ML090960318

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Independent Spent Fuel Storage Installation - Changes to the Emergency Response Plan and Implementing Procedures
ML090960318
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 04/01/2009
From: Speer S
Constellation Energy Group, Nuclear Generation Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ERPIP-303, Rev 9, Change 4, ERPIP-508, Rev 7, Change 0, ERPIP-511, Rev 12, Change 4, ERPIP-822, Rev 4, Change 3
Download: ML090960318 (121)
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Text

.Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Marylafid 20657 Constellation Energy-Nuclear Generation Group April 1, 2009 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 Independent Spent Fuel Storage Installation Docket No. 72-8 Changes to the Emergency Response Plan and Implementing Procedures As required by 10 CFR 50.54(q), 10 CFR Part 50 Appendix E.V, and 10 CFR 72.44(f), changes to the Emergency Response Plan and Implementing Procedures are enclosed. These changes do not decrease the effectiveness of the Emergency Response Plan.

Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219 or Mr. Steven C. Speer at (410) 495-5216.

Very truly yours, Steven C. Speer Director - Emergency Preparedness SCS/RDW/bjd

Enclosures:

ERPIP-303, Revision 9, Change 4 ERPIP-822, Revision 4, Change 3 ERPIP-51 1, Revision 12, Change 4 ERPIP-508, Revision 7, Change 0 cc: S. J. Collins, NRC Resident Inspector, NRC E. W. Brach, NRC (Without Enclosures)

D. V. Pickett, NRC S. Gray, DNR &I pt6s 61 14 Y,41-ýs P,2 r--r N

Constellation Energy, Calvert Cliffs Nuclear Power Plant TECHNICAL PROCEDURE ERPIP-303 RADIATION PROTECTION DIRECTOR Revision 00904 Safety Related CONTINUOUS USE Applicable To:

Calvert Cliffs Nuclear Power Plant Approval Authority:

Plant General Manager

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 2 of 25

SUMMARY

OF ALTERATIONS Revision Change Summary of Revision or Change 009 00 Changed ERO positional titles where necessary to support closure of AF200200004, Nos. 002-008 to ensure ERO position titles are consistent among Emergency Preparedness program plans and procedures.

Added 6.2.B NOTE indicating that the PGM, GSNO, and Center Directors are to be made aware of KI being dispensed. This requirement was also placed in page 2 of Attachment 6, Potassium Iodide Issue.

Added names of personnel authorized to dispense KI to Page 2 of Attachment 6, Potassium Iodide Issue.

009 05-054 Editorial Correction to:

  • Replace reference to "Site Emergency" with "Site Area Emergency" to reflect new EP action level designation.
  • Replace reference to PR-3-100 with CNG-PR-3.01 -1000, Records Management, to reflect replacement of site procedure with new Fleet procedure.
  • Step 6.1.C NOTE: Add that Radiation Protection Director's logbook may be kept electronically (additional information)
  • Update Radiation Protection titles where necessary throughout procedure.
  • Step 6.2.A.1.c NOTE and 6.2.A.1.c(1): Insert additional information regarding the Radiation Protection Director's ability to delegate certain actions.

009 02 Editorial Correction to perform the following:

0 Step 6.2.A.2: Insert additional information for greater clarification in obtaining Meteorological Data.

  • Step 6.2.A.8: Update EP title of person giving briefs to response teams on radiological conditions and requirements.
  • Attachment 5: Update EP title in NOTE (b).
  • Attachment 6: Update EP title for "Approved by" and removed individual names that are authorized to dispense KI and replaced with the actual position title.

009 03 Editorial Correction to perform the following:

  • Add step 6.2.A.8 and 6.2.A.9 to ensure Offsite Monitoring Team is informed when Emergency Work Permits are initiated.
  • Add Note to Step 6.2.A.6 to request a RADDOSE dose prediction map from the RAD at the EOF. This is to ensure that the plume direction lines up between both onsite and offsite plume teams.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 3 of 25

SUMMARY

OF ALTERATIONS (Continued)

Revision Change Summary of Revision or Change 009 04 Editorial Correction to perform the following:

0 Procedure reformatted to the new template per the requirements of CNG-PR-1.01-1005, Control of Constellation Nuclear Generation Technical Procedure Format and Content.

