L-PI-03-033, Emergency Plan Implementing Procedures

From kanterella
Revision as of 12:41, 23 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Emergency Plan Implementing Procedures
ML030830198
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 03/13/2003
From: Solymossy J
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-03-033
Download: ML030830198 (45)


Text

NiC' Committed to Nuclear Excefllenc Prairie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC L-PI-03-033 March 13, 2003 1 0CFR50.4 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 AND 50-306 LICENSE NOS. DPR-42 AND DPR-60 PRAIRIE ISLAND EMERGENCY PLAN IMPLEMENTING PROCEDURES Furnished with this letter are the recent changes to the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures F3 and the EOF Emergency Plan Implementing Procedures F8. This submittal includes the following documents:

INDEXES:

Emergency Plan Implementing Procedures TOC EOF Emergency Plan Implementing Procedures TOC REVISIONS F3-20 Determination of Radioactive Release Rev. 18 Concentrations F3-31 Response to Security Related Threats Rev. 7 F8-11 Transfer to the Backup EOF Rev. 4 DELETIONS:

None TEMPORARY CHANGE DELETIONS:

None INSTRUCTIONS:

Please post changes in your copies of the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures (F3 & F8). Procedures, which have been superseded or deleted, should be destroyed. Please sign and return the acknowledgment of this update to Bruce Loesch, Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089.

1717 Wakonade Drive East

  • Welch, Minnesota 55089-9642 Telephone: 651.388.1121 A04-7

USNRC NUCLEAR MANAGEMENT COMPANY, LLC L-PI-03-033 Page 2 This letter contains no new commitments and no revisions to existing commitments.

As per 10 CFR 50.4, two copies have also been provided to the NRC Region III Office and one to the NRC Resident Inspector. If you have any questions, please contact Mel Agen at 651-388-1121 Extension 4240.

,Joep M. mos it Vice President, rainIaland Nuclear Generating Plant CC USNRC - Steve Orth, Region III (2 copies)

NRC Resident Inspector (w/o attachment)

Attachment 1717 Wakonade Drive East

  • Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Mfst Num: 2003 - 0169 Date  : 03/05/03 FROM  : Bruce Loesch/Mary Gadient Loc  : Prairie Island TO  : UNDERWOOD, BETTY J Copy Num: 515 Holder : US NRC DOC CONTROL DESK SUBJECT : Revisions to CONTROLLED DOCUMENTS Procedure # Rev Title Revisions:

F8-11 4 TRANSFER TO THE BACKUP EOF UPDATING INSTRUCTIONS Place this material in your Prairie Island Controlled Manual or File. Remove revised or cancelled material and recycle it. Sign and date this letter in the space provided below within ten working days and return to Bruce Loesch or Mary Gadient, Prairie Island Nuclear Plant, 1717 Wakonade Drive E.,

Welch, MN 55089.

Contact Bruce Loesch (ext 4664) or Mary Gadient (ext 4478) if you have any questions.

Received the material stated above and complied with the updating instructions Date

PRAIRIE ISLAND NUCLEAR

Title:

I GENERATING PLANT EOF Emerg Plan Implementing Procedures TOC I IEffective Date : 03/05/03 lApproved By:

I --o-f PS sup&-

bw4ý'

Document # Title Rev F8-1 EMERGENCY OPERATIONS FACILITY ORGANIZATION 7 RESPONSIBILITIES DURING AN ALERT, SITE AREA OR 7 F8-2 GENERAL EMERGENCY IN THE EOF F8-3 ACTIVATION & OPERATION OF THE EOF 5 EMERGENCY SUPPORT & LOGISTICS 4 F8-4 OFFSITE DOSE ASSESSMENT & PROTECTIVE ACTION 8 F8-5 RECOMMENDATIONS F8-6 RADIOLOGICAL MONITORING & CONTROL AT THE EOF 6 4

F8-8 OFFSITE AGENCY LIAISON ACTIVITIES 7

F8-9 EVENT TERMINATION OR TRANSITION TO RECOVERY 2

F8-10 RECORD KEEPING IN THE EOF 4

F8-11 TRANSFER TO THE BACKUP EOF EMERGENCY REMP 3 FB-12 Page 1 of 1

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES SŽ~EFRECE.USE4"

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be availableat the work location.

O.C. REVIEW DATE: EFFECTIVE DATE I: ,C; ý 5C M. Werner 3 o0 s tOWNER:

Page 1 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES 1.0 PURPOSE This procedure specifies the actions to be taken if the EOF must be evacuated and the EOF functions transferred to the Backup EOF.

2.0 APPLICABILITY This procedure is applicable to the Emergency Manager, RPSS, Technical Support Supervisor, and the EOF Coordinator.

3.0 PRECAUTIONS 3.1 An evacuation of the EOF may be necessary due to the existence of a conventional hazard, e.g., fire in EOF, loss of power, hazardous gases, etc.

3.2 Radiological conditions requiring an evacuation of the EOF may vary significantly based on the extent of operations in progress, the severity of the radiation levels, the estimated time that the radiation levels will be significant, and the integrated dose to personnel.

3.3 Non-essential personnel (i.e., those not directly involved in the activities of the EOF organization) should be evacuated first from any areas that exhibit elevated radiation or contamination levels. These personnel would include vendors, consultants, and public employees of the state and local agencies.

4.0 RESPONSIBILITIES The Emergency Manager has the overall responsibility to direct and coordinate an evacuation of the EOF and will be supported directly by the RPSS and the EOF Coordinator.

5.0 PREREQUISITES Radiological or conventional hazards exist in the EOF such that personnel are at risk to remain in the emergency center or the EOF has lost its functionality.

6.0 PROCEDURE 6.1 Emergency Manager SHALL:

6.1.1 Direct the EOF Coordinator and the RPSS to provide status reports of the EOF environment.

6.1.2 Refer to F8-6, Radiological Monitoring and Control at the EOF, for protective action guidelines for EOF personnel.

6.1.3 Ensure nonessential personnel (vendors, consultants, and state/local employees) are evacuated from the EOF if there is a high potential for a hazardous environment.

Page 2 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES

" The need to evacuate emergency response personnel for radiological reasons should be determined based on the following considerations:

1 The integrated dose that these personnel would receive if they remained in a radiation area.

2. The potential loss of the ability to utilize key technical personnel due to radiation exposure limits.

S3. The effectiveness of the emergency organization

-. :*/ operating in a condition of reduced mobility or communication due to use of protective clothing and equipment.

S 4. The potential exposure received during evacuation as compared to the potential exposure received by not evacuating.

