses or dose rates in X5t ------ distances 1; 2; registers at distances specified ---- 100. 3; 4; 5 Press A to return to first step
*If a distance will not be used, put a zero in the register; this will cause Q further distance requests to be aborted.
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s REC 0iMtilDED PROTECTIVE ACTIONS FOR POPULATION AND WORKERS - i if ' Projected Dose (Ren) Reconmended Action (s)(a) ! i Comments To the Population ~ Whole Body Less than 1.0 No planned protective action (b) . State Previously reconmended may issue an advisory to seek shel ter and protective actions may Thyroid Less than 5.0 wait further instructions. Monitor be reconsidered or envircnnental radlation levels. tenninated . Whole Body 1.0 to less than 5.0 Seek shel ter as a minimum. Consider If constraints, exist, evacuation. Evacuate unless cnnstreints special consideration Thyroid 5.0 to less than 25.0 make it impractical . Monitor environmental should be given for j radiation levels. Control access. evaculation of children '
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- PMP 2081.EPP.014 EXHIBIT V DISTANCE FR04 PLANT IN FEET KM DESCRIPTION OF LOCATION LETTER MI 2,000 .61 Rosenary Beach House A .38 ~
2,450 .75 Entrance Gate to Rosenary Beach House B .46 3,500 1.1 Entrance Gate to Rosenary Beach Area C .66 D 1.13 6,000 1.82 Intersection of Willow Road and Thornton Road 1.08 5,700 1,74 Houses on Thornton Road E F 1.02 5,375 1.64 I-94 Guard House 6,200 1.89 Red Arrow Highway at Entrance to D. C. Cook G 1.17 Plant H .98 5,150 1.57 Under 345KV Lines on Thornton Road 5,900 1.80 Near 345KV Lines at Red Arrow Highway I 1.12
.88 4,650 1.42 Back Gate at Thornton Road J
.87 4,600 1.40 Under 745KV Lines on Thornton Road K
O L .98 5,200 1.59 Near 745KV Lines at Red Arrow Highway 4,250 1.30 Intersection of Livingston and Thornton Roads M .80 3,250 .99 Entrance Road to OS Station #5 at Livingston N .62 Road 2,200 .67 Road fran OS Station #5 at Livingston Road l 0 .42 2,250 .69 Livingston Road at Beach P .43 l !O l Page 1 of 1 f Revision 1 i L
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O 8 INDIANA & MICHIGAN ELECTRIC COMPANY g DONALD C COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure No. PMP 2080 EPP.001 Revision No. 3 TITLE EMERGENCY PLAN ACTIVATION AND CONDITION CLASSIFICATION , i l SCOPE OF REVISION Rev.1 - Complete Revision to clarify Operations responsibilities: ... . I in case of emergency. Rev. 2 - Incorporated Temporary Sheets. Clarified Emergency Condition categories and activation of emergency centers. Rev. 3 - Incorporated Temporary Sheets 1 and 2. Incorporated g., changes made to ESS's in Emergency Plan section 12.3.5.5.1, revision 1. SIGNATURES ORIGINAL Rev.1 REV.2 Rev.3 D$ pr R. Roone
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R- Annnr MA C e QUALITY ASSURANCE. EWEW INTERFACING DEPARTMENT J. Stietzel J. Stiet7pl J. Stiet7al FM U N/A N/A N/A V 2 M DEPARTMENT HEAD Q N/A N/A N/A #/A PLANT NUCLEAR . A COMME R. Keith B. Svensson E. Townlev PLANT MANAGER B. Svensson D. Shaller W. Smith /[I/ t.t N[k - 0 I 03-31-81 10-27-81 04-27-82 Form No. PMI:0101. nav. 2
PMP 2080 EPP.001 LIST OF EFFECTIVE PAGES O Page Number Revision Number And Date Page 1 of 31 Revision 3, Oct.12, 1982 Page 2 of 31 Revision 3, Oct.12, 1982 Page 3 of 31 Revision 3, Oct.12, 1982 Page 4 of 31 Revision 3, Oct.12, 1982 Page 5 of 31 EXHIBIT A Revision 3, Oct.12, 1982 Page 6 of 31 EXHIBIT A Revision 3, Oct.12, 1982 Page 7 of 31 EXHIBIT A Revision 3, Oct.12,1982 Page 8 of 31 EXHIBIT A Revision 3, Oct.12,1982 Page 9 of 31 EXHIBIT A Revision 3, Oct.12,1982 - Page 10 of 31 EXHIBIT A Revision 3, Oct.12,1982 Page 11 of 31 EXHIBIT A Revision 3, Oct.12,1982 ~ Page 12 of 31 EXHIBIT A Revision 3, Oct'.12, 1982': . E Page 13 of 31 EXHIBIT A Revision 3, Oct.12,1982 _ . m. :.. Page 14 of 31 EXHIBIT A Revision 3, Oct.12, 1982 i Page 15 of 31 EXHIBIT A Revision 3,- Oct.12, -1982 - o - l Page 16 of 31 EXHIBIT A Revision 3, Oct.12, '19821: . X-l Page 17 of 31 EXHIBIT A Revision 3, Oct.12, 1982 - l Page 13 of 31 EXHIBIT A Revision 3, Oct.12, 1982 Page 19 of 31 EXHIBIT A Revision 3, Oct.12, 1982
- Page 20 of 31 EXHIBIT A Revision 3, Oct.12, 1982 l Page 21 of 31 EXHIBIT A Revision 3, Oct.12, 1982 l Page 22 of 31 EXHIBIT A Revision 3, Oct.12, 1982 l g Page 23 of 31 EXHIBIT A Revision 3, Oct.12, 1982 W Page 24 of 31 EXHIBIT A Revision 3, Oct.12, 1982 l Page 25 of 31 EXHIBIT A Revision 3, Oct.12, 1982 Page 26 of 31 EXHIBIT A Revision 3, Page 27 of 31 EXHIBIT A Revision 3, Oct.12,1982 Oct.12, 1982 Page 28 of 31 EXHIBIT A Revision 3, Oct.12, 1982~ ~..
