ML20079P576
| ML20079P576 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Prairie Island, 05000000 |
| Issue date: | 12/21/1983 |
| From: | Fey F, Hudson G NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML113190974 | List: |
| References | |
| PROC-831221-01, NUDOCS 8401310271 | |
| Download: ML20079P576 (10) | |
Text
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(3 WCLEAR GENEMATION DEPARTRAENT CORPORATE NUCLEAR EteERGENCy PLAN insPtansENTwoo PROCaouRE NORTHERN STATES POWER COAAPANY g
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December 21, 1983 Adm. Emer9eDcy Rep redness kk h
TABLE OF CONTENTS ReviEwEn av:
RECORD OF REVISION G
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APPROVEDSv:
General MaMgeFNITclear Plants TABLE OF CONTENTS IMPLEMENTING PROCEDURES 1.1.1 CORPORATE EMERGENCY RESPONSE ORGANIZATION REV 4 1.1.2 NOTIFICATIONS REV 7 O
1.1.3 PUBLIC INFORMATION REV 4 k,.)
I,1,4 EMERGENCY ORGANIZATION RECORDS AND FORMS REV 5 1.1.5 STA E.UP AN3 OPERATION OF EOF REV 8 l
1.1.6 EMERGENCY ORGAHlZATION SHIFT TURNOVER REV 3 1.1.7 START-UP AND GPERATION OF HQEC REV 5 1.1.8 C0tWJNICATION ECUIPMENT AND INFORMATIO:i REV 3 1.1.9 EMERGENCY PROCESSING OF PURCHASE ORDERS REV 3 1.1.10 0FFSITE SURVEYS REY 4 1.1.11 ACCIDENT ASSESSMENT REV 6 l
1.1.12 IMPLEMENTATION OF THE RADIOLOGICAL ENVIR0 MENTAL REY 5
. MONITORING PROGRAM (REMP) 1.1.13 EVACUATION OF THE EOF REV 3 1.1.14 VENDOR AND CONSULTANT SERVICES REV 5 1.1.15 TRANSITION TO THE REC 0VERY PHASE REV 4 1.1.16 0FFSITE PERSONNEL AND VEHICLE MONITORING AND DECONTAMINATION REV 1 1.1.17 PERSONNEL MONITORING AT THE EOF REY 2 1.1.18 CONTROL OF RADIOACTIVE MATERIALS AT THE EOF REV 0 l
SUPPLEMENTAL PROCEDURES 1.2.1 EMERGENCY PLAN TRAINING REV 3 1.2.2 EXERCISES AND DRILLS REV 3 1.2.3 MAINTENANCE OF EMERGENCY PLANS AND PROCEDURES REV 3 1.2.4 S'JRVEILLANCES REV 3 Paes 1
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NUCLEAR GENERATION oEPMmsENT CORPORATE NUCLEAR EasERGENCY PLAN monumsENTiNo PRoCEcune NORTHERN STATES POWER coasPANY MuessER. EPIP 1.1.11 nEv: 6 1
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i Adn. Emergenc7 Preparedness N[ hh nEviEwEn sy:
EPIP 1.1.11 ACCIDENT ASSESSMENT Gen Supt Rad P 1stry
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1.0 PURPOSE AND OBJECTIVE 1
The purpose of this procedure is to specify the techniques and methods for data collection and analysis to assess the offsite consecuences of ar, emergency condition. This procedure alsa provides recessnenistion guide-lines for protective actions based o'i tnese assesmants.
1 2.0 CONDITIONS A2 PREREQUISITES, An energency condition has beer. 6eclared involving the potential for, or an actual release of, radioactive material from an NSP nuclear phnt.
I 3.0 CRGANIZATIONANDRESPONFf31LITIES
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3.1 Overall Responsibility - Emergency Manager
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3.2 In Charge - Radiation Protection Support Superv.isor 4.0 DISCUSSION I
4.1 Accident assessment is required to ensure that the consequences of any radiologfeal release art evaluated and that reconsnendatfons for protectfve actions are fomulated and provided to appropriate state officials. This assessment is a continuous process throughout the duration of an energency and should be continued as directed by the Emergency Manager.
' 4.2 The responsibility for accident assessment is initially assigned to Il the TSC. The Radiological Emergency Coordinator will make evaluations based on actual plant data, and calculated or measured doses. He will fomulate protective action reconsnendations for the Emergency Director and the Emergency Director will infom the state officials i
of the recommendations.
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4.3 After the EOF is activated, the Emergency Manager is responsible for g
all comunication with state end local officials. Therefore, all recommendations for protective actions shall be made to the Emergency Manager.
p 4.4 The decision to transfer accident assessment responsibilities from p
the TSC to the EOF is made by the Emergency Manager. This decision will be based on the type of emergency, the EOF equipment status and the staffing of the Radiation Protection Support Group. The plant will provide the EOF with an individual to operate the MIDAS system.-
Wien the Emergency Manager has determined that the EOF has the capability to perform accident assessment and formulate protective action recomendations, he will inform the TSC. He will then direct the Radiation Protection Support Supervisor to assume these respon-sibilities. Tne transfer of responsibilities shall be closely coordinated with the Radiological Emergency Coordinator.
4.5 The Radiation Protectica Support Supervisor will use the projected dose rates and actuai survey results to forTJulate protective actions.
He will inform the Emergency fianager of his recomendations. The Emergency Manager will make the necessary recommendations to state and local officials.
5.0 RESPONSIBI?_ITIES q
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5,1 Emergency Manager 5.1.1 Direct the Radiation Protection Support Supervisor to assume accident. assessment responsibilities. This should be imple-mented when the Radiation Protet.tfon Support Group is fully stafftd and transfer of responsibilities will enh,ance the overall emergency response.
5.1.2 Ensure that the state (s) receive (s) Protective Action Recommendations as required. Guidelines specified in this Figure 1 for transmittal of recommendations to state (s).] [Use procedure should form the basis for any reconenendations.
4 S.1.3 Prior to, or simultaneously with, telecopying a protective action recommandation to the state (s):
I e If at Monticello Initiate a 2-way phone call between the EM and the Minnesota Team Coordinator and explain the basis for the recommended protective action, e If at prairie Island Initiate a 3-way conference call between the EM. 'the Minnesota Team Coordinator and the Wisconsin State Radio-logical Coortlinator and explain the basis for the recom-mended protective action.
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5.2. Radiation Protection Support Supervisor, 5.2.1 Obtain offsite dose projection data, 5.2.2 Obtain and analyze the result of offsite monitoring efforts i
and compare these results with calculated dose projections.
5.2.3 Obtain information regarding the magnitude and nature of potential radioactive releases and analyze.the potential offsite consequences.
5.2.4 Provide the Emergency Manager with offsite dose and dose rate infonnation and reconnendations for offsite protective actions.
dation to the state (s)y to issue'a protective action recommen-5.2.5 If it becomes necessar
, prepare a Protective Action Recommen-dation Checklist, Figure 1 for Emergency Manager approval.
5.2.6 Prepare Emergency Notification Follow-up Nssage as found in Figure 2, of CPIP 1.1.5, " Start-up and Operation of EOF".
Provide courgleted fom t1 the Emergency tianager and transmit infensation to the State EOC.
5.2.7 If there has t: san a release to the envirots, ccnsioer
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increasing the~ normal sampling frequency of the Radiological Envirorsental Ponitoring Program (REMP) after all significant releaus are tamfaated and the plant is in a stable condition.
5.2.3 Cbtain and aralyte tne results of the Padio'.ogical Environmental Monitoring Progran; (REMF) as appropriate.
6.0 PROCEDURE 6.1 Analysis of Dose Pro.iecticas for Actual Airborne Releases 6.1.1 Obtain the following information.
6.1.1.1 Release rates and type of release (ground or elevated).
6.1.1.2 Meteorological data (wind speed, wind direction, and stability class).
6.1.1.3 Survey results from plant survey teams, as applicable.
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NuMeER. EPIP 1.1.11 Rev.
6.1.1.4 Projected,offsite dose calculations using the affected plant procedure for offsite dose calculations; Frairie Island Nuclear Generating Plant procedure F3-13. "Offsite Dose Calculations", or Monticello Nuclear Ger? rating Plant procedure.
A.2-406, 'Offsite Dose Projection".
6.1.2 Record dose projections on area map mferenced in EPIP 1.1.4 (use red marker).
6.1.2.1 This will normally be in the form of 16 sector dose data out to 10 miles.
6.1.2.2 Determine the highest integrated dose region and highest dose rate region..
6.1.3 Determine applicable radiation protection requirements for NSP personnel in affected offsite areas.
6.1.4 Dispatch survey teams to affected offsite regions with due reganf to radiation protection requirements.
6J1.4.1 Teams shculd be deployed to pcpulate:f areas where '.ha niqhest do5e rates are projected.
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6.1.4.2 Direct the offsite monitoring to be perfonred in accordar.ce with Corporate EPIP 1.1.10, Offsite Surveys".
6.1.5 When survey data is available, ploc the data on the area maps referenced in E. IP 1.1.4.
Offsite survey results chould be plotted (in blue marker) logging beta-gamma survey results in millirem /hr ToTTowed by air sample results in uct/cc.