6.1.4 If it becomes necessary to evacuate the EOF and time is available for a direct transfer to the Backup EOF, request that another Emergency Manager designee establish an EOF organization at the Backup EOF within the estimated evacuation time constraints. See Attachment A, Directions to the Backup EOF.

  • -.- ~ A new EOF organization should be staffed and functional at

-- TE* *,'Jt the Backup EOF before the EOF is evacuated, if conditions permit.

6.1.5 If time is NOT available for a direct transfer to the Backup EOF (i.e., the EOF must be evacuated before the Backup EOF can be staffed by EOF personnel), transfer the EOF functions back to the TSC until the backup EOF is staffed.

A. Notify the Emergency Director of the need to quickly evacuate the EOF and the necessity of the TSC to temporarily receive the EOF offsite functions.

I/NOTE.

... ~

....,,.whenThe TSC will transfer the EOF functions to the Backup EOF facility is staffed by EOF personnel.

B. Consider the option of bussing the current EOF staff to the Backup EOF as opposed to setting up a new EOF staff.

Page 3 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES 6.1.6 Ensure the Emergency Director is informed of the EOF evacuation to the backup EOF.

6.1.7 Direct the RPSS to determine the evacuation route that would limit I exposure and provide a means of monitoring personnel evacuating the EOF.

6.1.8 Direct the EOF Coordinator to prepare for evacuation by arranging for transportation of personnel, as appropriate.

The EOF organization at the Backup EOF should be ready to assume the EOF offsite functions when:

1. Plant status has been determined and is being tracked.
2. The MIDAS and ERCS are functioning and all necessary communication equipment is functioning.
3. Offsite communication links to state and local government are functioning.

6.1.9 When the Backup EOF is prepared to receive the EOF offsite functions, perform an orderly turnover of the following EOF operations to the Backup EOF.

I A. Offsite Communications B. Offsite Dose Assessment and Field Team Monitoring C. Reclassification and Offsite Protection Action Recommendation authorizations The Backup EOF should inform the NRC, TSC, state and N,0TE:6;; local governments of the change of EOF location.

Page 4 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES 6.2 EOF Coordinator SHALL:

6.2.1 When informed of the decision to evacuate the EOF, supervise the assembly of materials and equipment to be removed from the area.

Z'*

  • Materials may be contaminated and thus may not be able to E :i> , 7*

.be l removed. Everything that cannot be removed should be

- secured in a locked area.

Consider assembling and transferring the following material. Don't delay if material cannot be assembled.

A. "Plant Flow Diagrams" (one set exists at Ren Square 10th floor reference library)

B. "Logic Diagrams" (one set exists at Ren Square 10th floor reference library)

C. "Controlled Drawing File Index" (drawing aperture cards are located at 414 Nicollet Mall)

D. Cellular phone for EM and/or EOF Coordinator (used for communications in transit to Backup EOF) 6.2.2 Upon evacuation of the EOF, the EOF staff may be required to go to the Backup EOF to augment the Backup EOF staff members. Direct the Asst.

EOF Coordinator to arrange for transportation of personnel and equipment.

6.2.3 Contact each Sheriff's Department and inform them of the departure to the designated offsite assembly area or monitoring and decontamination facility.

6.2.4 Transfer your offsite responsibilities to the backup EOF (or TSC if necessary) as directed by the Emergency Manager.

Page 5 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES 6.3 RPSS SHALL:

6.3.1 When informed of the decision to evacuate the EOF determine possible evacuation routes that would limit exposure of personnel while enroute to the Backup EOF or an offsite monitoring and decontamination facility.

A. Selection of the offsite assembly area or monitoring and decon center will depend on various factors such as wind direction, weather conditions, and availability of the site. The following guidelines are used to assist in the selection of an assembly area or offsite monitoring and decon center:

1. Selected site should be upwind from any release.
2. Selected site should be accessible.
3. Evacuation routes to the selected site should minimize the time personnel would be exposed to any offsite radioactive release.

B. Any one of the following offsite facilities may be utilized as an assembly area or offsite monitoring and decon facility.

NOTE: SEC notifies Red Wing Service Center Representative when we go to an Alert.

1. Red Wing Service (if used, monitoring and decon kits from the EOF will need to be transported to the facility for setup).
2. Goodhue County/City of Red Wing Monitoring and Decon Center at the Red Wing Fire Department.
3. Dakota County Monitoring and Decon Center in Hastings.

6.3.2 If a county monitoring and decon facility is chosen, contact the appropriate county to notify and coordinate the logistics of the facility's use.

6.3.3 Supervise the assembly of monitoring teams to help coordinate the monitoring and decontamination of personnel, as necessary, during the evacuation.

6.3.4 Identify a collection point for Field Team samples to be transferred to a Monticello sample courier.

Page 6 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES 6.3.5 Contact the Monticello Plant to arrange for a sample courier to pick up samples at the collection point and return them to the Monticello lab for analysis. Possibly, the helicopter service could be used for this courier service (see F8-4).

6.3.6 Transfer your offsite responsibilities to the Backup EOF (or TSC if necessary) as directed by the Emergency Manager.

6.4 The Technical Support Supervisor SHALL:

Supervise the transfer of Technical Support personnel to the Backup EOF.

Page 7 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES Attachment A Directions To Backup EOF

1. The Backup EOF will be set up on the 10th floor of Xcel Energy's Renaissance Square.
2. You must bring your company I.D. card to gain access to the facility.
3. If approaching from Interstate 94:

A. Take Interstate 94 West to 5th Street off-ramp.

B. Stay on 5th Street to Nicollet Mall.

C. Park in either the ramp on the right side between Nicollet and Hennepin off 5th Street or park in the Skyway ramp at the corner of 4th and Nicollet.

4. If approaching from Interstate 35W:

A. Take Interstate 35W to Interstate 94 West.

B. Exit Interstate 94 West at Hennepin Avenue.

C. Stay on Hennepin Ave. to 4th Street and turn right.

D. Park in either the ramp between Hennepin and Nicollet or the Skyway ramp at the corner of 4th Street and Nicollet.

5. Renaissance Square (a reddish brown sandstone building) is located across 5th Street from Xcel Energy G.O. on Nicollet Mall.

Page 8 of 8

Mfst Num: 2003 - 0168 Date  : 03/05/03 FROM  : Bruce Loesch/Mary Gadient Loc  : Prairie Island TO  : UNDERWOOD, BETTY J Copy Num: 515 Holder : US NRC DOC CONTROL DESK SUBJECT : Revisions to CONTROLLED DOCUMENTS Procedure # Rev Title Revisions:

F3-20 18 DETERMINATION OF RADIOACTIVE RELEASE CONCENTRATIONS F3-31 7 RESPONSE TO SECURITY RELATED THREATS UPDATING INSTRUCTIONS Place this material in your Prairie Island Controlled Manual or File. Remove revised or cancelled material and recycle it. Sign and date this letter in the space provided below within ten working days and return to Bruce Loesch or Mary Gadient, Prairie Island Nuclear Plant, 1717 Wakonade Drive E.,

Welch, MN 55089.