Page 29 of 31 EXHIBIT A Revision 3, Oct.12, 1982 l Page 30 of 31 EXHIBIT A Revision 3, Oct.12, 1982 Page 31 of 31 EXHIBIT A Revision 3, Oct.12, 1982 Page 1 of 1 Rev. 3 l l L___________-------- - - - -- - - - ---______ -_________ _ _________ _ _ _________________ _
o + PMP 2080 EPP.001 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT EMERGENCY PLAN ACTIVATION AND CONDITION CLASSIFICATION 1.0 OBJECTIVES The objectives of this procedure are to ensure that proper actions are taken to place the plant in a safe condition; minimize the hazard to the public and plant personnel; assist injured personnel; and obtain adequate support to cope with the emergency. 2.0 RESPONSIBILITIES . 2.1 The Shift Supervisor is responsible. for initiation of this. pro . _ .. cedure. 2.2 The Shift Supervisor shall act as the- On-Site Emergency-Coordi------ nator (OSEC) until relieved of this responsibility.as described- - in PF" 2080 EPP.015, Responsibilities of tne On-Site Emergency- ~ Coordinator. 2.3 The Shift Technical Advisor (STA) is responsible for re-viewing and making an independent diagnosis of plant con-ditions. The STA then determines whether operator re-() sponses are correct and advises the SS/OSEC accordingly. 3.0 APPLICABILITY This procedure is to be initiated any time the S.S. recognizes the existence of, or potential for, off-normal conditions which may di-rectly lead to, meet, or exceed the Emergency Action Levels shown in Exhibit A. 4.0 INSTRUCTIONS 4.1 Implement Abnormal and/or Emergency Operating Procedures as dictated by plant conditions or indications. 4.2 In the event of: 4.2.1 Radiological Hazard requiring personnel to evacuate their work areas: 4.2.1.1 Evacuate personnel by PA if the condition is local, or 4.2.1.2 Evacuate by use of the Nuclear Emergency (hh Alarm, if the condition includes signifi-cant portions of the plant, and initiate PMP 2081 EPP.005 Personnel Evacuation Page 1 of 31 Rev. 3
e PHP 2080 EPP.001 e 4.2.2 Fire or Explosion: Sound the fire alarm and an-nounce the condition over the P.A. Implement (}} PMP 2080 EPP.009, Fire Emergency Guidelines. 4.2.3 Personnel Injury: Implement PMP 2080 EPP.014, Personnel Injury. 4.2.4 Toxic Gas Release: Implement PMP 2080 EPP.010, Toxic Gas Release. 4.2.5 Gaseous Release: Determine any off-site dose effects as per PMP-2080 EPP.006. Initial Dose Assessments (Gaseous). 4.2.6 Liquid Release: Notify the Chemical Lab to im-plement PMP 2080 EPP.007,' Initial Relea'se'As-sessments (Liquid). . 4.2.7 Natural Emergency: Implement PMP 2080 EPP.011, Natural Emergency Guidelines. - 4.3 Classify the Emergency Condition, using Exhibit A, according to the highest classification (Unusual Event, Alert, Site Emergency or General Emergency) the condition exceeds. 4.3.1 In the event of an Alert: g}) 4.3.1.1 Activation (via Step 4.4 below) of the Technical Support Center and Operations Staging Area is required. 4.3.2 In the event of a Site Emergency: l 1 4.3.2.1 Sound the Nuclear Emergency Alarm-(NEA) - 4.3.2.2 Follow the NEA with a P.A. announcement indicating whether or not personnel are to evacuate. 4.3.2.3 Activate (via Step 4.4 below) the Technical Support Center, Operations Staging Area, Joint l Public Information Center and Emergency Operations ! facility. ! 4.3.3 In the event of a General Emergency: ! 4.3.3.1 Sound the Nuclear Emergency Alarm (NEA) 4.3.3.2 Follow with a P.A. announcement indicating wether or not personnel are to evacuate. i l l l Page 2 of 31 Rev. 3