  • Changed Section 3.1.6 from PR-1-101, Preparation and Control of Calvert Cliffs Technical Procedures to CNG-PR-1.01-1005, Control of Constellation Nuclear Generation Technical Procedure Format and Content.
  • Changed Section 3.1.7 from PR--1103, Use of Procedures to CNG-PR-1.01-1009, Procedure Use and Adherence Requirements.

PR-1-103 is no longer used.

0 On Attachment 6, Potassium Iodide Issue, Page 2 of 4, removed names of those allowed to issue KI. Only list authorized positions.

RPA # 2009-0233

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 4 of 25 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 P UR P O S E .................................................................................................................................. 5 2.0 A PPLICA BILITY/SC O PE ........................................................................................................ 5

3.0 REFERENCES

AND DEFINITIONS ........................................ 5 3.1 Developm ental R eferences ............................................................................................. 5 3.2 Performance References ................................................... 6 3 .3 D e fin itio n s ....................................................................................................................... 6 4 .0 P R E R E Q UIS IT E S ...................................................................................................................... 6 4.1 Training and Qualification ......................................... 6 4 .2 Initial C onditions ..................................................................................................... .. 6 4.3 Docum entation and Support ....................................................................................... 6 5.0 PRECAUTIONS ........................................................................... 6 6.0 P E R FO R MA NC E .............................................................................................. .................... 7 6 .1 A ctiva tio n ......................................................................................................................

6 .2 O p e ratio n .......................................................................................................................... 8 6 .3 Deactivatio n ........................................................................................ ......................... 14 7.0 POST-PERFORMANCE ACTIVITIES ................................................ 15 8.0 BASES .................................................... ......... 15 9 .0 R EC O R DS ............................................................................................................................... 15 ATTACHMENT 1, EMERGENCY RESPONSE FACILITY MONITORING STATUS ......................... 16 ATTACHMENT 2, PROCESS AND AREA RADIATION MONITORS (RADIATION MONITORING SYSTEM) ................................................. 17 ATTACHMENT 3, PAGS FOR THE EARLY PHASE OF A NUCLEAR INCIDENT ........................... 19 ATTACHMENT 4, GUIDANCE ON DOSE LIMITS FOR WORKERS PERFORMING EMERGENCY S E R V IC E S ........................................................................................................ . . 20 ATTACHMENT 5, ONSITE EVACUATION CRITERIA ........................... ..... 21 ATTACHMENT 6, POTASSIUM IODIDE ISSUE [B2367] ............... ............... 22

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 5 of 25 1.0 PURPOSE This procedure provides emergency response instructions to Radiation Protection Director during the following events:

  • Alert 0 Site Area Emergency 0
  • General Emergency 2.0 APPLICABILITYISCOPE 2.1 This procedure applies to the Radiation Protection Director.

2.2 Performance of this procedure is in the order of Activation (Subsection 6.1), Operation (Subsection 6.2), and Deactivation (Subsection 6.3)

3.0 REFERENCES

AND DEFINITIONS 3.1 Developmental References 3.1.1 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency response Plans and Preparedness in Support of Nuclear Power Plants 3.1.2 10 CFR 20, Standard for Protection Against Radiation 3.1.3 10 CFR 50.47, Emergency Plans 3.1.4 10 CFR 50 Appendix E to Part 50, Emergency Planning and Preparedness for Production and Utilization Facilities 3.1.5 Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.1.6 CNG-PR-1.01-1005, Control of Constellation Nuclear General Technical Procedure Format and Content. 0 0) 3.1.7 CNG-PR-1.01-1009, Procedure Use and Adherence Requirements.

3.1.8 Technical Procedures Writer's Manual

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 6 of 25 3.2 Performance References 3.2.1 Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.2.2 CNG-PR-3.01 -1000, Records Management 0) 3.2.3 ERPIP-901, Communications Equipment 3.2.4 ERPIP-B.1, Equipment Checklist 9LO 3.3 Definitions None 4.0 PREREQUISITES 4.1 Training and Qualification Personnel performing this procedure shall be qualified on the tasks or activities contained in this procedure.