Contact Bruce Loesch (ext 4664) or Mary Gadient (ext 4478) if you have any questions.

Received the material stated above and complied with the updating instructions Date

Is PRAIRIE ISLAND NUCLEAR I

Title:

GENERATING PLANT Emergency Plan Implementing Procedures TOC SI Effective Date : 03/05/03 I I lApproved By:

UBPS Supt-/'

Document # Title Rev F3 -1 ONSITE EMERGENCY ORGANIZATION 19 F3-2 CLASSIFICATIONS OF EMERGENCIES 32 F3-3 RESPONSIBILITIES DURING A NOTIFICATION OF UNUSUAL 18 EVENT F3 -4 RESPONSIBILITIES DURING AN ALERT, SITE AREA, 28 OR GENERAL EMERGENCY F3-5 EMERGENCY NOTIFICATIONS 21 F3-5 .1 SWITCHBOARD OPERATOR DUTIES 8 F3-5.2 RESPONSE TO FALSE SIREN ACTIVATION 9 F3 -5.3 RESPONSE TO RAILROAD GRADE CROSSING BLOCKAGE 8 F3-6 ACTIVATION & OPERATION OF TECHNICAL SUPPORT CENTER 16 F3-7 ACTIVATION & OPERATION OF OPERATIONAL SUPPORT 16 CENTER (OSC)

F3-8 RECOMMENDATIONS FOR OFFSITE PROTECTIVE ACTIONS 20 F3-8 .1 RECOMMENDATIONS FOR OFFSITE PROTECTIVE ACTIONS FOR 13 THE ON SHIFT EMERGENCY DIRECTOR /SHIFT MANAGER F3 -9 EMERGENCY EVACUATION 18 F3-10 PERSONNEL ACCOUNTABILITY 19 F3-11 SEARCH & RESCUE 8 F3-12 EMERGENCY EXPOSURE CONTROL 14 F3-13 OFFSITE DOSE CALCULATION 15 F3-13.3 MANUAL DOSE CALCULATIONS 11 F3-13.4 MIDAS METEOROLOGICAL DATA DISPLAY 7 F3-13.5 ALTERNATE METEOROLOGICAL DATA 5 Page 1 of 3

PRAIRIE ISLAND NUCLEAR Title  : Emergency Plan Implementing Procedures TOC GENERATING PLANT Effective Date : 03/05/03 Document # Title Rev WEATHER FORECASTING INFORMATION ii F3-13.6 F3-14.1 ONSITE RADIOLOGICAL MONITORING F3-14.2 OPERATIONS EMERGENCY SURVEYS 9 F3-15 RESPONSIBILITIES OF THE RADIATION SURVEY TEAMS 22 DURING A RADIOACTIVE AIRBORNE RELEASE F3-16 RESPONSIBILITIES OF THE RADIATION SURVEY TEAMS 17 DURING A RADIOACTIVE LIQUID RELEASE F3-17 CORE DAMAGE ASSESSMENT 10 F3-18 THYROID IODINE BLOCKING AGENT (POTASSIUM IODIDE) 10 F3-19 PERSONNEL & EQUIPMENT MONITORING & DECONTAMINATION 8 F3-20 DETERMINATION OF RADIOACTIVE RELEASE 18 CONCENTRATIONS F3-20 .1 DETERMINATION OF STEAM LINE DOSE RATES 9 F3-20.2 DETERMINATION OF SHIELD BUILDING VENT STACK 9 DOSE RATES F3-21 ESTABLISHMENT OF A SECONDARY ACCESS CONTROL POINT 10 F3-22 PRAIRIE ISLAND RADIATION PROTECTION GROUP RESPONSE 16 TO A MONTICELLO EMERGENCY F3-23 EMERGENCY SAMPLING 18 F3-23.1 EMERGENCY HOTCELL PROCEDURE 12 F3-24 RECORD KEEPING DURING AN EMERGENCY 7 F3-25 REENTRY 8 F3-26.1 OPERATION OF THE ERCS DISPLAY 7 F3-26.2 RADIATION MONITOR DATA ON ERCS 7 F3-26.3 ERDS - NRC DATA LINK 1 F3-29 EMERGENCY SECURITY PROCEDURES 18 F3-30 TRANSITION TO RECOVERY 6 Page 2 of 3

-4 PRAIRIE ISLAND NUCLEAR Title  : Emergency Plan Implementing Procedures TOC GENERATING PLANT Effective Date : 03/05/03 Document # Title Rev RESPONSE TO SECURITY RELATED THREATS 7 F3-31 2

F3-32 REVIEW OF EMERGENCY PREPAREDNESS DURING OR AFTER NATURAL DISASTER EVENTS Page 3 of 3

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be availableat the work location.

O.C. REVIEW DATE: OWNER: EFFECTIVE DATE M.Werner 5-6-03 Page 1 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 1.0 PURPOSE This procedure provides instructions to determine the concentration and flow rate of radionuclides being released via the steam release headers or Shield Building vent stacks.

2.0 APPLICABILITY This Instruction SHALL apply to Radiological Emergency Coordinators (REC), Radiation Protection Support Supervisor (RPSS), and the MIDAS operators.

3.0 PRECAUTIONS Use engineering judgment whenever possible to estimate steam relief flow rates.

4.0 PREREQUISITES An Alert, Site Area Emergency, or General Emergency has been declared and there exis an actual or potential for radioactive airborne release.

Page 2 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 5.0 PROCEDURE 5.1 Steam Release Activity 5.1.1 IF the ERCS is obtaining steam release data, THEN obtain the steam line dose rates and the steam rad'release rate from the ERCS as follows:

A. At the TOC (Turn On Code), enter "GRPDIS STM-RAD" to gain access to the STM-RAD group of parameters.

B. The display will respond with a list of the points along with the prompt: ENTER UPDATE RATE IN SEC (5-1800). Enter the desired update interval, and then press <RETURN>.

C. Log Loop A & B Rad Level on Part I of PINGP 783.

D. Log Radiation Release Rate in pCi/sec on Part I of PINGP 783 (ERCS Rad Release Rate is already converted to pCi/sec Xe-133 Equiv.)