o 4 e PHP 2080 EPP.001 4.3.3.3 Recommend the Berrien County Sheriff's Department and Michigan State Police consider (}) the following protective actions, as a minimum: 4.3.3.3.1 Activation of the Siren Warning System 4.3.3.3.2 Sheltering within a two-mile radius a and five miles downwind 4.3.3.3.3 Placing cows within ten miles on stored feed, if appropriate 4.3.3.4 Activation (via Step 4.4 below) of the Technical Support Center, Operations Staging Area, Joint Public Information Center and Emergency Operations facility is required. NOTE See PMP 2080.EPP.015, Exhibit A, Responsibility of the On-Site Emergency Coordinator for a listing of on-site and off-site -- actions for each emergency condition. 4.4 Implement PMP 2080 EPP.003, Calling Off-Duty Plant Personnel. 4.5 Implement PMP 2080 EPP.012, Initial Off-Site Notifications if the Plant Manager or Operations Superintendent cannot be reached promptly. O 4.6 Notify the NRC via red telephone within 1 bour. Be prepared to provide one person full time to communicate information over this phone to the NRC if so requested. 4.7 Be prepared to provide updates or additicnal information to the Michigan Department of Public Health if so requested. 4.8 Start trend blocks 12 through 16 on the Prodac. Start the TSC printers. 4.9 Upon arrival of support personnel: 4.9.1 Activate the Technical Support Center Operation as l per PMP 2081 EPP.020 by designating an interim TSC Manager. 4.9.2 The SS shall continue to act as'the On-Site Emer-gency Coordinator until appropriately relieved as per PMP 2080 EPP.015, Responsibilities of the On-Site Emergency Coordinator. l 4.10 Continue to monitor plant conditions: 4.10.1 Ensure notification of the Berrien County Sheriff's Department, Michigan State Police, and NRC if emer-({} gency classification changes. Page 3 of 31 Rev. 3 -wa . .. . m . a m s A ,-.w . .w n , -. . - .- - . ~ L
s ., , i PHP 2080 EPP.001 4.10.2 If significant state, local, and federal sources have been activated, attempt to obtain concurrence between h all parties prior to de-escalation and entry into the recovery phase of operations. 4.11 Terminate use of this procedure when plant conditions are safe and/or within normal operating parameters. O O Nge 4 i 31 Res. 3
PMP 2080 EPP.001 EXHIBIT A EMERGENCY CONDITION CATEGORIES i ECC-1 Aircraft Crash or Missilus from any source ECC-2 Control Room Evacuation ECC-3 Earthquake ECC-4 Explosion ECC-5 Fire ECC-6 Seiche ECC-7 Security Threat or Compromise ECC-8 Tornado or Severe Winds ECC-9 Toxic Gas ECC-10 Loss of AC Power ECC-11 Loss of DC Power ECC-12 Loss of Plant Shutdown Functions () ECC-13 Other Conditions or Systems required by Tech. Specs. ECC-14 Fission Product) and Loss of Coolant Accident Barriers ) ECC-15 Fuel Damage ECC-16 Loss of Secondary Coolant ECC-17 Steam Generator Tube Rupture ECC-18 Fuel Handling Accident ECC-19 Radiation Releases l ECC-20 Personnel Injury ECC-21 Other Hazards ECC-22 Loss of Control Room Annunciators / Alarm i ! ECC-23 Liquid Release O i l Page 5 of 31 Rev. 3
o PMP 2080 EPP.001 EXHIBIT A ECC-1: AIRCRAFT CRASH OR MISSII.ES FROM ANY SOURCE Unusual Event
- 1. Aircraft crash on-site.
- 2. Unusual aircraft activity by SS's judgment.
Alert
- 1. Aircraft crash in the protected area or switchgear 345KV, 765KV or Emergency po-wer yards.
- 2. Missiles from any source landing in the protected area.
Site Emergency
- 1. Aircraft crash which, in the judgment of the SS, affects the Aux. Building or Containment.
- 2. Missile damage which, in the judgment of the SS, (h) causes damage to safe shutdown equipment such that it cannot fulfill its safety function.