6.1.6 Perfonn a comparison of radiological data as follows:
6.1.6.1 Compare offsite monitoring results for consistency.
Re-monitor areas of concern, as required.
6.1.6.2 Compare offsite monitoring results with dose calcula-tion projections. Re-monitor areas of concern, as
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6.1.6.3 Dose calculation techniques should represent an upper bound to potential offsite dose and dose rates.
Field survey results more accurately indicate inte-grated dose and dose rate in the environs.
6.1.8 Verify that offsite dose projections are consistent with l
offsite survey team results.
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IIIPLERAENTING PROCEDURE NutIEER:EPIP 1.1.11 REY: 6 6.1.9 Detemine any protective action recommendations that are prudent. These reco'mmendations should be made and plotted on Figure 1 using the guidance provided in this procedure.
6.1.10 Provide the Emergency Manager with the current integrated dose and dose rate infomation data for populated areas and other areas of major concern. A summary report should be prepared at periodic intervals as time and infomiation pemit. The sum-mary report should consist of the following:
6.1.10.1 Plot of integrated dose and dose rate infomation on area maps referenced in EPIP 1.1.4 (date, time, color code).
6.1.10.2 Summary of meteorological conditions, past changes in conditions and potential changes germaine to radio-active material transport.
6.1.10.3 Areas of highest integrated dose and dose rate.
6.1.10.4 Population areas of greatest concern.
6.1.10.5 Susanaiy of monitoring and dose calculation effort?, to date.
C 6.1.10.6 Planned monitoring and dose calculations in progress.
6.1.11 Complete the Emergency Mtification Follow-up l'assage for reporting of the event. Use Figure 2. EPIP 1.L.5, " Start-up and Operation of EOF". Provide completed form to the Emergency Manager.
6.1.12 After the release has been teminated, consider retrieval of the " Emergency" TLDs (refer to EPIP 1.1.12 Implementation of Radiological Enviromental Monitoring Program).
6.2.
Analysis of Dose Pro.iection for Potential' Airborne Releases l
6.2.1 If the potential exists for a significant release of radio-active material from the plant, perfom an analysis of potential offsite consequences as follows:
6.2.1.1 Determine the approximate releasable curie content of the containment.
l 6.2.1.2 Determine the most probable release path, i.e. ground release, stack release or building ventilation release.
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wuctaAR annaRAnoes oePARTmeur asPtaasswTwen PRoctouns mussesR: EPIP 1.1.11 Rav: 6 6.2.1.3 Detemine dose projection calculations based on release of'this material under present and various
. meteorological conditions using the affected plant procedure for offsite dose calculations; Prairie Island Nuclear Generating Plant procedure F3-13 "Offsite Dose Calculations", or Monticello Nuclear Generating Plant procedure, A.2,-406, "Offsite Dose Projection".
6.2.1.4 Assess the probability of a total rapid release vs a continuous slow. release for an extended period of time. Perfom dose calculations for most likely release mode and worse case mode.
6.2.1.5 Detemine the population areas in risk.
6.2.2 Detemine any protective action recommendations that are prudent. These recommendations should be made, plotted on Figure 1, and forwarded to the Emergency Manager using the guidance in this procedure.
6.2.3 Provide the Emergency Manager with current assessment infor-mation. A sunnary report should be prepared at periodic intervals as other duties and infomation pemit. The summary i
relcrt should include the following:
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6.2.3.1 Plot of most probEble and worse case integrated dose l
on on area map.
6.2.3.2 fateorological 'Jasis for the plot and potential for l
improvement or degradation of meteorological cor.di tions.
6.2.3.3 Sectors of highest potential dose and population centers of concern.
6.2.3.4 Efforts undensay to better detennine the magnitude of the potential release.
6.2.4 Complete the Emergency Notification Follow-up Message using Figure 2 EPIP 1.1.5, " Start-up and Operation of EOF".
Provide the completed fom to the Emergency Manager.
6.3 Assessment of Liquid Releases 6.3.1 Obtain offsite monitoring data in accordance with Corporate EPIP 1.1.10. "Offsite Surveys".
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6.3.2 Develop a followup report to the Emergency manager which l
includes the following:
6.3.2.1 Results of offsite monitoring.
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6.3.2.3 Dilution considerations and prJjected concentration of radioactive material at the nearest public water intake structure.
6,3.3 If the relecse is at Monticello, conta,t' the TSC and obtain the expected arrival time of the radioactive material at the Minneapolis and St. Paul water intake structures.
6.3.4 If necessary, contact the state EOC and recomend that Minneapolis and St. Paul water intakes be closed. (Use Figure 1.)
6.4 Assessment for Re-Entry 6.4.1 Obtain offsite monitoring data in accordance with Corporate EPIP 1.1.10, Offsite Surveys.
6.4.2 Prepare a report to the Emergency Manager which includes:
6.4.2.1 Summary of offsite monitoring results, includtng exposure rates, contamiriation levels, and isotopic O
information 6.4.2.2 Calculated values for the one-fear integrated expo.
sures, whole body and thyroid, which would be experi-enced by an' individual allowed unrestri:ted re-entry to the affected area- (U;e procedure in TA6 8.)
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NORTNERN STATES POWER C000PANY CORPORATE NUCLEAR ERIERGDICY PLAN NUCLEAR GENERATION DEPARTRAENT lasPLERADf710tG PROCEDURE NunmEn EPIP 1.1.11 Rev. 6 7.0 GUIDANCE FOR RECOMENDING PROTECTIVE ACTION NOTE:
1.
The values given in sections 7.1, 7.2 and 7.3 are conservative NSP guidance for reconnending protective action to the state (s).
This guidance is to be used at the discretion of the Emergency Manager and is based upon the following:
1The dose expressed is based on 1/4 of.the EPA lower limit dose for evacuation.
The thyrold dose expressed is based on child thyroid dose.
3The dose expressed is based on RG 8.13.
4The dose expressed is based on the EPA lower limit dose for evacuation.
These recommendations are based on actual offsite doses or a nigh degree of confidence that doses are actually expected offsite.
2.
Fer a General Emergencl. refer to Tab C - Flow Chart for General Emergency Offsite Protective DecisicGs. (
Reference:
NUREG 0654, Appendix 1).
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All protectivo action recomendations should be discussed with the State (s) Health Department, 4
Tre EP4 Guidelines for Reconnended Protective Actions located in IAS A shall serve as 3e maxi.nuiE^iWels.
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Further guidance may be found in Appendix C, Protective Action Guidance, NSP Corporate Nuclear Emergency Plan.
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' TABLE 1 MSP CONSERVATIVE GUIDANCE FOR P
NS
>(see note in Section 7.0)
EPA Mandatory Evacuation Recommend Reconnend Evacuation
' Evacuation Pregnant Women General Pubite and Children Reconmend No Sheltering Protective
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WHOLE BODY TASE (MILLIRG4) t EPA Mandatory Evacuation Reconnend Evacuation General Public Recomend a
Sheltering l
No Protective i
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0 li50 5030 25000 i
i THYROID DOSE (MILLIREM)
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NUCLEAR uMERAnow oEPARTesEur lesPLEnsEwTwoo PROctouRa NutsSER. EPIP 1.1.11 REv: 6 TABLE 2 NSP CONSERVATIVE GUIDANCE FOR ALLOWING RE-ENTRY (see Section 8.2)
WHOLE BODY DOSE (MILLIREM) 0 170
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No Protective Actions Allow limited Access with Protr.ctive Measures 0
5U0 1500 THYROID DOSE (MILLIREM) 10 i
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l NORTHERN STATES POWER CoesPANY CORPORATE NUCLEAR ERIERGENCY PLAN NUCLEAR oENERATION DEPARTidENT lesPLEnfENTweG PROCEDURE NueseER EPIP 1.1.11 REv: 6 INo Protective Actions will be ryy~ (nded up to 250 mrem whole body 7.1 dose or 1250 mrem Thyroid dose see note) 7.2 Shel terinq 7.2.1 Sheltering is a protective action which involves members of the general public taking cover in a building that can be made relatively air tight. Generally, any building suitable for winter habitation, with windows and doors closed and ventilation turned off..would provide reasonably good protection for about two hours; but would be ineffective after that period due to natural ventilation of the structure. _ _.
Sheltering is an appropriate protective action for the following:
i 7.2.1.1 Severe incidents in which an evacuation cannot be
("plenented because of the rapid passage of the plume im puff" release).
7.2.1.2 When an evacuation is. indicated, but local constraints, such as inclement weather, road condition, etc., dictate that directing the public to seek shelter is a monr feasible and effective protective measure than evacuation.
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7.2.1.3 As a precautionary measure, whila a detennination of the need to evacuate is made, i
7.E.2 Sheltering of the general public may be recommen r: Rem whole body dose or 1250 mrem thyroid deseged at 250(see note) 7.3 Evacuation 7.3.1 Timely evacuation of members of the population is the most effective protective action. There are, however, disadvan-tages and constraints that may make evacuation inappropriate.