E. Go to Step 5.1.7.

5.1.2 If the ERCS is unable to provide steam release data, request an RPS to obtain the steam line dose rates in accordance with F3-20.1; or read R51 and R52 Rad Monitors local readout located in Train A Event Monitor Room (via 112 Bus Room). Log results on Part II of PINGP 783.

A. Using the time since reactor shutdown, obtain the Dose Rate Concentration Conversion Factor (IDE) from Figure 1, Figure 2 or Figure 3.

B. Calculate the noble gas release concentration, ItCi/cc Xe-133 equivalent, by multiplying the steam line monitor dose rate (mR/hr) times the dose rate concentration conversion factor ([tCi/cc/mR/hr).

Page 3 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 5.1.3 Determine if a steam release is occurring thru the Safety Relief Valves, PORV's, Dump Valves or SDAFW Pump Turbine Exhaust.

A. If the Power Operated Relief Valves (PORV's) are not closed:

1. Estimate the fractional opening of the PORV (0-1). Assistance from the Engineering Technical Group may be required as appropriate.
2. Determine each PORV flow rate as follows:

Flow Rate (CFM) = (3500)(L) where L = fractional opening B. If the dump valves are not closed:

1. Check the position of the MSIV's. If both closed, no release should be occurring. If open, continue.
2. Estimate the fractional opening of the dump valves, L, (0-1).

Assistance from the Engineering Technical Group may be required as appropriate.

3. Calculate each dump valve flow rate as follows:

Flow Rate (CFM) = (6400)(L) where L = fractional opening (0-1)

C. If any of the safety relief valves are not closed:

1. The REC should request engineering to calculate each safety relief flow rate.
2. If the safety is known to be full open, a default flow of 6000 cfm may be used.

D. If Steam Driven Aux Feedwater Pump is in operation on contaminated steam from faulted steam generator, use a steam exhaust flow rate of 150 cfm as a maximum flow rate.

Page 4 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 5.1.4 Determine the total steam release rate by summing the PORV, dump valve, safety valve, and Steam Driven Aux Feedwater Pump flow rates.

5.1.5 Ifthe SG's are flooded and water is relieving thru the PORV's, dumps or safeties, use engineering judgment to determine the flow rate., Use the estimated SG tube break flow rate. Consider using SI and Charging flow rates to be the flow rate through the SG tube break. Assume all the liquid flashes as it leaves the PORV's, dumps, or safeties.

5.1.6 Determine the noble gas release rate (Xe-1 33 Equiv [tCi/sec) by multiplying the noble gas concentration by the total steam flow per Part IV of PINGP 783.

5.1.7 Determine the iodine release rate or concentration as follows:

A. Obtain the SG wide range level (%).

1. If the SG level
  • 85%, use 0.001 as an iodine/noble gas ratio.
2. If the SG level > 85%, use 0.1 as an iodine/noble gas ratio or as determined by primary system of S/G sample.

B. Calculate the iodine release rate or concentration by multiplying the noble gas release rate or concentration by the applicable iodine/noble gas ratio.

Page 5 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES In order to perform a MIDAS dose projection using an iodine/noble gas ratio of 0.1, use "Manual Entry of Isotopic Concentration" or "Manual Entry of Isotopic Release Rate".

II 5.2 Shield Building Vent Stack Activity 5.2.1 Calculate the ventilation flow rates (cfm) of each Shield Building Vent Stack.

A. Determine which ventilation systems are in service.

(Information may be obtained from Control Room.)

Unit 1 Vent: Aux Special - 8000 CFM Shield Building Vent - 400 CFM Spent Fuel Pool Special - 5000 CFM Unit 2 Vent: Aux Special - 8000 CFM Shield Building Vent - 400 CFM Spent Fuel Pool Special - 5000 CFM Shield Building Vent should only be inservice on the unit experiencing accident. There are two trains of Shield Building Vent, each 200 CFM.

B. Log results on PINGP 784.

5.2.2 Determine the gas activity (Xe-133 Equiv.) being released via the Shield Building Vent Stacks.

A. If the Shield Building Vent Stack radiation monitors are operable and on scale:

1. Obtain the Unit 1 and Unit 2 Shield Building Vent Stack radiation monitor count rate or dose rate from 1 [2] R-22 or 1 [2] R-50.
2. Using the count rate or dose rate, refer to the radiation monitor calibration curves, Figure 4, Figure 5 or Figure 7, to determine the gaseous release activity in [tCi/cc Xe-1 33 equiv.
3. Record results on PINGP 784.

Page 6 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

i*.*--*,*..F3-20 OF RADIOACTIVE "DETERMINATION

'RELEASE CONCENTRATIONS REV: 18 B. If the Shield Building Vent Stack radiation monitors are not operable or not on-scale:

1. Request the RPS to obtain the 1 [2] R-50 gas chamber dose rates in accordance with F3-20.2.
2. Using the 1 [2] R-50 gas chamber dose rates, refer to Figure 5,

-to determine the gaseous release activity in jtCi/cc Xe-133 equiv.

3. Record results on PINGP 784.

5.2.3 Determine the iodine release activity (1-131 equiv.) as follows:

A. Request the RPS to obtain gas, iodine and particulate samples in accordance with F3-20.2.

B. Determine the total sample time in minutes.

1. Record the time the AgZ was changed.
2. Record the sample start time, which may be either:

" accident start time;

" release start time, if known. This may be determined by rad monitor indication, or;

"* time since AgZ was last changed

3. Using the sample start and ending times, determine the total sample time, in minutes.
4. Record results on PINGP 784.

Page 7 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES C. Obtain and record on PINGP 784, the AgZ flow rates in cc/min.

.t For high flow rate AgZ section, use conversion factor of NOTE
*

.. . -.. 1:.

__.. ...... I.l 2.83E04 cclft 3 convert CFM to cc/min.

D. Determine the total iodine activity on the AgZ adsorber.

1. Obtain, from the RPS , the count rate or dose rate on the AgZ, whichever is applicable.
2. Using the count rate or dose rate, refer to Figure 8, Figure 9, or Figure 10, to determine the total iodine activity, in gtCi, on the AgZ adsorber.
3. Record results on PINGP 784.

E. Determine the iodine activity, in gCi/cc, for each stack, as follows:

1. Stack Activity = AcqZ Activity (gCi) X 50 AgZ flow rate X Total Sample Time (cc/min) (min)
2. Calculate the stack activity for both Shield Building Vents and record results on PINGP 784.

'-:- A correction factor of 50 is used to adjust for sample line NOTE: - I plate out of iodine.

N. If particulate activity is calculated; a correction factor of 3 is S, :p%*

  • used to adjust for sample line plate out of particulates.