4.2 Initial Conditions One of the following emergency action levels is called at Calvert Cliffs Nuclear Power Plant:

  • Alert
  • Site Area Emergency o*

C)

  • General Emergency o 4.3 Documentation and Support Forms needed to implement this procedure are contained as attachments to this procedure.

Forms may be computer generated or revised without requiring a change or revision to this procedure, providing the intent is not changed, and the required information is not deleted from the existing form.

5.0 PRECAUTIONS Declared pregnant women and minors are not authorized to perform emergency functions.

.t

RADIATION PROTECTION DIRECTOR ERevIPion0090 Revision 00904 Page 7 of 25 6.0 PERFORMANCE 6.1 Activation 6.1.1 REPORT to the Operational Support Center on notification of Alert, Site 0)

Area Emergency or General Emergency. 0) 6.1.2 NOTIFY Operational Support Center - Director of your presence in the Operational Support Center.

NOTE User controlled plant procedures are available in the OSC. If additional copies are needed, they may be obtained from Electronic Procedures Management or NORMS Imaging. Copies reproduced on available copy machines should be verified for current revisions and changes.

C) 0 The Radiation Protection Director's logbook may be kept electronically. C) 6.1.3 OBTAIN procedure(s), Radiation Protection Director Logbook AND administrative supplies from the equipment locker.

6.1.4 SET UP the Radiation Protection Director work station.

6.1.5 IDENTIFY personnel filling the following positions:

NOTE Dosimetry Team Leader may report to the 72' Auxiliary Building Access Control Desk for an Alert. The Dosimetry Team Leader will contact the Radiation Protection Director when on station. For a Site or General Emergency, the Dosimetry Team Leader reports directly to the Operational Support Center.

1. Dosimetry Team Leader
2. Onsite Monitoring Team Leader
3. Emergency Work Permit Coordinator
4. Operational Support Center/Nuclear Security Facility Monitor and Control Room/Technical Support Center Monitor
5. Support Staff

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 8 of 25 6.1 (Continued) 6.1.6 ASSESS plant conditions by review of center status boards or by a briefing

-from Operational Support Center - Director.

1. CONSIDER contacting the Interim - Radiation Protection Director (that is, the on-shift Radiation Protection Technician) for situation update. 04 C) 6.1.7 INITIATE the Radiation Protection Director's log of significant events.

6.1.8 NOTIFY the Operational Support Center - Director of position readiness.

NOTE The actions in Subsection 6.2, Operation, steps 6.2.1 through 6.2.3 may be performed in any order and only appropriate actions implemented considering the situation.

6.2 Operation 6.2.1 PROVIDE guidance and supervision for onsite radiation protection and

-exposure control.

NOTE Meteorological data is available on the Radiation Protection Director's computer.

1. ASSESS radiological conditions.
a. REVIEW Radiation Monitoring System data regularly.
b. REQUEST radiation and contamination survey reports from the Onsite Monitoring Team Leader.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 9 of 25 6.2.1 (Continued)

NOTE 0)

The following task maybe delegated. C0

c. RECEIVE radiological monitoring input from emergency center monitors (Control Room/Technical Support Center and Operational Support Center/Nuclear Security Facility).

NOTE 0)

The following task maybe delegatedC (1) MAINTAIN status on Attachment 1, Emergency Response Facility Monitoring Status.

2. OBTAIN Meteorological Data from the Meteorological Data terminal in the OSC (this may be delegated). CD
a. EVALUATE needed meteorological data, as specified in ERPIP-825, MeteorologicalData Acquisition Methods.
3. PROVIDE radiation protection coordination and support to Operational Support Center - Director.
4. ENSURE in-plant radiation monitoring is accomplished.
a. REVIEW the scope of radiation and contamination surveys with the Onsite Monitoring Team Leader.
b. ASSESS plant conditions to determine required surveys.
c. IF practical, THEN VERIFY alarms from permanently installed radiation monitors.