Evacuation is an appropriate protective action for. the follow-ing:
7.3.1.1 Situations where the lead time between declaration of the emergency and population relocation is compatible with plume movement.
7.3.1.2 Situations which do not provide for advance warning, but for which substantial reductions in population dose can be made by avoiding) exposure to residual radioactivity (plume fallout in wake of sudden severe incidents.
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CORPORATE NUCLEAR IMERGENCY PLAN NUCLEAR GENERATION oePARTMENT IMPLEMENTING P90CEouRE EPIP 1.1.11 REv: 6 7.3.2 Evacuation of pregnant women and children may be recomended at 500 mrem whole body dose.3 (see note) mrem whole body dose. or 5000 mrem thyroid dose.ged at 1000(see note)
Evacuation of the general public nuy be reconsnen 7.3.3 7.3.4 Evacuation Time Estimates are located in Appendix D to the Corporate Nuclear Emergency Plan.
7.4 Public Alert & Notification System (PANS)
NOTE: It is the responsibility of the state (s) to activate this system.
7.4.1 A Site Area Emergency and a protective action such as shelter-ing or evacuation has been reconsnended for the public witnin all, or a portion of, the 10 mile Emergency Planning Zone (EPZ) surrounding each plant.
7.4.2 A General Emergency classification has been declared at either the Monticello or Pralrie Island Nuclear Generating Plant.
Q 7.4.3 The Emergency Manager shall, if necessary recommend to the Minnesota Divistori of Emergency Services (DES) and the C
Wisconsin Division of Emergency Government (WDEG) activation of the Public Alert and Notification System when a protective action guideline (PAG) is reconsnended.
7.4.4 The State (s) Duty Officer will be responsible for activating the Public Alert 4 Notification System which includes develop-ment of messages for the public.
7.4.5 If the State EOCs are not activated and the emergency requires insnediate activation, make such a recomendation directly to the County Sheriffs.
Monticello Area Prairie Island Area e Sherburne County e Goodhue County e Wright County e Dakota County o Pierce County 7.4.6 Tne Pubife Alert & Notification System for alerting the public l',
in the 10 mile Emergency Planning Zone (EPZ) surrounding each plant consists of the following:
e Fixed sirens fcr 100% coverage throughout the 5 mile zone
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and in population centers in the 5-10 mile zone.
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L NORTHERN STAft1 POWER COMPA%Y CORPORATE NUCLEAR EMERGENCY PLAN NUCLkAR GENERATION DEPARTMENT mapunemMS PROCEDURE wuumER: EPIP 1.1.11 nEv: 6 e Emergency vehicles with sirens and public address in the 5-10 mile areas not covered by fixed sirens.
e National Oceanic and Atmospheric Administration (NOAA) acti-vated tone alert radios in institutional, educational, and consnercial facilities, e The Einergency Broadcast Systen (EBS) which has access to television and radio stations within the area.
The primary means of alerting the public to an impending notification will' be the use of fixed and mobile sirenr. Onch alerted, the public should turn to local comunercial broadcast messages as the primary means of notification for conditions.
Should there be more than one PAG during an incident and they are detennined at djfferent times, this procedure shall be repeated.
7.5 Close Minneapolis and St Paul Water Intakes (for Monticello liquid release).
7.5.1 This protective action should be recomunended as detennined necessary by Section 6.3 of this procedure.
O 8.0 ' Guidance for Recommending Contamination Control and Re-entry V
8.1 Contamination Control (food, water, milk, etc.)
8.1.1 On a timely basis considering the needs of the energency effort and the persorinel resources available, the extent of radiological contamination within the 10' mile and 50 mile emergency planning zones should be assessed. This can be accomplished by implemmenting the " Radiological Environmental Monitoring Program". EPIP 1.1.12 or by examination of environmental nunitoring data from the state. This may not be part of the initial Protective Action effort.
8.1.2 As infonnation becomes available, detenninations concerning the need for offsite protective actions within the 50 mile EPZ should be made. These detenninations should be made in accordance with the environmental guidance of the State Protective Action Guides provided in the Corporate Emergency Plan, Appendix C, and the State of Minnesota Radiological Emergency Response Plan.
8.4.3 Provide any recommendations for contamination control to the state (s).
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i 8.2 Guidance for Reconnending Re-entry Following a general evacuation, re-entry may be recommended according to the following:
8.2.1 On an individual basis, persons with valid, uqent needs for access may be allowsd to re-enter under. the-following conditions:
8.2.1.1 The expected sole body dose coninitment does not exceed 500 mrem /yr; t i l
8.2.1.2 The expected thyroid dose commitment does not exceed i
1500 mrem /yr; and 8.2.1.3 Precautions are taken to minimize exposure.
8.2.2 The general population may be allowed to re-enter if the fol-lowing applies:
8.2.2.1 The expected whole body dose conunitment does not exceed 170 mrem /yr; and 8.2.2.2 The expected thyroid dose commitment does not exceed gi 500 mrem /yr.
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ttAPLERIENTW8G PROCEDURE NutdeER-EPIP 1.1.11 REv: 6 i
TAB A EPA GUIDELINES'FOR RECOMMENDED PROTECTIVE ACTIONS (WHOLE BODY AND THYROID DOSE FROM EXPOSURE TO A GASEOUS PLUME)
Projected Dose (Rem) to Recommendation Comments The Population Actions Whole Body <1 No planned protective actions.
Previously recommended Issue an advisory to seek shelter protective actions may and await further instructions, be reconsidered or Thyro'id <5 Monitor environmental radiation terminated.
levels.
Whole Body 1 to 45 Seek shelter as a minimum.
If constraints exist, Consider evacuation. Evacuate special consideration unless constraints make it should be given for impractical.
evacuation of children Thyroid 5 to < 25 Monitor environmental radiation and pregnant women.
levels. Control access.
Whole Body 5 and above Conduct mandatory evacuation.
Seeking shelter would Monitor environmental radiation be an alternative if levels and adjust area for evacuation were not Thyroid 25 and above mandatory evacuation based on imediately possible.
these levels. Control access.
Projected Dose (Rem)
To Emergency Workers Whol'e Body 25 Control exposure of emergency Although respirators team members to these levels and thyroid prophy-Thyroid 125 except for lifesaving missions.
laxis should be used (Appropriate controls include where effective to time limitations, respirators control dose to emer-and thyroid prophylaxis.)
gency workers, Thyroid dose should not be the Whole Body 75 Control exposure of emergency limiting factor for team members perfonning a life-lifesaving missions, saving mission to this level.
(Control of time ex be most effective.)posure will 4.
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GUIDELINES FOR CONTAMINATION OF HUMAN FOOD AND ANIMAL FEED
- Preventive PAGs -
1.5 rum projected dose consnitment to thyroid 0.5 rem projected dose consnitment to whole bndy, bone marrow, or any other organ Response Levels Preventive PAG
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I-131 Cs-134 Cs-137 Sr-90 Sr-89 0.13 2
3 0.5' 8
- Initial Activity ( AreauCi/m )
2 Deposition Forage Concentration (uC1/kg) 0.05 0.8 1.3 0.18 3
(Fresh Weight)
Peak Milk Activity (uCf/ liter) 0.015 0.15 0.24 0.009 0.14 Total Intake (uC1) 0.09 4
'7 0.2, 2.6 A
Emergency PAGs -
15 rem projected dose censnitment to the thyroid 5 rem projected dose commitment to the whole body, bone marrow, or any other organ Response Levels for Emergency PAG I-131 Cs-134 Cs-137 Sr-90 Sr-89 Infant / Adult Infant / Adult Infant / Adult Infant / Adult Infant / Adult
[nftfal Activity 1.3 18 20 40 30 50 5
20 80 1600
- rea'Dgposition luCf/m )
orage Concentration 0.5 7
8 17 13 15 1.8 8
30 700 luci/kg)
Peak Milk Activity 0.15 2
1.5 3
2.4 4
0.09 0.4 1.4 30 luCf/ liter) i rotal Intake (uC1) 0.9 10 40 70 70 80 2
7 26 400 4
Reference:
Accidental Radioactive Contamination of Human Food and Animal Feeds; Food and Drug Administration Recommendations for State and Local Agencies, Federal legister, October 22, 1982.
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NORTHERN STATES' POWER COefPANY CORPORATE NUCLEAR EMERGENCY PLAN NUCLEAR GENERATION DEPARTRAENT ledPLEMENTING PROCEDURE NunseER: EPIP 1.1.11 REv: 6 s
TAB A RECOMMENDED WOTETIVE ACTIONS ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE REC 0f91 ENDED EMERGENCY Inhalation of Evacuation, shelter, access control, PHASE 1
gases, radio-respiratory protection, prophylaxis (0.5 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />),
fodine, or (thyroid protection).
particulate Direct wnole Evacuation, shelter, access control body exposure Ingestion of Take cows off pasture, prevent cows
~
milk from drinking surface water, discard contaminated milk, or divert to stored products, such as cheese.
INTERMEDIATE Ingestion of Wash all produce, or impound produce, R
PHASE 2 fruits and delay harvest until approve substi-vegetables tute uncontaminated produce.