5.2.4 If radioactive effluents are being released from more than one release point, then determine an activity concentration and flow for each release path and input each into MIDAS dose calculations or calculate one weighted average concentration and total flow and input into MIDAS dose calculations. See PINGP 784 for calculating weighted averages.

Page 8 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

DETERMINATION OF RADIOACTIVE F3-20 RELEASE CONCENTRATIONS I

REV: 181 Figure 1 STEAM LINE MONITOR DOSE RATE CONCENTRATION CONVERSION FACTOR IDE VERSUS TIME FOR GAP RELEASE 0 - 24 HOURS 10 3


--- - -- - - - - - - - - -3 o------- ------ - ---


IDE: microcupes/cc of XE-133---- ---

. . mR/hr - .. . ..

1 L- -3 .- ~-----

  • i L--------------...-.---------.....---

I S

  • L S

I L-- -. ------- Si ---

S------- I ------ ------- ....

- . - - ...... - -- I---J-

_----------- S S

- I S

  • S

-- --- i --- I, ------------ S ---------------- - -------- - .---- S .--

- - - - -- -- - - - -- -- - - - - -- ---- 4- -

0 0 ....... .- - - - -- - -- A - ----- a - J ------ ------ ------ ....----........... -

- -  !- I - - -  ! i -----

Si A A a .- --- .---- L-- .... I----S--.---1.---

10--------I o *"

C.) - - ----- -------------

- - - - - - - - ---------- L


- J.....--..... ----..

L i-r ~~-*-

r---------- -----

i-------

10 . . -,I r-r -r-rn-; -, -

  • - ' -r -rrr-r-r--r rrr-r r-T-r 0 2.4. 6 o 10 '12 14 16 18 20 22 24.

TIME SINCE REACTOR SHUTDOWN - HOURS Page 9 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 2 STEAM LINE MONITOR DOSE RATE CONCENTRATION CONVERSION FACTOR IDE VERSUS TIME FOR GAP RELEASE 24 - 48 HOURS 5

i0 -.------------------ - - -

0:: -------


- - - - - - ------ - -r - -

0 1

0 i -------------------------------

IDE crocuies cc of XE - 133 10 , -. , . .. ,.. .. ..--.. ..-------.. ..-. . ..--

LD ------- .- -

0 ---------------%--------. ------I------ -----

0zoE ---- ------------- ------- I------ I------- -----.-

10- --------------

10..... .-------.... .. ... ... ...


- -- . --------..--... --- ..---.. --.. - I------------- -- -- .- . . ..i..

< w OL

z C 0 ,, ,-, T 1 *. ",.- -- ,  ;.. ,. . .

L.i 0

ck-n 10r * -------- I,- rr-r r-a---- --1 rI--- T --- -- I----

0 24 26 28 30 32 34 36 38 40 42 44 46 48 TIME SINCE REACTOR SHUTDOWN - HOURS Page 10 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 3 STEAM UNE MONITOR DOSE RATE CONCENTRATION CONVERSION FACTOR IDE VERSUS TIME FOR GAP RELEASE 0 - 7 DAYS 106 S.. ...-. . .-..---

.** .t* . .. .. .. . -

. *f.JL.

. .ft ... J . f. .J.L . .5.. . . ... UJ. U..f.t.J.. t L~~J... 7Ct'.

f. . f. . .I. .

.t. .t.f~tff~ .*t .. .. . ...... ft.

.. 4 C) 0 It /. ..................

Ll.

Z: 10~

0

, ~~ ~

ft:f. t .

Zt. . .

. . . ...... f f..

f 10 0 0" ft.......... .. f.......f 0<C-) --.a - . --. ~~

.. 4 o .~.f.

< -) S n-rn-r-or f

444 tf . . .* . .

-v . . . . . . . . . .. t . .

z~101 J.

f....................

qLJj _:_ _q.

_p.1A~J. _pLLJ..JLj~p

_ _j L_,_ r L.LJ.k..A f

QLai f... ftI.J.,_... ftI.ft.I ti i j.ftf.D t e1 I if,.Jft e 4* o II o: I .. t ft. ,,,ft..ftftft I ftl _L.~.f t ft,..

0

":7"

'AZ Inz

. ft.t._S.Jt...L.

1r .. tA.LS.J.L.ft.ft...

IL! 4444-:444-.

~*

r

  • r4* I Ii °r"* "- T.. 1-d1T L J 0 rrTiTir r -ri-
  • , . S
  • I ft ,

101 I 3 5 6 7 2

TIME SINCE REACTOR SHUTDOWN - DAYS Page 11 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 4 1 R22 & 2R22 CALIBRATION CURVES 1E+6 1E+5 1E-+4 a

I 0c~r I0 z

0 C- 1E+3 1 E+2 IIII IIIn III 1E+1 1 E-7 1E-6 1E-5 1E-4 1E-3 1E-2 1E-1 1E+O CONCENTRATION - uCi/cc XE133 Equivalent Page 12 of 18

PRAIRIE ISLAA*D NUCLEAR GENERATING PSLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 5 I AND 2 R-50 CALIBRATION CURVE 1E+8 1E+7 1E+6 IE+5 E IE+4 lLfJ IE+3 D

1 E+2 1E+1 1E+0 1E-1 1E-2 IE-1 1E+O 1E+1 1E+2 1E+3 IE+4 1E+5 1E+6 CONCENTRATION uCilcc Xe-133 Equivalent Page 13 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 6 SHIELD BUILDING STACK MONITOR SAMPLE CHAMBER MONITOR POINTS TELESCAN or EXTENDER - End of probe against or RO-20 RO-2A - Bottom of meter chamber at designated point. against side.

Page 14 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT 'EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

X DETERMINATION OF RADIOACTIVE F3-20 Fk +'+,*'-; RELEASE *REV: CONCENTRATIONS 18 Figure 7 PORTABLE METER VERSUS STACK GAS CHAMBER ACTIVITY 10 ------


4 I gig I * * * **I1*I S *

  • i*l* l IS IS I 1 I g S 5555¶11 I I I .IllI. SI aR ii. I S

.... *I..V.

I

.. . ... 5 4 *

5) I

.. I5 y -.

i II*

. . . ... , , , ,,, f , , ,,,,,I , *,,,, ,. . . .

q_ 10 . -------- ---- ------------ 14H-Z -2'

.**.* 10 ':., S . S -~ ---IS

  • IzZ'-+....* *S.2:.-  ::Z,,+Z

,.Z.t':I .- a.,*-. *.*....[.. .... *..*.......