General Emergency N/A Page 6 of 31 Rev. 3
'. PMP 2080 EPP.001
. EXHIBIT A ECC-2: CONTROL ROOM EVACUATION _
Unusual Event N/A Alert
- 1. Evacuation of Control Room is anticipated.
- 2. Evacuation of Control Room is required with control of unit shutdown systems at local station established within 15 minutes.
Site Emergency
- 1. The Control Room is evacuated and control of all the following systems or equipment is not esta-blished within 15 minutes:
- a. Auxiliary Feedwater and O b. Boric Acid Transfer Pumps and
- c. Pressurizer Heaters and
- d. Atmospheric Steam Dump Valves and
- e. Charging Pumps and
- f. Charging Flow Control Valve and
- g. Letdown Isolation Valves.
General Emergency N/A t b Page 7 of 31 Rev. 3
> 0 PMP 2080 EPP.001 EXHIBIT A ECC-3: EARTHQUAKE k) Unusual Event
- 1. Any actuation of seismic instrumentation that is verified to be the result of an earthquake.
Alert
- 1. Earthquake that is readily felt but does not cause observable damage to the plant or sur-rounding structures.
Site Emergency
- 1. Earthquake that is of sufficient magnitude to cause significant damage to the plant or sur-rounding structures. It may cause an auto-matic trip of the reactor and/or turbine due to equipment or instrumentation malfunctions.
General Emergency N/A (2) Page 8 of 31 Rev. 3
PMP 2080 EPP.001
. EXHIBIT A ECC-4: EXPLOSION O Unusual Event
- 1. Any explosion Near or On Site Alert
- 1. Explosion damage to the plant affecting unit operation or offsite power supplies.
Site Emergency
- 1. Explosion damage which, in the judgment a -
of the SS, causes damage to safe shut-down equipment such that it cannot ful-fill its safety function. General Emergency N/A O (5) Page 9 of 31 Rev. 3
- 4 P!fP 2080 EPP.001 EXHIBIT A ECC-5: FIRE h Unusual Event
- 1. Any significant fire lasting more than 10 minutes on plant site (protected area) or switchgear yards.
Alert
- 1. Fire potentially affecting safety systems cs judged by the SS.
Site Emergency
- 1. Fire affecting any safety system as judged by the SS.
O General Emergency N/A l
- O Page 10 of 31 Rev. 3 L _ . _ _ _ _ _ _ - - -
- . - 4 PMP 2080 EPP.001 EXHIBIT A I ECC-6
- SEICHE O Unusual Event
- 1. Lake level deviation, from operating levels (on screen house water level monitor) by more than 5 ft, up or down but less than 8 ft. up or down.
Aiert
- 1. Screen house level indication shows.a deviation between 8 ft. and 11 ft.
Site Emergency
- 1. Screen house level indication showsza deviation greater than 11 ft.
General Emergency O N/A O Page 11 of 31 Rev. 3
4 .a PMP 2080 EPP.001 EXHIBIT A ECC-7: SECURITY THREAT OR COMPROMISE O Unusual Event
- 1. Security threat, attempted entry, or attempted sabotage in the judgment of the SS and/or shif t security supervisor.
Alert -
- 1. Ongoing security compromise in the judgment of the SS and/or shift security supervisor.
Site Emergency
- 1. Loss of physical control of the facility'is likely in the judgment of the SS based on the advice of -
the shift security supervisor. (h) General Emergency
- 1. Loss of physical control of the facility as deter-mined by the S.S. based on advice from the shift se-curity supervisor.
t l ( Page 12 of 31 Rev. 3
a s PMP 2080 EPP.001
. . E:3IBIT A ECC-8: TORNADO OR SEVERE WINDS Unusual Event
- 1. Any tornado near or on site.
Alert
- 1. Tornado damage to the plant affecting unit operation or offsite power supplies.
- 2. Sustained winds in excess of 85 mph.
Site Emergency
- 1. Sustained winds in excess of 100 mph.
General Emergency h N/A O Page 13 of 31 Rev. 3
I
* -s l
l PMP 2080 EPP.'J)1 l , EXHIBIT A ECC-9: TOXIC GAS O Unusual Event
- 1. Near or on-site toxic or flammable gas re-lease.
Alert 2
- 1. Entry into the protected area of lethal or concentrated volumes of toxic or flammable gas.
Site Emergency
- 1. Entry into vital areas of lethal or con-centrated volumes of toxic or flammable gas which in the judgment of the SS af-fects operation of the safe shutdown equip-ment.