Ingestion of Cut off contaminated supplies, substi-water tute from other sources, filter, de-mineralize.
O
~
(24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> E Ie body Relocation, decontamination, access 30 days),to v
~
exposure and control.
inhalation Ingestion of Decontamination, condemnation, or food and water destruction of food; deep plowing, contaminated condemnation, or alternate use of from the soil land.
LONG TERM PHASE 3 either by resus-pension or uptake
- through ruots.
Whole body expo-Relocation, access control, decon-sure from deposi-tamination, fixing of contamination, (Over 30 days),
tion material deep plowing, or inhalation of resuspended material.
)
1 Emergency Phase - Time period of major release and subsequent plume exposure.
2 Intemediate Phase - Time period of moderate continuous release with plume exposure and contamination of environment.
4 3
(,
Long Tenn Phase - Recovery period.
- i V
- "Tvnical" pnet.Arcident tima na ricAe l
rom ir4eninam Pege Of U t
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NORTHERN STATES POWER COGIPANY CORPORATE Mm's saR EndERGENCY PLAN NUCLEAR GENERATION DEPARTRIENT MAPLERIENTW8G PROCEDURE nuesEER: EPIP 1.1.11 REv: 6 TAB A REPRESENTATIVESHIELDINGFACTORSFROMGAitMACLOUDSOURCE Sh telding Structure or Location Factor (a)
Representative Range Outside 1.0 i'
Vehicles 1.0
'~ ~
Wood-Frame House (b) 0.9 l
(No Basement)
Basement of Wood House 0.6 0.1to0.7(C)
Masonry House (No Basement) 0.6 0.4to0.7(C)
[-
Basement of Masonry House 0.4 0.1 to 0.5 (c)
Large Office or Industrial 0.2 0.1 to 0.3 (c, d)
!- A Building C'
(a)
The ratio of the dose received inside the structure to the dose that would be received outside the structure.
(b) A wood frame hous'e with brick or stone veneer is approximately equivalent, to a masonry house for shielding purposes.
(c)
This range is mainly due to different wall materials and different geometries.
(d)
The shielding factor depends on where the personnel are located within the building (e.g., the basement or an inside room).
i SELECTED SHIELDING FACTORS FOR AIRBORNE RADIONUCLIDES Wood house, no basement 0.9 Wood house, basement 0.6 Brick house, no basement 0.6 i
Brick house, basement 0.4 Large Office or Industrial Building 0.2 Outside 1.0
- Taken from SAM) 77-1725 (Unlimited Release)
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NORTHERN STATES POWER COMPANY CoWoRATE NUCLEAR ERIERGENCY PLAN wuCLEAR oumaRATion oEPARTesEur martEausmus PRoCEcuRE muussa EPIP 1.1.11 Rev: 6 TAB A REPRESENTATIVE SHIELDING FACTORS FOR SURFACE DEPOSITED RADIONUCLIDES REPRESENTATIVE REPRESE.1TATIVE STRUCTURE OR LOCATION SHIELDING FACTOR [,)
RANGE 1 m above an infinite smooth 1.00 surface I m above onlinary ground 0.70 0.47 - 0.85 i
1 m above center of 50-ft roadways,.
0.55 0.4
- 0.6 50% decontaminated lI Cars on 50-ft road; Road fully contaminpted 0.5 0.4
- 0.7 Road 50% decontaminated 0.5 0.4
- 0.6 Road fully decontaminated 0.25-0.2
- 0.5 Trains 0.40 0.3
- 0.5 One and two-story wood-frame 0.4 0.2
- 0.5 house (no basement)
(b)
One and tw6-story block and 0.2
-0.04 - 0.40 brick house (no basement) b)
House basement, one or two walls 0.1 0.03 - 0.15 fully exposed:
.0.5 (b)
One story, less than 2 ft of 0.03 - 0.07 basement, walls exposed Two stories, less than 2 ft of 0.03 (b) 0.02 - 0.05 basement, walls exposed 1,'.
Three-or four-stgry structures, 5000 to 10,000 ft per floor; First and second floors:
0.05 0.01 - 0.08 Basement 0.01 0.001 - 0.07 Multi-story structures,10,000 ft - per floor:
b)
Upper floors 0.01 0.001 - 0.02 b) 0.001 - 0.015 Basement 0.005
. I (a) The ratio of dose received fr. side the structure to the dose that would f
be received outside the structure.
l (b)
Away from doors and windows.
Taken from SAND 77-1725 (Unlimited Release) j 19,, 22 l,j p
1:
s 1
NORTHERN STATES POWER COMPANY CORPORATE NUCLEAR EMEMGkscY pt.AN NuctaAR onneRAnow osPARTuswT metamenTme PROcanuns muussR: EPIP 1.1.11 nav: 6 h/
1As e DETERMINATION OF ONE-YEAR DOSE Cor4MITMENT AS CRITERIA FOR RE-ENTRY TO EVACUATED AREAS 2
Inputs:
- Ground deposition, Q, in uC1/m of radionuclides whose composition has been determined by laboratory analyses or portable MCA.
- Exposure rate, R,, 3' above contaminated ground determined by field measurements. Used to confirm calcu' lated dose rates.
Assume:
- Soil-to-air re-suspension factor of 10 uC1/m per uC1/m2 (units of
-6 3
,-1) for inhalation pathway.
3
- Breathing rate of 0.91 m /hr.
Find:
- Projected one year dose to individuals re-entering evacuated area, sum of external and internal doses.
i=n 2
2 6
External: I (0.F.),
mrom/hr/pC1/m x Qg uC1/m x 10.pC1/uci l t) i=1 x 1,44 Ti (1-e i
- Dose factors can be obtained from Table E-6 of Reg. Guide 1.109.
inn 3
Inhalation: I 0.91 m /hr x Q uC1/m2, 196 pC1/uci x 10'4
-1 m
g S t) i=1 x (D.F.)** ares /pC1 x 1.44 T, (1-c i
- Dose factors for inhaled radionuclides can be ontained from Tables E-7 l
to E-10 of Reg. Guide 1.109. Use most restrictive D.F. listed (infant to adult).
1 =
identified isotope integration period (use 1 year) t =
Tg= Effective environmental half-life of isotope 1.
Use radiological half-life, unless better information available.
2 O = Ground concentration in uC1/m of 9,,g,,,
g I
Ingestion :(To be determined) l m
Ncte: For times when the ground is show-covered, assume ingestion path-t way exposure to be negligible.
i ro,, i m....e pw 20 m22__
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EPIP 1.1.11 Rev 6 TAB C v
FLOW CHART FOR GENERAL EMERGENCY OFFSITE PROTECTIVE DECISIONS
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(Sense en Centres Room la*** sore. No Dose preseeneae Aseverses l
. SMinute Cecieseamekaag. Acttwenon of Alerting System end (SS Message i
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' '3 Actual or protectee reseees of 20% goe from core er sees of pave cas centros of tne seeat to iatrueers.
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Page 21 of 22 s
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NOnTHEnN STATES POWER COesPANY COnPonATE NuCLEAn ERsEnGUICY PLAN NuctsAn osmanATion ospAnTisenT insplansamme anocsouna Mussesn.
EPIP 1.1.11 nav: 6 1
l FIGURE 1 PROTECTIVE ACTIOK RECOMMENDATION CHECKLIST 1
NOTE:
v.
3, 3,y o When this form is
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telecopied to the
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r state, a call must
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EM to explain the b,. u w s
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recommandation.
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used in conjunction 4
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with an Emergency l
N i
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up Message.
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zones as follows:
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I for evacuation i
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5 Date Time Wind direction / speed At From (mph)
PROTECTIVE ACTION:
SHELTER Sector (s)
Mile (s)
Sector (s)
Mile (s)
CONSIDER EVACUATION OF PREGNANT WOMEN AND CHILDREN EVACUATION Sector (s)
Mile (s)
Sector (s)
Mile (s) p,,
.~. 9, ;
ACTIVATE PUBLIC ALERT & NOTIFICATION SYSTEM CLOSE MINNEAPOLIS & ST PAUL WATER INTAKES (for Monticello 1iguid release)
~
CONTAMINATION CONTROL Sector (s)
Mile (s) l (food, water, milk)
Sector (s)
Mile (s)
' '~~ ~
CONSIDER TERMINATION OF PROTECTIVE ACTIONS IN PRO l
Justification for Protective Action Recommandations:
Prepared by:
Approved by: Emeroency Manaaer/ Emergency Director Form 1741 tit 43 E898 Of 8
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!O itsPi.Easemma rRocEDuRE i
NORTHERN STATES POWER COtePANY NutneER EPIP 1.1.18 0
l REY:
PREPARED BY:
EFFECTIVn DATE: December 21, 1983 q
AdmEmYrgenqyPreparedness m
1.1.18 CONTROL OF RADI0 ACTIVE REVIEWED BY:
A*'[
- MATERIALS AT THE EOF Gen Su Chemistry APPROVED BY:
General Manaaer Nuclear Plants 1.0 Purpose and Objective The purpose of this procedure is to control radioactive materials and limit contamination at the EOF. The access point for potentially contaminated personnel and sample transport paths are also defined.