10--- ------ ig .i

~:~z~: ------------- -- - S *r

  • al~ I l .4 I
  • Ii lg ll SIa S Sl 11. I1 I ll l

,.iA ------- ~{

. . k... L.. . . I .. a...J.J - - - A- - I--. . .. ..

  • I I *II * *SgS*lll I S I I llaS I SISII Ii I 5
+-- * -.... - ----

- - - - - - - - - -- +]...

A- : - J V )

,,L a L.

-- Lk..*.

1a d...

~-i ..L J. . .. . L 1i JI J-

-J J a-. -. .J

- -J~

.J.a j-J

........ /

  • ~~
  • I**a.

5**


~ , ....... ..

I ..V . .... ; + .* .. .. 4 .. .+ 0' + .) - . . . . . - *- . . . . .- -- " 3..J CONCENT

-... *....RATION *-- .. /.... XE+-' -133... EQUIVALENT" "::*2*-"."

C

/0210-11 T ....

10 XE-133 1

EQUIVALENT 12 0 T..... ,......L:z I ...........

....... ... .. Page...15...of..18 10 i'"4-,Ji-.ir,.r'4 J~ '.SIlfl4.. . a.I-

-. 1.t.Pag 15 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES

' . . tT-- NUMBER:

DETERMINATION OF RADIOACTIVE

,! ,: *RELEASE CONCENTRATIONS REV: 18 Figure 8 GROSS IODINE CURVE USING RM-14 WITH 2" GM PANCAKE PROBE WITH SILVER ZEOLITE ADSORBER 6

10 POI IONIPONBiE ~ it C)... ~il ~ lTCT~ ~ L..,J.m ~ - ~- -

~-. ~ - - -....... , ,a.,: . . ...

L.JII r..... . P ......

T..

i l i i i

iI

.4. - . .

F3,IiI)I, H 3

.ri. ._*t_

3,

+/-

-I -Ii

-,i-i-i v

[ -..

  • OITO ,ROBE'  :;:11 I i
1ra '

r f

1'....---

i ir

<--10' o........-

- n...A...-J..-

L..

JA 4-1......

z- ,.,- - .- . - . -**-- .. - *!I - R -R - -

Z La] -. . ...- F --- , -.. ----------


r .-.

r.-------a- - -.-

i I II I i *.a* I a I jI I l I,. l I w) 1 .-..-....- --- ----.--- , ..-..... 1-- T

- 0* i I ll--1--A A *L~~~~~A-------- - - t -11 J-- - 4-4 1*_-- - .

1 .... ...... 4 .... - *.
  • 2 *.. j

............ ) . J... J.L.i-t....L**-z.aLz ..

I *. a i t.iIi g* i*i ..l

  • l *
    • 9 II j * *
  • I *a Ig I *a Ial a I i l

..--- 4- -- - -

0-.

. . . . .a/, .

, .. /.*

.. I.......t..4.tkJA&. 4....'

. S ai .. .I

_'.'J l..*:J... J....... J... *

a. . .. .. . . .  : :  :.. . . ' .... . . . .... *:' 1

..... * ... 1- --- ---- *-- - -..... . .- ,,.,

-- *..4 .. I.

i0 3 10-2Z 10- 1 10 0 10 110 TOTAL ACTIVITY ,..t.Ci ON ADSORER Iodine Page 16 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 9 IODINE ADSORBER ACTIVITY VERSUS COUNT RATE RM-14 PANCAKE PROBE AT 12"'

-S-----i 5-,-fl -

10 ..----- .


.L

  • --a---------
  • 4.*
  • S S 5 55 ha i S S 5 i i *--------r5
  • , 5 5 5 *s5
  • S S 5 5555
  • a 5 5
  • i
  • S
  • S 5 5 * , 5 *-J........ .i...k...L...
  • 5 5 55555
  • . S
  • 5 5 5.5.
  • S 5 5 5 *S

.* ..... .. .*. .i* .,Sj . * -1..

5 5 5 S5Ss

- 5 5 5 515S -

  • S
  • S 5555 5

5 5 5 5 5.5.

  • a -
  • Is Sr

.5 5 5 55555

2 , .
  • 5555 p
  • 5 5 5 555, 10 4 I I S 5 i 1

. i 5 5 5555i

  • a
  • 5555 i S
  • 5 5 5 5s55
  • 5 5 5 5555

--- - -------- 55:

  • S 5 5 e e
  • 5 5 5 5555
  • 5 s S S
  • 5 5 55555 i ! i i lili
  • . *5
  • j * . 5 .5555 S* S S Li
  • S i
  • S I ---- ----------

- *- - - -- S -

o , - 5i

-*J "- ............ .4 --- -------- ----

-- ---5 -- -- --. -. -I

-t .i.5 -2 10 , ,rS *-- S, LI 10 0

... . *S...

. . - S.

-,. ., iS _. 5 - 5 S i i o l :s .  ; , a 5*l z S... . ... 5 55.i

.p

'*' ' .' f . ..... p*'.. 5 .t Sl.q y . ....... . 5*-

£..-J-------.---

...----- " 5- r5. . 5.5 0 0-------

-- * . 5 5 5 5

  • 5 **si i I I i5 s i i' i 3-- --- ---------- s a SIo i5

- - -- - - - - 1 i  : a 5 5 5 5

- ----- -- *~ --- I5 - - - - - I -

. . j - -

.5..... ' :s.... J I5

  • 5 5 5I 5555 5 5 I 5 55i.55
  • a p LJ 0 ..... ..*v ',*-*

-. **--t.

.5.x S....J

.t.

5,1l5

.4.s 1

S,* *s i i S

5 5 S~

l 5.5 i

5I I

5555. .

ii

,5 i5 0 *SI 55 5

5 5

5 5

S 5

s l il l

I I S

9 S

55555 S *5sI

.. . *.. 5. . S S.*

S i

S S

S... . S.

S S

S S I 5 5 5

  • S
5. 5..

5 S

555

.5.

I

.5.

I **

5

i. .:~-

)

  • S&---I------..J--------

, Is S

s 55555 S

S 5s5 i

.5, 10 .. . , .. S.....n- ,

100 10* 1010 TOTAL ACTIVITY ON ADSORBER jCi Iodine Page 17 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 10 IODINE ADSORBER ACTIVITY VERSUS DOSE RATE DOSE RATE METER AT 12" IU,

.. t--r-.l*;:. .. . .,k- A.L ,.,~::..----!"

- "---'j- , .*  !' i .- .-: .: --'73 .:,iI - 3".!,

  • -4 r . .7 *. Z- : ="-,

.... ..' -..,- "X,.-,o1r i IU - - TA - T

-- -- +/-.....