(1) Attachment 2, Process and Area Radiation Monitors, lists radiation monitoring system process and area radiation monitors and their locations.

d. DIRECT the Onsite Monitoring Team Leader to dispatch monitoring teams as the situation warrants.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 10 of 25 6.2.1.4 (Continued)

e. RECEIVE in-plant and onsite dose rates AND air sample (gaseous and particulate) survey results from monitoring team leader.
f. REVIEW monitoring team survey results AND actions.
5. MAINTAIN radiological access control in-plant AND onsite.
a. SET UP access control points as the situation warrants.
b. NOTIFY Team Leaders and Security Liaison of site access control point location(s).
c. FOLLOW ALARA principles.

WARNING Failure to emphasize the importance of pre-established access routes may result in ALARA principles violation.

d. ESTABLISH access and egress routes for site personnel as situation warrants (use Operational Support Center controlled prints,62-140 series, Post LOCA Dose Rates).

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 11 of 25 6.2.1 (Continued)

NOTE Information effecting offsite dose projections (such as plant conditions, system 9 to operation, or event classification(s) need to be forwarded to the Radiation Assessment Director (RAD) at the EOF as soon as possible. The following are examples of specific information needed by the RAD [B1148]:

- Chemistry sampling status/analysis

- Source of leak/release and path

- Verified dose rates on-site

- Time to stop leak/release (that is, fix valve, plug hole, and so forth)

NOTE A RADDOSE dose prediction map should be requested from the RAD at the EOF to ensure correct plume release.

6. DETERMINE actual or projected dose rates in-plant/onsite.
a. Attachment 3, PAGS Forthe Early Phase of a Nuclear Incident, and Attachment 4, Guidance on Dose Limits For Workers PerformingEmergency Services, lists protective action recommendations. These recommendations are for planning purposes. Protective action decisions at the time of the incident must take existing conditions into consideration and are based on Attachment 5, Onsite Evacuation Criteria.

(1) REASSESS dose rates throughout the emergency.

(2) ADVISE the Operational Support Center - Director, LOl Plant General Manager AND Emergency 00, Director/Recovery Manager on in-plant/onsite protective actions.

7. ENSURE proper personnel exposure control.
a. SELECT AND ISSUE respiratory protection.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 12 of 25 6.2.1.7 (Continued)

b. AUTHORIZE entry into areas with exposure rates greater than or equal to 10 R/h ifjustified.
c. APPROVE planned exposures in excess of 5 REM ifjustified.
d. AUTHORIZE jointly (with the Emergency Director/RecoveryO Manager) ifjustified.worker doses in excess of 10CFR20 emergency annual limits 9o
e. AUTHORIZE ANDIOR MODIFY Emergency Work Permits as needed.
f. AUTHORIZE continued use of interim Emergency Work Permits AND current Special Work Permits as needed.

CNJ

8. INFORM Radiological Assessment Director when Emergency WorkoM 0

Permits have been initiated.

9. PROVIDE copies of the Emergency Work Permits to Offsite Monitoring Team Leader at the EOF. M1
10. ENSURE the Onsite Monitoring Team Coordinator briefs response teams on radiological conditions and requirements before their departure from the Operational Support Center (Briefings may be held in briefing areas outside of the Operational Support Center status room to minimize Operational Support Center people loading AND noise).
11. PROVIDE periodic radiological status updates to the Operational Support Center staff.
a. COORDINATE with the Operational Support Center-Director.
b. DIRECT team leaders to UPDATE respective teams.
12. ADVISE the Operational Support Center - Director when Operational Support Center relocation is required due to radiological conditions.

Refer to Attachment 5, Onsite Evacuation Criteria.

13. RECORD:in the Radiation Protection Director's logbook, a chronological history of significant events. For example:
a. Significant changes or trends.
b. Task request and completion information.

,). J c. Major decisions.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 13 of 25 6.2.1.13 (Continued)

d. Other significant events affecting Radiation Protection.

NOTE The PGM, GSNO, and Center Directors are to be made aware that KI is being dispensed.