O General Emergency N/A O l l Page 14 of 31 l Rev. 3 i _.
i
- o. a f
PHP 2080 EPP.001 EXHIBIT A ECC-10: LOSS OF AC POWER Unusual Event
- 1. Loss of all off-site AC power capabilities, including 69KV emergency power, such that the T-11 A, B, C, D buses for U-1 (or T-21 A, B, C, D buses for U-2) cannot be energized from these sources og all on-site AC power capabilities (both diesel generators for one unit are unavailable or inoperable due to mechanical, electrical, or error effects) is lost, this includes the main generator.
Alert
- 1. Loss of all off-site power supplies with a) rapid increase of primary to secondary tube leakage to several gpm, and b) off-i scale readings on R-15 (SJAE Monitor), and c) large increase on Steam Generator Blow-down Monitor R-19, and d) confirmation of high radiation levels.
([) 2. Loss of off-site powar and loss of on-site AC power capacity as indicated by failure of Emergency Diesel Generators to start, and load ampmeters for buses IA, IB, IC, ID for Unit 1 and buses 2A, 2B, 2C, 2D for Unit 2 are at zero. Site Emergency
- 1. Loss of off-site power is indicated by all ampmeters for the 4160 buses reading 0 amps; and Steam Generator tute rupture indicated by readi.ngs on the Condenser Air gjector Moni-tor (R-15) greater than 1 X 10 cpm and~
these readings have been confirmed; and SI initiated by the Engineered Safety Fea-ture Actuation System
- 2. Ampmeters for 4160V buses all read 0 amps, and Voltmeters for 4160 V buses read 0 volts, and Above conditions last for more than 15 minutes.
O General Emergency N/A Page 15 of 31 Rev. 3 I
-- . ._-_ _.n w- -
t
PHP 2080 EPP.001 EXHIBIT A ECC-11: LOSS OF DC POWER (A & B TRAIN BATTERIES) Unusual Event N/A Alert -
- 1. All battery voltmeters read zero, and board indicating lights are off.
Site Emergency
- 1. All battery voltmeters indicate-0 volts and no indication of availability of backup DC voltage, and the condition lasts for more than 15 minutes.
O General Emergency N/A s O Page 16 of 31 Rev. 3 L_--__--____----------------------..------.--- _ _ _ . - - - - _ . - . - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
l
- o. a 1 PMP 2080 EPP.001
. . EXHIBIT A ECC-12: LOSS OF PLANT SHUTDOWN FUNCTIONS Unusual Event .
- 1. Plant shutdown as required by Technical Specification for loss of essential assess-ment or communication capabilities, such as:
- a. Reactor trip instrumentation
- b. Engineered Safety Feature Actuation Instrumentation
- c. Radiation Monitoring Channels
- d. Post Accident Monitoring Channels
- e. Essential communication to off-site authorities including back-up capability.
Alert
- 1. Loss of all Residual Heat Removal (RHR) pumps, heat exchangers and/or controls, with los's of all auxi-11ary feedwater capacity needed.
O Site Emergency
- 1. Loss of all the following systems, equipment or controls:
- a. Auxiliary Feedwater System
- b. Boric Acid Transfer Pumps
- c. Pressurizer Heaters
- d. Atmospheric Steam Dump Valve
- e. Charging Pumps
- f. Letdown Isolation Valves or Letdown Flow Control General Emergency N/A O
Page 17 of 31 Rev. 3
- s. e PMP 2080 EPP.001 EXHIBIT A ECC-13: OTHER CONDITIONS OR SYSTEMS REQUIRED BY TECHNICAL SPECIFICATIONS Unusual Event i
- 1. ECCS initiation by valid signal as listed in Technical Specifications Tables 3.3-3 and 3.3-4.
- 2. Environmental Technical Specification 2.1.1 (liquid waste effluent limits) or 2.1.3 (gaseous effluent limits) possibly have been exceeded with verification by Radiation Protection analysis, as indicated by readings on any of:
- a. Condenser air ejector monitor (R-15) 0 exceeds 1 X 10 cpm
- b. WDS liquid effluent monitor (R-18) exceeds 1 X 10' cpm
- c. Blowdown Liquid Monitor (R-19) exceeds 1 X 10 cpm
- d. ESW monitors (R-20 and R-28) exceed 300 epa
- e. Blowdown treatment monitor (R-24) exceeds 7 X 10' cpm
- f. Unit vent air particulate (R-25) exceeds 1.3 X 10' epm
- g. Unit vent gas monitor (R-26) exceeds:
1 X 10 cpm (fresh gas) or 1 X 10 cpm (old gas) O Page 18 of 31 Rev. 3
A a PMP 2080 EPP.001 EXHIBIT A ECC-13: OTHER CONDITIONS OR SYSTEMS REQUIRED BY TECHNICAL SPECIFICATIONS (CONT'D) Use the "old gas" criterion for:
- 1. Release originating from a gas decay tank shown by unexplained GDT pressure decrease seen on recorders MR058 or MR059.