17 Lk- ... JJ 0 ..-- 4-.--! J .. ... 4- .J-rtJJJJ 1, 1 ,Tr ,4-0 II I 5I I i** i gt * ,

  • i,CsIi C ' I III
  • II I CI
  • 155i I I C I IC IllS m Ip C II SI I
  • C i ICI
  • I I IgI, II Il 10
  • C crI I r.+/-rr;1 .I I i 5 i----------- - -r- - - hI C .- DrT, JJ.trj. -:rl .

S... ........... J J .. ..-...

. *.. . r I, Ia a.,

  • .. , S' .'"11.1 . .. 5**""r3 '1 . . . ." t- *,r* . ."' 1 "** %"CC I

.... .

  • I * ..* t I
  • CI CgI
  • C
  • 5 IgSl
  • I I, II ls
  • I I, [* I i
  • I I i ISIIj

--414~

-- 2 11 - *

  • I aIIii St ll ll I I

-4 I

  • I i I I

I i I ,

Ii l

  • I I I I7,-rnIi 1
  • C 1II
  • I lilll a' l ll I I IlIi I g C pg *+,i

. LT.JJ *.. .... ,. .3 I *. . . .j.  :. ; .. - _ * , I I I cr, Iii 1,i1 -

LUI

  • C5,

.. '.I


.-------C C 1 I .1::

2 -----:--4----4 i I .1 I .*

  • I aa pI C 9
  • I I i IiI F-: * ~r * **,* ------ C--- ---- I I I I p IF .II III a I
  • I.I ., S I .SI *I I I i ItII oc
  • p t S Fi*I

-*4 . . -+ -, -. . . . . ' " -'.. ....

4- -,*..-....

  • I 5.119 I1 a--- *--- - 4-

.~ . z.... -t - k L.. . . . -- ... . . . . ... [ . . . . ..

I p

  • C i .

C hitII l

i C S

  • I .** I
  • I I I I III Si F

I CI ii i I C

.I C *

.i C

C

. C i

  • SC 5

tI I

Ol C

1 I

g 1.1,I CIIII 1

  • 5 I .I II I
  • I.II l 1

TL. ..... It - "-'* fl.. ..& . .~I .W .. .J..... 4. . .. L... F I i I j Ii

.......... .-... ..... ..... ... t ---A........... °t. .. . . . . . Is I *

  • S I
  • FI~ II O11 k... .. L. . ....-.- I......., *4 I
  • IC C I *5* I

,1151 i I II

I , : '.,
  • C I ,C1 I . . "',F... C,"' . .. . " C'r a". "'~ -. 1,'

l.-,*~.#iI " . " 1 .1, 101 102 1( S TOTAL ACTIVITY ON ADSORBER /yCi Iodine Page 18 of 18

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE REFERENCE USE-`

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be availableat the work location.

O.C. REVIEW DATE: FJv Iwi.'- EFFECTIVE DATE I M. Werner Page 1 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 1.0 PURPOSE This procedure provides guidance for responding to a credible security threat by the plant staff resulting in a declared emergency.

2.0 APPLICABILITY This procedure SHALL apply to the duty Shift Manager (SM), Shift Supervisor (SS),

Plant Manager, Emergency Director (ED) and plant personnel during a credible security threat. Specific Security Force actions and responses are described in the Safeguards Contingency Plan and procedures.

3.0 PRECAUTIONS If a bomb or sabotage device is found, 3.1 Personnel should remain at a distance of 300 to 500 feet, if possible, from the device.

3.2 The person discovering the device SHALL NOT touch or disturb it.

3.3 Hand-held radios should not be operated within a distance of 50 feet from the explosive device.

Page 2 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 4.0 RESPONSIBILITIES 4.1 The Plant Manager or designee has responsibility to assist the Shift Manager during a plant security event.

4.2 The Operations Shift Manager has responsibility for safe operation of the plant and initiation of the Emergency Plan during a plant security event.

4.3 Operations Shift Supervisor has responsibility for plant operations and assessment of operational aspects of the emergency.

4.4 Superintendent Security/designee has responsibility to implement the Safeguards Contingency Plan during a security event and support the Operations Shift Manager as necessary.

4.5 Shift Emergency Communicator (SEC) has responsibility to assist Shift Manager in performing notification during security threats.

4.6 Shift Chemist has responsibility to perform responsibility of the SEC when the SEC is NOT available.

5.0 GENERAL INFORMATION 5.1 Definitions 5.1.1 HIGH Threat Severity - The threat of physical attack to the plant represents a potential, substantial degradation of the level of safety of the plant.

5.1.2 LOW Threat Severity - The threat of physical attack to the plant represents a potential degradation of the level of safety of the plant.

5.1.3 Non-Credible Threat - Information assessed as offering no reasonable basis to quality as credible.

5.1.4 Security Threat - Any notification from any source which is received at the site or the corporate office which could be considered as a threat to the safety of the site whether considered credible or not.

Page 3 of 11.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 5.2 Discussion Once a security threat (i.e., bomb threat, adversary threat, etc.) is determined to be a HIGH credible security threat, the definition of an ALERT is met and an ALERT should be declared per F3-2, Classifications of Emergencies.

Once a security threat (i.e., bomb threat, adversary threat, etc.) is determined to be a LOW credible security threat, the definition of a NUE is met and a NUE should be declared per F3-2.

The duty operations Shift Manager remains in charge of the overall plant response to the security threat with assistance from Plant Security, Operations, Local Law Enforcement Agencies (LLEA) and Nuclear Management Company (NMC) staff.

If changing security or plant conditions warrant escalation to a higher emergency classification, the Shift Manager is responsible to authorize the escalation.

Implementation of Emergency Plan procedures during a security event may need to be modified, depending on the event, in order to protect the safety of plant personnel, vital equipment, or protect the health and safety of the public.

6.0 PREREQUISITES 6.1 A credible security threat exists and; 6.2 A Notification of Unusual Event (NUE) or Alert has been declared.

Page 4 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 7.0 PROCEDURE 7.1 The Plant Manager or designee should go to the Control Room to assist with communications.

7.2 The Duty Shift Manager/Shift Supervisor should ensure the following activities are performed or considered:

7.2.1 IF a bomb device exists, THEN ensure the following message is broadcasted over the-plant P/A system:

INOTE.-

NOTE.:During

,:, I; drills, the announcement

-** ,"THIS IS A DRILL".

should begin and end with "ATTENTION ALL PLANT PERSONNEL. ATTENTION ALL PLANT PERSONNEL.

"A BOMB MAY EXIST IN THE AREA."

(specify area)

"STAY CLEAR OF 1' (specify area)

Repeat message after about ten (10) second interval.