2.0 Conditfors and Prerequis;ty G
This procedure is to be initiated when any or all of the following conditions have t'
occurred:
2.1 Radioactive samples have been sent Tr's the plant to the EOF for counting.
2.2 Contaminated plant personnel have been transported to the EOF for decontamination.
2.3 A release of radioactive materials has occurred and samples from the offsite survey teams are being returned to the EOF for counting.
2.4 Emergency response personnel which may have been exposed to a plume or other radioactive materials require access to the EOF.
3.0 Organization and Responsibilities 3.1 Overall Responsibility - Emergency Manager 3.2 In Charge - Radiation Protection Support Supervisor 3.3 Assistance - EOF Coordinator
- Radiation Protection Specialist M fF490211 @
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NORTHERN STATES POWER COMPANY CORPCRATE NUCLEAR EMERGENCY 5'LAN NUCLEAR GENERATION DEPARTMENT IMPLEMENTING PROCEDURE NumeER:EPIP 1.1.18 REv: 0 n
4.0 Responsibilities 4.1 Radiation Protection Support Supervisor (RPSS) 4.1.1 Responsible for control of radioactive materials and limiting con umination at the EOF.
4.1.2 Supervise the set up and operation of cccess control procedures for samples and potentially contaminated personnel entering the EOF.
4.1.3 Initiate surveys of the EOF to detemine habitability and contamination areas.
Note _:
EPIP 1.1.13. " Protective Guidelines for EOF Personnel and Evacuattor!"
provides guidance to the EM for limiting personnel exposure.
4.2 E0F Coordinator 4.2.1 Assist in the establishment of a radiological control point for access to the EOF by providing personnel to assist the Radiation Protection Specialist.
4.2.2 Relocate the security access to a point near the receiving area if
/
any of the conditions identified in Section 2.0 of this procedure occur. (see figure 1).
Plate:
e At the discretion of the EOF Coordinator, personnel may be allowed to exit the EOF other than through the potentially contaminated access control area.
Prior to exiting however, all personnel must follow security procedures for leaving the EOF.
4.3 Radiation Protection Specialist 4.3.1 Establish radicactive material control measures as specified in Section 5.0 of this procedure.
4.3.2 Control access of potentially contaminated personnel to the EOF.
4.3.3 Control receipt and transport of samples within the EOF.
4.3.4 Direct personnel decontamination measures in accordance with EPIP 1.1.16.
'4. 3. 5 Complete surveys within the EOF as required by the RPSS.
4.3.6 Direct facility decontamination activities as required.
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NORTHERN STATES POWER CoasPANY CORPORATE me me EasERGENCY PLAN muctuan asnenAnow asPAnTisEnT msPtsasemme PnocPouan nuesesk: EPIP 1.1.18 Rav: 0 0
5.0 Procedure 5.1 Personnel Access 5.1.1 Instruct the guards to lock the front entrances and establish a security point near the receiving area (see figure 1). Signs should be posted on the front doors instructing al.1 personnel to use the rear entrance.
5.1.2 Ensure that the airlock door and all other doors to the EOF are closed.
5.1.3 Establish a barrier rope from point A to points B & C (see Figur,e 1) for contamination control and radiological screening. This will establish an E0F access holding area.
5.1.4 Set up a step off pad and frisker at points E & F (see Figure 1).
5.1.5 Direct personnel entering the EOF to pass through control point E,'
using the frisker to detect contamination as they do so.
I 5.1.6 Personnel which have been screened and are not contaminated should be b
allowed access to the EOF in accordance with EPIP 1.1.17, " Personnel Monitoring at the EOF".
Personnel not involved with EOF activities O
(e.g. evacuated Plant personnel) should be instructed to assemble in C
one of the unoccupied classrooms.
5.1.7 Contaminated personnel should be instructed to assemble in the EOF access holding area.
5.1.8.
Personnel should be decontaminated in accordance with EPIP 1.1.16 "Off-site Personnel and Vehicle Monitoring and Decontamination".
Note:
The dec0ntamination shower drains to a 1000 gallon liquid j.
waste holding tank which is equipped with a high level alarm. There is a 4" withdrawal pipe outside the receiving access door for pumping out this tank.
5.1.9 After decontamination, personnel shall be checked at Frisker Point F and allowed access to the EOF.
5.2 Sample Access 5.2.1 Establisis barriers and step off pads as specified in Section 5.1 of this procedure.
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d NORTHERN STATES POWER COGAPANY CORPORATE NUCLEAR ERRERGENCY PLAN NUCLEAR GENERATION DEPARThsENT llePLEndENTING PROCEDUfE i
NueseER: EPIP 1.1.18 REv: 0 i
5.2.2 The access guard shall ensure that all samples are held at S0P Point E until released by a Radiation Protection Specialist.
5.2.3 The Radiation Protection Specialist assigned to the E0F Count Room shall ensure that, prior to transporting re.mples to the EOF Count Room, all samples are bagged or rebcgged as necessary and dose rates are checked, as necessary, before pas.dng through clean areas.
5.2.4 If necessary, samples should be rebagged and stored in the shielded
. sample storage area.
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p Figure 1 Access Control for Radioactive Materials at the EOF l
SYMBOLS O Frisker p,
Step off pad Shielded sample storage if D'
Iw D
Comm/I&C Training Room # 5 r3 4"
Q Withdrawal Pipe Outside Airlock Hallway Gua_rd O.,ggp
_. Access Door
(
e a
O shower 1000 gal CLEAN privarv Waste AREA cud;ain T
Holding o.
Tank 2
@@l HOLDING i
AREA gu __
Receiving Area stores area a
Overhead Door i
Comp. Office-Loading Dock Area (parking)
Page 5 of 5 4
O samuasEnTina PnocEDunE NOnTHEnN STATES PoWEn Cot 0PANY NueseEn.
EPIP 1.2.1 nEv: 3 q
EPPECnVE DATE:
December 21, 1983 PREPAnED BY:
Adm. Emergencf' Preparedness L
1.2.1 EM Y PLAN nEviEWED BY:-
Gen Supt Rad Tstry ApenoVEDB General Manager Nuclear Plants 1.0 PURPOSE AND OBJECTIVE The purpose of this procedure is to specify the training requirements for NSP and support agency emergency response plan personnel.
Documentation requirements are also specified. Detailed outlines of the training topics are to be provided in the lesson plans.
~
2.0 CONDITIONS AND PREREQUISITES O
2.1 Personnel assigned emergency response activities shall receive training as described in this procedure.
2.2 Emergency Plan Training is conducted in accordance with the Emergency Plan Training Program.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 Overall Responsibility - General Manager Headquarters Nuclear Group 3.2 In Charge - Manager, Production Training 3.3 Assistance - Production Trair.ing Staff 4.0 RESPONSIBILITIES 4.1 General Manager Headquarters Nuclear Group l
l 4.1.1 Responsible for overall development of the Emergency Response Training Program 4.2 General Supt. Radiation Protection & Chemistry 4.2.1 Administration of the -overall NSP Emergency Preparedness Dennenm Fomtt74902ttt43 Poe. 1 of 7 e
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NORTHERN STATES POWER CoalPANY CORPORATE NUCLEAR ERIERGENCY PLAN mCLEAR aENERAnoN oePARTasENr usPtansENTwas -==
NunseER:
EPIP 1.2.1 REv: 3 1
i 4.3 Manager of Production Training 4.3.1 Administration of the NSP Emergency Response Training Program.
4.3.2 Development and conduct of the Emergency Plan Training Program.
4.3.3 Development of training program course content.
4.3.4 Assignment of program instructors.
4.3.5 Scheduling of personnel for emergency response training.
4.3.6 Coordination of the Emergency Response Training program with_- -
scheduled emergency response drills and exercises.
4.4 Department Maragers 4.4.1 Scheduling suboniinate personnel to attend emrgency plan training in accordance with schedules developed,by Production Training Department.
5.0 PROCEDURE 5.1 Training Requirements for the Corporate Emergency Organization
()
5.1.1 Corporate Overview Training a.
All corporate personnel assigned energency response duties shall annually receive Corporate Overview Training which generally encompasses the following areas:
- 1) Int"oduction to Emergency Planning
Corporate Emergency Response Plan 4
Sununary of Site FJnergency Plans 5
Summary of Minnesota State Emergency Plan 5.1.2 Specialized Training l
l a.
All personnel assigned the responsibility for filling the Power Production Management Position si;all annually receive training which generally encompasses the following areas:
- 1) Corporate Overview Training i
- 2) EQEC Orientation i
- 3) Corporate Implementing Procedure Training TlC o
Form t749114tt43 Paes 2 m7 s
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l NORTHERN STATES POWER COMPANY CORPORATE &# CLEAR EMERGENCY PLAN NUCLEAR GENERATION DE*ARTMENT IMPLEMENTING PROCEDURE NuMeEn:
EPIP 1.2.1 REv: 3 O"
b.
All personnel assigned the responsibility for filling the Emergency Manager position shall annually receive training which generally encompasses the following areas:
- 1) Corporate Overview Training
)
- 2) Emergency Manager Training
- 3) EOF Coordinator Training
- 4) Protective Action Guide Training
- 5) EOF Orientation
- 6) HQEC Orientation i
c.