- 2. Release originating from a CVCS holdup tank, shown by unexplained CVCS holdup tank header pressure de-crease (QPA 600) and pos-sibly excessive cover gas demand.
Use " fresh gas" condition for:
- 1. Releases from sources other than those listed above.
- h. Unit vent radio-iodine (R-32) 3 exceeds 2 X 10 cp ,
NOTE Before applying this criterion, ensure the " window" selector is set to .4, and the " input mode" (iodine) selector is set to N.
- 3. Abnormal coolant temperature, pressure, and/or abnormal fuel temperatures exceeding Technical Specification 2.1.1 or 2.1.2 safety limits exceeded and exceeding Limiting Safety Systems Os Settings listed in Technical Specification 2.2.1, without a unit trip, with the excursion confirmed.
Page 19 of 31 Rev. 3
- e PHP 2080 EPP.001
. . EXHIBIT A ECC-13 OTHER CONDITIONS OR SYSTEMS REQUIRED BY TECHNICAL SEECIFICATIONS (CONT'D)
O 4. Containment integrity Technical Specifications exceeded with a unit shutdown required by the associated Technical Specification.
- 5. Engineered Safety Features or Fire Protection System causing unit shutdown due to associated action statement in the applicable Technical Specification caused by malfunction, procedural error, or personnel error.
- 6. Reactor Coolant ".eakage exceeds Tech. Spec. 3.4.6.2 and the Unit is shut down for this reason.
Alert
- 1. Radiation monitoring channels exceed indicated levels with confirmational analysis-by radiation-protection.
- a. R-1 (Control Room Area Monitor) exceeds 10mR/hr.
- b. R-3 (Radiochemistry Lab) exceeds 100 mR/hr.
- c. R-4 (Charging Pump Room) exceeds 1 R/hr.
( d. R-5 (Spent Fuel Area) exceeds 100 mR/hr.
- e. R-6 (Nuclear Sampling Room) exceeds 1 R/hr.
- f. R-26 (Unit Vent Gas Monitor) exceeds 10 cpm.
l
- 2. Failure of the reactor trip' logic to provide a reactor trip when a signal is received for a setpoint as listed in Technical Specification Table 2.2-1, with rod indication showing no trip has occurred and manual trip l ciscuitry fails to provide a trip.
- 3. Analysis of effluent samples confirms that instantaneous limits stated in Environmental Technical Specification 2.1.1 and 2.1.3 have been exceeded by a factor of 10.
l l Site Emergency l N/A General Emergency N/A Page 20 of 31 Rev. 3
/
PMP 2080 EPP.001 EXHIBIT A ECC-14: FISSION PRODUCT BARRIERS / LOSS OF COOLANT Unusual Event
- 1. Technical Specification Limits 3.4.6.2a, b, c, & d are exceeded and the unit is shut <*cwn for these rea-sons.
- 2. Presserizer safety valves or power operated relief valves stay open as indicated by temperature in the line and by the acoustic monitor.
Alert
- 1. Rapid increase of primary to secondary leakage to.
several gpm with off-scale readings on steam jet air - ejector montitor (R-15) and large incre-fse on steam generator blowdown monitor R-19 with confirmation of high radiation levels and with loss- of off-site. power, - ru,
- 2. Large primary to secondary leak rate likely as indicated by an increase to maximum of charging flow and off-scale ~
radiation readings on R-15 cad R-19 confirmqd.
- 3. Steam line break as indicated by a Safety Injection (SI)
O for Technical Specification listed in Table 3.3-4 with primary to secondary leak rate in excess of 10 gpa as ~ calculated by the most recent leak rate.
- 4. Primary Coolant leak rate is tco high for one charging pump to maintain level in pressurizer above 22% (leak
- rate is greater than 50 gpm over that total allowed in Technical Specification 3.4.6.2), or a second charging pump has to't.e started to maintain pressurizer level above 22%.
Site Emergency
- l. Safety Injection (SI) initiation followed by c.,ntain-ment spray (and Phase B) initiation due to high (2.9 psig) containment pressure, with increasing contain-ment sump levels and increasing radiation levels M containment.
General Emergency
- 1. Loss of 2 out of 3 fission product barriers with a potential loss of the third barrier.
- a. Confirmed loss of core geometry, and O b. Confirmed loss of Reactor Coolant System integrity,
.and ,
- c. High potential for loss of Containment ictegrity^
Page 21 of 31 s-Rev. 3 u
> d PMP 2080 EPP.001 EXHIBIT A ECC-15: FUEL DAMAGE Unusual Event
- 1. Unit is shutdown as required by Tech. Spec. 3.4.8.