Page 5 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGE:NCY PLAN IMPLEMENTING PROCEDURE 7.2.2 IF an Alert has been declared, THEN:

The Alert classification was declared based on a HIGH credible security threat. Site personnel are to be placed out of harms way as soon as possible. The Backup Emergency Operating Facility (EOF) and Joint Public Information Center (JPIC) are to be staffed and activated to support offsite communications.

A. Assume the position of Emergency Director in absence of Plant Manager or other Emergency Director designee.

B. Ensure the following PA announcement is completed:

SNOTE:*"** * ,During drills, the announcement should begin and end with

. THIS IS A DRILL".

"ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL. A SECURITY THREAT EXISTS.

PLACE ALL ESSENTIAL ACTIVITIES IN A SAFE CONDITION.

ALL EOF PERSONNEL ASSEMBLE AT THE BACKUP EOF.

OPERATIONS PERSONNEL, FIRE BRIGADE PERSONNEL, AND DUTY CHEMIST ASSEMBLE IN THE CONTROL ROOM.

ALL OTHER PERSONNEL LEAVE THE SITE AND GO HOME."

Repeat announcement after about ten (10) second interval.

C. Direct the Shift Emergency Coordinator (SEC) to:

1. Perform offsite government notifications per checklist PINGP 580, Emergency Notification List for an Alert, Site Area, or General Emergency. (Shift Chemist use PINGP 1465, Shift Chemist Emergency Notification Call List for a Security Event.)
2. Activate EOF personnel to staff Backup EOF and JPIC personnel to staff JPIC per checklist PINGP 580 (Shift Chemist use PINGP 1465).

Page 6 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE D. Ensure NRC is notified of Alert (PINGP 666, Event Notification Work Sheet).

E. Follow-up Threat actions:

1. Coordinate with Emergency Manager, to designate appropriate plant representation at the LLEA command center to provide site facility and plant operations advice to the LLEA.

Ongoing management communication will take place from the Backup EOF.

,,NO TE:. I The hub for security communication will be the NMC Hudson

. Security Command Post at (715) 377-3353.

2. Determine and execute appropriate procedures to place the plant in a condition that will minimize the potential consequences of execution of the anticipated or occurring security threat.
3. Consider terminating high-risk or special operations that may be in progress (e.g., refueling, resin sluicing, etc.).
4. In the case of a credible bomb threat, consider shutting down the plant with due consideration for out-plant operator safety.
5. Coordinate with Security and LLEA to determine an appropriate response to the security event.
6. Keep plant personnel clear (if possible, 300 to 500 feet) of the affected areas if their personal safety is at risk.

Page 7 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE

7. After security "all clear" is given, ensure all appropriate emergency plan actions in PINGP 1125, Control Room, Shift Manager/Shift Supervisor Emergency Director Checklist are being completed with due consideration for personal safety and security considerations as appropriate.
8. IF threat results in plant damage and security threat still exists, THEN continue to assess conditions.
9. IF threat results in plant damage and security risk to personnel no longer exists, THEN:
a. Activate remaining ERO per PINGP 1384, Emergency Response Organization Activation for Non-Security Event.

AND

b. Evaluate EALs per F3-2.
10. IF threat is resolved, THEN terminate event per F3-2.

7.2.3 IF a NUE has been declared, THEN:

The NUE classification was declared based on a LOW credible security threat. Site personnel are to be placed out of harms way as soon as possible. The Backup EOF and JPIC are to be staffed and activated to support offsite communications.

A. Assume the position of Emergency Director in absence of Plant Manager or another Emergency Director designee.

B. Ensure the following PA announcement is completed:

Page 8 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE IN'*J* *t  ;.;**

  • During drills, the announcement should begin and end with
  • '-,;,,
  • f "THIS IS A DRILL".

"ATTENTION ALL PERSONNEL. ATTENTION ALL PERSONNEL. A SECURITY THREAT EXISTS.

PLACE ALL ESSENTIAL ACTIVITIES IN A SAFE CONDITION.

ALL EOF PERSONNEL ASSEMBLE AT THE BACKUP EOF.

OPERATIONS PERSONNEL, FIRE BRIGADE PERSONNEL, AND DUTY CHEMIST ASSEMBLE IN THE CONTROL ROOM.

ALL OTHER PERSONNEL LEAVE THE SITE AND GO HOME."

Repeat announcement after about ten (10) second interval.

C. Direct the SEC (Shift Chemist) to:

1. Perform offsite government notifications per checklist PINGP 579, Emergency Notification Call List for a Notification of Unusual Event.
2. Activate EOF personnel to staff Backup EOF and JPIC personnel to staff JPIC per checklist PINGP 579.

D. Ensure NRC is notified of NUE (PINGP 666).

Page 9 of 11

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERG*ENCY PLAN IMPLEMENTING PROCEDURE E. Follow-up Threat actions:

1. Coordinate with Emergency Manager, to designate appropriate plant representation at the LLEA command center to provide site facility and plant operations advice to the LLEA.

Ongoing management communication will take place from 5!the Backup EOF.

4 The hub for security communication will be the NMC Hudson Security Command Post at (715) 337-3353.

2. Determine and execute appropriate procedures to place the plant in a condition that will minimize the potential consequences of execution of the anticipated or occurring security threat.
3. Consider terminating high-risk or special operations that may be in progress (e.g., refueling, resin sluicing, etc.).
4. In the case of a credible bomb threat, consider shutting down the plant with due consideration for out-plant operator safety.
5. Coordinate with Security and Local Law Enforcement Agencies to determine an appropriate response to the security event.
6. Keep plant personnel clear (if possible, 300 to 500 feet) of the affected areas if their personal safety is at risk.
7. Ensure all appropriate emergency plan actions in PINGP 1125 (SM/SS ED Checklist) are being completed with due consideration for personal safety and security considerations as appropriate.

Page 10 of 11

PRAIRIE ISLAND NUCLEAR GENERATING P-LANT EMERGENCY PLAN IMPLEMENTING PROCEDURE

8. IF event results in plant damage, THEN reclassify per F3-2 and go to Alert section of this procedure.
9. IF threat becomes a HIGH credible threat, THEN reclassify and go to Alert section of this procedure.
10. Coordinate with EOF Manager to assess personnel needed in the EOF and release unnecessary EOF and JPIC personnel.

Personnel needed to support essential activities should t'r; * 'i remain at work or be called back in. All other personnel NOTE:

  • should go home. Inform such personnel of the de**termination through management channels.
11. Coordinate with NMC headquarters management personnel and determine what essential activities should proceed.
12. IF threat is resolved, THEN terminate event per F3-2.

Page 11 of 11