All personnel assigned the responsibility to fill the EOF Coordinator position shall annually receive EOF Coordinator i
training which generally encompasses the following areas:
)
- 1) Corporate Overview Training
- 2) EOF Coordinator Training 3
Emergency Manager Training 4
Protective Action Guide Training 5
EOF Orientation
- 6) Communication Training NOTE: Only EOF Coordinators authorized to assume Emer-gency Manager responsibilities are required to receive q
('
d.
.All System Dispatchers who have Emergency Plan responsi-bilities shall annually receive training which generally encompasses the following areas:
- 1) Corporate Emergency. Plan Implementing Procedures -
Notification e.
All personnel assigned emergency organization responsibili-ties which require their presence in the HQEC shall annually receive HQEC trainfug which generally encompasses the fol-lowing areas:
1 Corporate Overview Training 2
HQEC Orientation 3
Corporate Implementing Procedure Training f.
All personnel assigned emergency organization responsibili-ties which require their presence in the EOF shall annually receive EOF training which generally encompasses the following areas:.
- 1) Corporate Overview Training
- 2) EOF Orientation
- 3) Corporate Implementing Procedure Training
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EPIP 1.2.1 nev: 3 g.
All personnel assigned the responsibility for filling the Radiation Protection Support Supervisor position shall annually receive training which generally encompasses the following areas:
- 1) Corporate Overview Training
- 2) EOF Orientation
- 3) Corporate Implementing Procedure Training
- 4) Protective Action Guide Training 5.2 Training Requirements for the Plant Emergencf 0rganizations 5.2.1 Plant Overview Training a.
Ali plant personnel assigned energency response duties shall annually receive Plant Overview Training which generally encompasses Plant Emergency Response Plan / Procedures. '
b.
For initial training an overview of the interface between Plant Emergency Plans Corporate Plan, and State Plans should be presented.
5.2.2 Specialized Training a.
All plant personnel assigned energency response duties for 3
in-plant. radiation protection functions shall annually receive Eme gency Radiation Protection Specialist training which genera.ly encompasses the following areas:
- 1) Plant Overview Training
- 2) Plant Emergency Plan Implementing Procedures 3
Activation of Emergency Plan 4
Radiological Surveillance and Control Training b.
All plant personnel assigned the responsibility tc fill the Radiological Emergency Coordinator position shall annually receive special training which generally encom-passes the following areas:
- 1) Plant Overview Training
- 2) Protective Action Guide Training 3
Accident Assessment 4
Activation of Emergency Plan
- 5) Plant Emergency Plan Implementing Procedures 1
c.
All personnel who are assigned responsibility to fill the Emergency Director position shall anr.ually receive training which generally encompasses the following areas:
1 Plant Overview Training m
2 Classification of Emergencies Training i
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- 3) Activation of Emergency Organization 4
Protective Action Guide 5
Accident Assessment d.
All personnel who are assigned responsibility to fill the Emergency Communicator and/or Assembly Point Coordinator positions shall annually receive training which generally encompasses the following areas.
- 1) Plant Overview Training
- 2) Roles of Emergency Communicator and Assenbly Point Coordinator 5.3 Training Requirements for Outside Organizations 5.3.1 State and Local a.
Hospital and emergency medical personnel shall be trained annually in the following areas:
- 1) Basic Radiation Protection and Contamination Control
- 2) Plant Emergency Response Plan and Implementing Pro-cedures b.
Local Fire Department personnel shall be trained annually in the following areas:
- 1) Basic Radiation Protection and Contaminat' ion Control
- 2) Site Access Procedures
- 3) Plant Fire Fighting Equipment and Aspects of Fire -
Fighting in Contaminated Areas c.
Local and State Police department personnel shall be trained annually in the following areas:
- 1) Specific Plant Emergency Response Plan (as applicable to offsite notification and. response) d.
Local and state agencies shall receive initial training in and subsequent training as part of annual drills in the following areas:
- 1) Plant and Corporate Emergency Response Plan Overview
- 2) Interfaces between NSP and outside agencies e.
Training for media and public infomation personnel shall be perforfted on an annual basis by the Comunications Depart-ment. Training for these personnel shall be perfomed in the following areas':
- 1) The Corpor' ate Emergency Response Plan and Organization
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NORTHERN STATES power COGIPANY CORPORATE paaf's Mt EIGERGENCY PLAN NUCLEAR oesERArioM oEPARTMENT IGAPLEMENTN0G PROCEDURE NutseER:
EPIP 1.2.1 REv: 3 (G
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The Nature and Effects of Radiation 3
Corporate Communications of Public Infonnation 5.3.2 Vendors a.
Vendors wi,11 mceive necessary training'upon request.
5.4 Scheduling of Emergency Preparedness Trainiro 5.4.1 Corporate and Plant Training Schedule a.
The Manager Production Training shall produce an annual schedule that covers the mquired training. This schedule should cover the time period from April 1 to March 30 of the succeeding year. A 3 month grace period is allowed for additional training.
t-b.
Scheduled training may be in the fonn of lectures (live or video tape), exercises, drills, reading assignments or practical factor training. Subsequent annual training may be documented through reading assignments, attendance of scheduled lectures, or participation in drills, and drill critiques. The Manager Production Training shall forward a sununary report of completed training to the General Supt. Rad. Prot. & Chemistry. This sununary should be T
submitted on an annual basis (based on Emergency Plan training annual cycle).
c.
Training that is specifically applicable to either the Monticello and/or Prairie Island Plants will be conducted and/or coordinated by the Production Training Staff.
In order to adequately document co.npletion of this training the Manager Production Training, shall provide the plant training supervision with a list of the required training to be conducted by the plant. The plant training super-vision will schedule the listed training in the plant's training program and complete the list by supplying the scheduled dates. The completion of the scheduled training will be documented and returned to the Manager, Production Training, for documentation on the corporat,e schedule. The Manager, Production Training, shall fonvard a summary report of completed training to the Gen. Supt. Rad. Prot. &
Chemistry. Training that is part of a continuous program of qualification at the plant sites, such as the first aid or
,the fire fighting programs, satisfies the requirements of l
this instruction.
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noRTwfRn STATES POWER c00spANY CORPORATE NUCLEAR EMERGENCY PLAN wuctaAR oEntnATion oEPAsmsEwr ineptansswTwee PRocaouRE NuesSER:
EPIP 1.2.1 REv: 3 O
5.5 Documentation 5.5.1 Activities accomplished to meet the requirements of this pro-cedure shall be documented. When training has been completed, the instructor shall forward the following documentation to the Manager Production Training (corporate and state gov't agencies) or Plant Training Superintendent (plant specific).
a.
Training lesson p.lan or outline b.
Lecture ' quiz (if applicable) c.
Attendance record d.
Quiz grades (if applicable) 5.5.2 The Manager Production Training shall ensure that all outside organizations and corporate personnel assigned to the emergency response team complete the :equired training. He shall sched-ule additional training as necessary to ensure all response team members maintain proficiency in their emergency plan actions.
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mortausNTwee pnocsouna NOnTHEnN STATES POWEn COMPANY Numosa:
EPIP 1.2.2 anv: 3 hQ EFFECTIVE DATE:
December 21, 1983 PREPAaED BY:
Adm. Emergency 7r aredness TITLE 1 hr h
1.2.2 EXERCISES AND DRILLS naviewso ev:
y Gen Supt Rad P Apenovao ev:
GeneraT Manager Nuc War Plants 1.0 PURPOSE AND OBJECTIVE The purpose of this procedure is to skcify the responsibilities and require-ents for conducting drills and eurcises. Drills and Exercises are con-t ducted to test the Corporate and Plant Nuclear Emergency Response Organiza,-
tions, Plans, Implementing Procedures, facilities, and equipment.
2.0 CONDITIONS AND PREREQUISITES r\\
V Exercises and drills should be conducted in accordance with the NSP Drill and Exercise Program.
3.0 ORGANIZATION AND RESPONSIBILITIES
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3.1 Overall Responsibility - General Manager Headquarters Nuclear Group 3.2 In Charge - Gen. Supt. Rad. Prot. & Chemistry l
Manager Production Training 3.3 Assistance - Production Training Sections 4.0 RESPONSIBILITIES 4.1 General Manager Headquarters Nuclear Group 4.1.1 Management responsibility for development, implementation, and l
maintenance of the Drill and Exercise Program.
l.
4.2 General Manager Nuclear Plants 4.2.1 Responsible for approval of drill schedule.
4.2.2 Responsible for authorizing the conduct of major exercises specified in the program.
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1 4.3 Gen. Supt. Rad. Prot. & Chemistry l
l 4.3.1 Responsible to ensure that applicable regulatory requirements are met.
4.3.2 Responsible for coordinating pre-exercise drills and exercises with the activities of all involved NSP or5anizations, state and local officials, and the NRC, as appropriate.
4.3.3 Responsible for reviewing drill and exercise critiques, and tracking identified deficiencies..
A.4 Manager Production Training i
4.4.1 Administrative responsibility for the development, implementa-tion and maintenance of the Drill and Exercise Program.