- 2. An increase in failed fuel detector gross gamma readings to off-scale and by chemical laboratory aaulysis indicating an increase of greater than
.1% failed fuel within 30 minutes.
Alert
- 1. Very high coolant activity (exceeds 300 pCi/cc dose equivalent Iodine).
- 2. A sudden increase in possible failed fuel as indicated by a rapid gross gamma reading in-crease on failed fuel monitor and rapid increase '
on Charging Pump Room Area Monitor radiation
~
levels.
,-3. Loss of flr e or more reactor coolant loops
.iuitiates _ecor trip (manual below 50% power) followed by specific activity of the primary cool-(h) ant increasing to greater than 300 pCi/cc equiva-lent of I-131.
Site Emergency
- 1. Core saturation surve or core subcooling monitor indicates subcooling of 0*F or less and this reading is ccafirmed.
General EE.ergency N/A s l % n. 1 CE) Page 22 of 31 Rev. 3
PMP 2080 EPP.001 EXHIBIT A ECC-16: STEAM LINE BREAK Unusual Event 1. Steam generator safety valves, or power operated relief valves stay open with significant gpm primary to second-ary leakage existing as indicated by off-scale readings on condenser air ejector and gland steam seal radiogas monitors. Alert 1. Steam line break as indicated by a safety injection with primary to secondary leak rate in excess of 10 gpm as per latest calculated rate.
- 2. Steam line break with failure of steam lity isolation valve to close as indicated by continued high steam line flow on the flow meters.
Site Emergency 1. Steam line break as indicated by any of following SI conditions: High steam line flow coincident with () steam line pressure or coincident with Low Low Tavg, (for U-1, for U-2 is low steam line pressure) or high differential pressure between steam generators (both units), or low pressurizer press (both units) as per Technical Specification Table 3.3-4 setpoints, and
- 2. Calculated primary to secondary leak of 50 gpm, and
- 3. Fuel damage as indicated by Reactor Coolant dose equivalent I-131 greater than 300 pc/g.
General Emergency N/A O Page 23 of 31 Rev. 3
lY' PHP 2080 EPP.001 EXHIBIT A ECC-17: STEAM GENERATOR TUBE RUPTURE O Unusual Event
- 1. Tech. Spec. 3.4.6.2.c exceeded.
Alert
- 1. Primary to secondary leak rate in excess of 10 gpm as per latest calculated rate with steam line break as indicated by a Safety Injection (SI) for Technical Specification listed in Table 3.3-4.
- 2. Rapid increase of primary to secondary leakage to several gpm with off-scale readings on Steam Jet Air Ejector Monitor (R-15) and large increase- on Steam Generator Blowdown Monitot (R-19) and confirmed high radiation levels with loss of off-site power.
- 3. Large primary to secondary leak rate likely as in-dicated by an increase to maximum of charging flow and off-scale radiation readings on R-15 and R-19 confirmed.
Site Emergency O 1. a. Steam generator tube rupture indicated by read-ing on the Steam Jeg Air Ejector Monitor (R-15) greater than 1 X 10 cpm and these readings have been confirmed; and
- b. SI initiated by the Engineered Safety Feature Actuation System; and
- c. Loss of off-site power is indicated by all ampmeters for the 4160 volt buses reading 0 emps.
- 2. a. Calculated primary to secondary leak of 50 gpm; and
- b. Steam line break as indicated by any of the follow-ing SI initiating conditions: High steam line flow coincident with low steam line pressure or coinci-dnet with Low Low Tavg (for U-1, for U-2 is low steam line pressure), or high differential pressure between steam generators (both units) or low pres-surizer pressure (both units) as per Technical Spec-ification Table 3.3-4 setpoints, and
- c. Fuel damage indicated by Reactor Coolant dose equi-valent I-131 greater than 300 pc/g.
(}} General Emergency i N/A Page 24 of 31 Rev. 3
PMP 2080 EPP.001 EXHIBIT A ECC-18 FUEL HANDLING ACCIDENT Unusual Event N/A
\
Alert '
- 1. If an apparent accident occurs and containment area monitor (R-2) shows a reading 100 times previous reading while handling fuel during re-fueling, cy R-5, spent fuel area monitor ex-ceeds 100 times previous reading while moving fuel or objects over spent fuel pit. Analysis confirms fuel failure by detection of fission l
products. Site Emergency
- 1. A heavy object (Technical Specification 3.9.7) impacts spent fuel while the spent fuel is in containment or in the spent fuel pit.