4.4.2 Responsible for the conduct of drills and exercises.
4.4.3 Responsible for coordinating the Emergency Response Training Program with the Drill and Exercise Program.
d 4.4.4 Responsible for development of drill / exercise scenarios.
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4.4.5 Responsible for assignment of observers / controllers for the m
conduct of the Drill and Exercise Program.
4.4.6 Responsible for assigning individuals to correct deficiencies identified as a result of drills or exercises.
4.4.7 Responsible for revision to the Training Program as required to correct deficiencies identified during drills / exercises.
4.4.8 Responsible for developing a schedule of drills as specified I
in the program.
4.4.9 Responsible for verifying completion of the drill schedule.
4.4.10 Responsible for approval of plant drill scenario packages, 4.4.11 Responsible for preparation of drill and exercise critiques.
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4.4.12 Responsible for maintaining records associated with the Drill and Exercise Program, 4.5 Plant Manager i
i 4.5.1 Responsible for providing personnel to assist in the develop-i ment of scenarios.
4.5.2 Responsible for providing personnel to serve as drill and exer-cise observers / controllers.
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5.0 DRILL AND EXERCISE PROGRAM DEVELOPMENT 5.1 A comprehensive program of drills and ' exercises shall be, developed and maintained.
5.2 The program shall describe the administrative organization for planning, conducting and documenting drills and exercit.es.
5.3 The program shall describe all the necessary drills and exercises required to maintain NSP personnel qualifications in emergency preparedness activities. These requirements shall satisfy 10 CFR Part 50, Appendix E and the guidelines provided in NUREG-0654 and IE Infor1 nation Notice No. 82-44.
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iMPLEMENnNa PRoCEouRE NORTHERN STATES PC'erER COMPANY NUMBER EPIP 1.2.3 Rev: 3 hw M
EPPECnvE oATE. December 21, 1983 PREPAREo sv:
Adm. Emergejcy7re aredness Af
'p 1.2.3 MAINTENANCE OF EMERGENCY REvwwEn ov:
A A
OCEDURES Gen Supt Rad stry j
APPROVED 8 Genfral Ma(agerTuclear Plants 1.0 PURPOSE AND OBJECTIVE This procedure and Nuclear Generation Departmental Procedures estab-l lish a system to govern the generation, identification, revision, distribu-tion, and inventory of the Corporate Nuclear Emergency Plan and Corporate Nuclear Emergency Plan Implementing Procedures. It also provides for periodic reviews of plans and procedures and specifies other administrative programs that support the emargency preparedness effort.
2.0 CONDITIONS AND PREREQUISITES 2.1 Maintenance of emergency plans and procedures is supported by the Operational Quality Assurance Program.
t 3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 Overall Responsibility - Gen. Supt. Rad. Prot. & Chemistry.
l 3.2 In Charge - Administrator Emergency Preparedness.
4.0 RESPONSIBILITIES 4.1 Gen. Supt. Rad. Prot. & Chemistry' 4.1.1 Maintenance of the Corporate Nuclear Emergency Plan and Corporate Nuclear Emergency Plan Implementing Procedures.
4.1.2 Review of Plant Nuclear Emergency Plans, i
I 4.1.3 Scheduling of exercises.
4.1.4 Scheduling of an Annual Independent Review of the Emergency Pre-paredness Program to include:
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EPIP 1.2.3 REv: 3 O
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a.
An evaluation for adequacy of interfaces with state and local governments.
b, Drills & Exercises.
c.
Emergency Plans & Implementing Procedures.
d.
Training (capabilities).
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Facilities & Equipment.
4.1.5 Establish raanagement controls to ensure that corrective actions identified as a result of NRC Inspection Reports, Drill and Exer-cise Critiques, and Annual Reviews of the Emergency Preparedness Progran are implemented.
1 4.1.6 Maintain the Headquarters Emergency Center (HQEC).
4.1.7 t,
Maintain the Public Alert and Notification Systems (PANS).
4.1.8 Annual Internal review, update, and certification of emergency plans and agreements.
4.1.9 Corporate Emergency Plan Surveillance Program.
4.1.10 Funding for state and local emergency preparedness.
4.2 Administrator Emergency Preparedness 4.2.1 Preparation of the Corporate Nuclear Emergency Plan and Corporate Nuclear Emergency Plan Implementing Procedures.
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NUCLEAR GENERATION DEPARTMENT CORPORATE NUCLEAR EMERGENCY PLAN
'"PLEMENmG PROCEDURE NORTHERN STATES POWER COM#ANY NUMBER-EPIP 1.2.4 REv: 3 EPPECME DATE:
December 21, 1983 PRErARED BY:
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1 Adn. Emergency Prep &rtRiness hh h,
1.2.4 SURVEILLANCES REviEwEn eV:
Gen Supt Rad P ry APPROVEDSY:
Genera ~l Mariger N5 clear Pl$nts 1.0 PURPOSE AND OBJECTIVE This procedure establishes a Surveillance Program to maintain the Corporate Nuclear Emergency Plan, Implementing Procedures, response facilities and equipment.
_ 2.0 CONDITIONS AND PREREQUISITES The HQEC and EOFs have been established and equipped.
3.0 ORGANIZATION AND RESPONSIBILITIES Gen. Supt!. Rad. Prot. & Chem.
l 3.1 Overall Responsibility Gen. Supt. Rad. Prot. & Chem.
l 3.2 In Charge Manager Production Training Plant Managers Production Training 3.3 Assistance Plants 4.0 CORPORATE NUCLEAR EMERGENCY PLAN SURVEILLANCE REQUIREMENTS 4.1 Emergency Operations Facility (EOF) l Procedure Frequency 1.
Comunication Test (federal. state, local)
Monthly 2.
Comunication Test (equipment check)
Quarterly 3.
Inventory non-HP Equipment Quarterly l
4.
Inventory HP Equipment Quarterly 5.
Operational Test of HVAC Quarterly 6.
HVAC HEPA Filters once per opera-ting cycle or once every 18 months a omuu P999 I
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NUCLEAR GENERATION DEPARTMENT IMPLEMENTING PROCEDURE NUMeER. EPIP 1.2.4 REv: 3 n
4.2 Headquarters Emergency Center (HQEC)
Procedure Frequency 1.
Communication Test Monthly 2.
Inventory Quarterly 4.3 Corporate Surveillances Procedure Frequen'cy 1.
Telephone Number Verification Quarterly 2.
Independent Review of Emergency Preparedness Annually 3.
Internal Update and Review Annually 5.0 RESPONSIBILITIES 5.1 Gen. Supt. Rad. ' Prot. & Chemistry l
5.1.1 Responsible for ensuring that the required surveillance pro-cedures are developed to maintain corporate plans, procedures, facilities and equipment.
5.1.2 Responsible for maintaining the following surveillance procedures:
o HQEC Communication Test
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e HQEC Inventory Telephone Number Verification e Independent Review e Internal Update Review 5.1.3 Responsibilities that are required to maintain the above Sur-veillance Procedures include:
e Development and revision of surveillance procedures.
e Scheduling of surveillances, o
Conduct of surveillances, o
Initiation and resolution of corrective action for dis-crepancies noted as a result of the surveillances.
e Records
- Completed surveillance procedures
- Copies of revisions to surveillance procedures
- Completed surveillance schedules 5.2 Manager Pro-duction Training 5.2.1 Responsible for the following EOF Surveillance Procedures:
e Comunication Test (federal, state and local) e Communication Test (equipment check) e Inventory non-HP equipment e Operational Test. of HVAC e-HVAC HEPA Filters
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5.2.2 Responsibilitics that are required to. maintain the above Sur-veillance Procedures include:
e D'evelopment and revision of surveillance procedures.
e Scheduling of surveillances.
e Conduct of surveillances, o Initiation and resolution of corrective action for dis-crepancies noted as a result of the surveillance.
e Records
- Cor.pleted surveillance procedures
- Copies of revisions to surveillance procedures
- Completed surveillance schedules 5.3 Plants Managers 5.3.1 Responsible for the following EOF Surveillance Procedure:
e Inventory of HP equipment 5.3.2 Responsibilities that are required to maintain the above Sur-veillance Procedure include:
o Development and revision of surveillance procedures, o Scheduling of surveillances.
e Conduct of surveillances.
e Initiation and resolution of corrective action for dis-k's, crepancies noted as a result of the surveillance.
e Records
- Completed surveillance procedures
- Copies of revisions to surveillance procedures
- Completed surveillance schedules-b N
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Nuclear Support Services Dept. Procedure.'
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DOCUMENT CONTROL FOR THE NSP
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' PREPAAi!D BY:
M CORPORATE NUCLEAR EMERGENCY PLAN AND IMPLEMENTING PROCEDURES REVIEWED SY:
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Q l.0 Purpose The purpose of this procedura is to establish a system to govern the generation, identification, revision, distribution, and inventory of Corporate Nuclear Emergency Plans and Corporate Nuclear Emergency Flan Implementing Procedures. This procedure will ensure that, in the event of a nuclear plant emergency, all plan and procedure holders shall h.ive access to current Corporate Nuclear Emergency Plan and Corporate Nuclear Emergency Plan Implementing Procedures.