O 2. Water level in the vessel or spent fuel pit drops below the top of the fuel. General Emergency N/A O Page 25 of 31 Rev. 3
- _ _ _ 1
l PMP 2080 EPP.001 EXHIBIT A 1 ECC-19: RADIATION RELEASE Unusual Event See also ECC-13 for classifications of specific RMS monitor readings. Alert See also ECC-13 for classifications of specific RMS monitor readings.
- 1. Measured or projected dose rate of 2 mR/hr whole body at site boundary under existing weather con-ditions.
Site Emergency
- 1. Measured or projected dose rate of 50 mR/hr whole body or 250 mR/hr thyroid at the site boundary under existing weather conditions.
General Emergency
- 1. Measured or projected dose rate of 250 mR/hr whole body or 1250 mR/hr thyroid at the site boundary under existing conditions.
l 0 l l Page 26 of 31 l Rev. 3
PMP 2080 EPP.001 EXHIBIT A ECC-20: PERSONNEL INJURY Unusual Event
- 1. Transportation of contaminated individual (s) to off-site hospital.
- 2. Any fatality, or serious injury occurring on site requiring a stay at a medical facility in excess of 48 hours.
- 3. Any serious personnel radioactive contamination requiring extensive on-site decontamination or outside assistance.
Alert ; N/A Site Emergency N/A General Emergency N/A I,' l I i
, l Page 27 of 31 Rev. 3
.. . . ~ . _ ~ . . .. .- ,
P!iP 2080 EPP.001 EXHIBIT A ECC-21: OTKr.R HAZARDS Unusual Event
- 1. Turbine failure with resulting damage but not penetrating outside turbine housing.
- 2. Rapid uncontrolled depressurization of the secondary side.
- 3. Unit is shut down in an uncontrolled manner or conditions exist which might escalate to a more severe class; such as, uncontrolled rod withdrawal, dropped RCCA assembly or bank, uncontrolled dilu-tion, less of one or more Reactor Coolant Pumps above 50% power, loss of load, loss.of normal feed-water or malfunction (overcooling, excessive load increase), inactive RCS loop startup, steam line break.
Alert
- 1. Other plant conditions exist that warrant pre-cautionary activition of Technical Support Center O and near-site emersencv ePerations center, as Per SS judgment.
- 2. Turbine failure causing damage as judged by the SS penetration outside turbine housing.
Site Emergency
- 1. SS judgment, i.e., a less severe emergency class has escalated to meet S:te Emergency criteria.
General Emergency
- 1. Loss of Coolant Accident (LOCA), (large or small),
with the failure of the Emergency Core Cooling Sys-tem (ECCS) to function leading to severe core degra-dation or melt. With core melt sequences, ultimate containment failure likely with several hours availa-ble for response.
- 2. Transient due to loss of the Feedwater System or Con-densate System followed by the failure of the Auxiliary h Feedwater System for an extended period. Core melting is possible in several hours with ultimate containment failure likely if core melts.
(Cont'd) Page 28 of 31 Rev. 3
PMP 2080 EPP.001 EXHIBIT A ECC-21: OTHER HAZARDS (CONT'D)
- 3. Transient condition requiring operation of Reactor Protection System with a failure to trip the reactor followed by a failure of ECCS and makeup system which would lead to a core melt.
- 4. Failure of offsite and onsite power along with total loss of emergency feedwater capability for several hours which would lead to eventual core melt and likely containment failure.
- 5. Small LOCA with initial ECCS actuation success-ful with subsequent failure of containment heat removal systems. Ultimate core melting is likely with probable containment failure.
O 1 1 (O _/ Page 29 of 31 Rev. 3
PMP 2080 EPP.001 l EXEJBIT A l l l ECC-22: LOSS OF CONTROL ROOM ANNUNCIATORS / ALARMS i 1 O Unusual Event
'i/A Alert l
- l. All annunciator panels in Control Room non-functioning.
- 2. The unit is undergoing a transient while the annunciators are inoperable.
Site Emergency N/A General Emergency 7, N/A L) O
%)
Page 30 of 31 Rev. 3 _ _ __ _ _ .. _m_..__._ __ _ . _ . _ . . ,
PMP 2080 EPP.001 EXHIBIT A ECC-23: LIQUID RELEASE Unusual Event
- 1. Environmental Technical Specification 2.1.1 (liquid waste effluent limits) or 2.1.3 (gaseous effluent limits) exceeded with verification by radiation protection analysis.
Alert
- 1. Radioactive liquid effluent releases which exceed 10 X Technical Specification limits.
Site Emergency
- 1. Radioactive liquid effluent releases which for a single isotope or mixed isotopes exceeds 50 X MPC in water (averaged over 24 hours).
General Emergency
- 1. Radioactive liquid effluent releases which for a single h isotope or mixed isotopes exceeds 500 X MPC in water (averaged over 24 hours).
I O Page 31 of 31 Rev. 3
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