2.0 Scope This procedure governs document control for the Corporate Nuclear Emergency Plans and Corporate Nuclear Emergency Plan Implementing Procedures. The following topics ars' presented:
Section Topic 6.1 Review and Approval of Corporate Nuclear Emergency Plan / Implementing Procedures 6.2 Document k:cnerol for Corporate Nuclear Emergency Plan Manuals 6.3 Document Control for Corporate Nuclear Emergency Plan Implementing Procedure Manuals 6.4 Distribution of Plan / Procedure Manuals, and Revision
?ackages 6.5 Filing Requirements 6.6 Required Inventories 6.7 Required Records f'
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.m-Nuclear Support Services DepL Procedure:
9.t Rev: t f,S 3.0 Applicability s
This procedure shall apply to the Corporate Nuclear Emergency Plan and Corporate Nuclear Emergency Plan Implementing Procedures.
4.0 Definitions None 5.0 Responsibilities s
5.1 The Assistant Administrator Emergency Preparedness shall ba responsibile for 1.
Preparation of the Corporate Nuclear Emergency. Plan and changes theret,o.
2.
Preparation of Corporate Nuclear Emergency Plan Implementing Procedures and changes thereto.
5.2 Managar Nuclear Environmental Services shall be responsible fort 1.
Review of the Corporate Nuclear Emergency Plan and changes thereto.
2.
Review of ths Corporate Nuclear Emergency Plan Implementing Procedures tad changes thereto.
3.
Notifying plant management of changes within the Corporate Nuclear Emergeccy Plan and Corporate. Nuclear Emergency Plan Implementing Procedures that affect the Plant Nuclear Emergency Plan / Implementing Procedures.
4.
Submittal of plan or procedure revisions to the Nuclear Regulatory Commission.
5.
Document control measures as delineated bthin Section 6.2-6.7 for the Corporate Nuclear Emergency Plan and Corporate
' Nuclear Emergency Plan Implementing Procedures.
6.0 Instructions 6.1 Review and Approval of the Corporate Nuclear Emergency Plan and Corporate Nuclear Emergency Plan Implementing Procedures i
6.1.1 Proposed revisions to the NSP Corporate Nuclear Emergency 1
Plan or Corporate Nuclear Emergency Plan Implementing Procedures shall be submitted to the Assistant Administrator Emergency Preparedness.
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6.1.2 The Assistant Administrator Emergency Preparedness shall:
1.
Conduct a review of the proposed change.
2.
Determine the nature of the change and its effect od other related documents.
3.
Forward a revised copy of the affected document to the Manager Nuclear Environmental Services for review.
6.1.3 The Manager Nuclear Environmental Services shall' 1.
Review the proposed revision.
2.
Determine if the change decrasses effectiveness of the
)
plan and if the change will require NRC approval prior to implementation.
3.
Deternica if the change affects the Plant Emergency Plan or the Plant Emergency Plan Implementing Procedures and if so, advise plant management.
4.
If determined to be satisfactory, forward the proposed change to the D". rector of Nuclear Generation p
(Plan) or General Manager Nuclear Plants (Procedures)
Q for approval.
6.1.4 When the proposed change has been approved, revised pages of the Corporate Nuclear Emergency Plan or Implementing Procedures shall be prepared and distributed in accordance with Sections 6.2, 6.3, and 6.4.
6.1.5 6.2 Document Control Measures for Corporate Nuclear Emergency Plan Manuals 6.2.1 When revisiona to the plan section of the Emergency Plan manusIs are generated, chey shall:
1.
Include revised manual title page, if necessary.
2.
Include revised Table of Conteits, if necessary.
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3.
Include a revised Record of Revision page which lists the current plan pages and the appendices. Appendix pages do not have to be individually 11sted 'on the Record of Revision page due to special distribution l
requirements found in Izter sections.
4.
Inc~1ude documentation of preparation, review, and approvar signature for new revisions to the manual.
Normally, this doctmentation is found on the Record of Revision page.
5.
Include merkings on revised plan pages to indicate changes, such as the use of sidelining.
6.
Include current revision numbers on revised plan pages. This number shall correspend to the Record of Revision Rev number.
7.
Include page numbers composed of two digits [(plan section number) - (page number)] on each revised plan page.
8.
Be distributed as eingle page revisicrs in lieu of distributing entire sections of the Pian or the
,T entire Plan.
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9.
Be distributed in accordance with the requirements of section 6.4.3.
6.2.2 When revisions to Appendix A Letters of Agreement are generated, they shall:
1.
Include a revised Table of Contents for Appendix A 11 sting all Letters of Agreement.
1 2.
Be revised individually or in total.
3.
Be distributed in accordance with section 6.4.3.
6.2.3 When a revision to Appendix B, Emergency Padiation Environmental Monitoring Program is generated, it shall:
1.
Be made as a complete document in 11eu of page revisions.
2.
Be distributed in accordance with Section 6.4.3.
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6.2.4 When revisions to Appendix C, Protective Action Guidance, are generated:
1.
The revisions shall be made as complete documents l
in lieu of page revisions.
l 2.
The revision shall be distributed in accordance with Section 6.4.3.
j 6.2.5 When revisions to Appendix D1-D3 are generated:
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1.
The revision shall he made as a complete document, j
e.g. Appendix D1.
2.
The revision shall be distributed in accordance with
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6.2.6 When revisions to Appendix E, NSP Cross Reference Index (Corporate) are generated:
I 1..
The revision shall be made as a complete document.
l' 2.
The revisions shall be distributed in accordance with section 6.4.3.
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6.4 Cistribution of Plan /Procedura Manuals and Revision Packages l
Distribution of Corporate Nuclear Emergency Plan and Corporate Nuclear Emergency Plan Implementing Procedure Marsuals shall be administered as indicated in the following paragraphs.
6.4.1 - Distribution lists shall be prepared, approved and utilized by the Assitant Administrator Emergency Preparedness and shall include:
L.
Name of manual holder.
2.
Professional or job title of manual holder.
l 3.
Address of manual holder.
l 4
Telephone number (if nacassary).
5.
Ascigned controlled copy number.
6.4.2
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6.4.3 Ravision package to the Corporate Nuclear Emergency Plan should include:
1.
Transmittal manifest.
2.
Distribution list.
3.
Acknowledgement of Receipt.
j 4.
Title Page, if necessary.
5.
Record of Revision Page.
r 6.
Tablo of Contents, if necessary.
7.
Revised pages with changes marked.
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Summary of changes, if necessary.
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6.5 Departmental Filing Regttirements 6.5.1 Corporate Nuclear Emergency Plan filing should include:
1.
Copy of Revision Package to: Ristory File.
2.
NRC submittal letter to:
- EP-Gov't-NRC-Cderespondence Pl'an file.
- Monticello Plant NRC - I i E Correspondence file.
- Prairie Island Plant NRC - I & E Correspondence file.
3.
Transmittal Manifest to:
EP-Transar.:tal Manifest-Plan file.
4.
Returned Acknowledgement of Receipts to:
EP Acknowledgement of Roceipt-Plan-Rolding file.
5.
Certification Slip to:
EP-Acknowledgement of Receipt-Plan-Certification file (when all acknowledgement of receipts have been returned).
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4.
5.
Certification Slip to:
EP-Acknowledgement of Receipt-Procedures-Certification file (when all Acknowledgement of Receipts have been j
returned).
6.6 Inventories 6.6.1 Corporate Nuclear Emergency Plans and Corporate Nuclear Emergency Plan Implementing Procedures should be invantoried at a sinimum of once each two-year period.
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m 6.6.2 Inventory is defined as requesting the individual, to whom the copy is assigned, to complete a page check against the most current listing of pages or procedures (Record of Revision page).
6.6.3 Inventories should be initiated by request from the Manager Nuclear Environmental Services.
6.6.4 Requests for inventory should include instructions for performing, documenting, and returning the results of the inventory to the Manager Nuclear Environmental Services.
6.6.5 Requests for inventory may be included within transmittal manifests for revision packages and a returned acknowledgement of receipt will provide documentation of completion.
6.6.6 Discrepancies noted during the inventory should be reported to the Manager Nuclear Environmental Services.
6.6.7 Selected copies,; may further be audited by NSS Department Personnel to ensure that they are up to date.
Re ion Departmental records are established by Nuclear Support Services (NSS) to facilitate an sdainistrative management process. Departmental records do not require specialized storage. The following record.1 should be maintained in NSS:
6.7.1 Historical Copies l.
Revision packages to the Corporate Nuclear Emergency Plan including appendices.
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Retention Time 2 years 2 years 3.
Changes to document control 2 years procedure 4.
Results of inventories 2 years l
1.
Corporate Nuclear Emergency Plan Indefinite Indefinite 6.7.4 Media Conversion 1.
Records that are required for the affected l
life of the plant or indefinitely may be stored on microfils.
y 2.
Conversion to microfilm should fo11cv standard departmental procedures.
6.7.5 Outdated Records Document control records which have elapsed their specified retention times may be disposed of.
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