6.2.2 OVERSEE use of potassium iodide for monitoring teams and plant personnel if action level is met according to Attachment 6, Potassium Iodide Issue, and if notified by Radiological Assessment Director of approval to dispense potassium iodide. [B2367]

1. NOTIFY Radiological Assessment Director of any onsite action levels met in accordance with evaluation of Attachment 6, page 1 of 4, Potassium Iodide Issue.
a. EVALUATE the preferred use of respiratory protection devices according to RSP1 -117, Issuance and Wearing of Respiratory Protection Devices Used to Protect Against Airborne Radioactivity.

6.2.3 RELOCATE if the Operational Support Center becomes uninhabitable.

1. DETERMINE the relocation route AND any applicable radiation protection measures to be taken for relocating to the alternate Operational Support Center.
2. BRIEF Operational Support Center staff members on radiological conditions AND relocation route.
3. COLLECT, to the extent possible, supplies necessary to perform Radiation Protection Director functions from the alternate Operational Support Center.
4. ENSURE Onsite Monitoring Team Leader notifies any dispatched teams of relocation.
5. RELOCATE to the alternate Operational Support Center when directed by the Operational Support Center Director.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 14 of 25 6.3 Deactivation 6.3.1 DEACTIVATE Radiation Protection Director work station when notified of event termination AND Center deactivation.

6.3.2 FORWARD records to Emergency Preparedness.

6.3.3 ASSIGN a seal source qualified individual to source check OSC instrumentation and inventory OSC sampling AND survey supplies according to ERPIP-B.1, Equipment Checklist. C C

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Paae 15 of 25 7.0 POST-PERFORMANCE ACTIVITIES None 8.0 BASES

[B2367] IR3-044-111, AIT IR200100687, clarify guidance on process for administration of potassium iodide.

[B13148] 1R200400503, Milestone #6: Provide a process tool for validating critical DAO data inputs 9.0 RECORDS Records generated by this procedure may be permanent, non-permanent, or lifetime radiological records depending on the circumstances under which they are generated.

Records shall be captured and controlled as follows:

9.1.1 During an actual event as described in the purpose statement of this procedure, records shall be considered permanent records and submitted to the Emergency Preparedness Unit for final disposition according to CNG-PR-3.01-1000, Records Management.

N C) 0)

  • Emergency Response Facility Monitoring Status C)

9.1.2 During an actual event as described in the purpose statement of this procedure, dosimetry records, that is, any dose-related record including access history records, are considered radiological lifetime records and are to be handled and maintained according to standard practices and unit procedures.

None 9.1.3 During a drill or exercise, records shall be considered non-permanent records and submitted (C) 0 to the Emergency Preparedness Unit for evaluation and retention according to 0 CNG-PR-3.01-1000.

  • Emergency Response Facility Monitoring Status

" Potassium Iodide (KI) Issue Log [B2367]

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 16 of 25 ATTACHMENT 1, EMERGENCY RESPONSE FACILITY MONITORING STATUS MONITOR NAME TIME DOSE RATE A/S RESULT TIME DOSE RATE A/S RESULT TIME DOSE RATE A/S RESULT TIME DOSE RATE A/S RESULT TIME DOSE RATE A/S RESULT TIME DOSE RATE

  • A/S RESULT TIME DOSE RATE A/S RESULT

RADIATION PROTECTION DIRECTOR ERevIPion0090 Revision 00904 Page 17 of 25 Page 1 of 2 ATTACHMENT 2, PROCESS AND AREA RADIATION MONITORS (RADIATION MONITORING SYSTEM)

1. Air Particulate Monitors (1) Unit #1 Main Vent U1-RE-5415 Room 524 (2) Unit #2 Main Vent U2-RE-5415 Room 526 (3) Unit #1 Containment Room 224 (4) Unit #2 Containment Room 203
a. Detector Scintillation 1-1/2" x 1" Nal (TL)
b. Shielding 4.5 inches of lead
c. Check Source 10 pCi Cs 137
d. Range 10E0 to 10E6 CPM
2. Radioactive Gas Monitors (1) Unit #1 Main Vent U1-RE-5415 Room 524 (2) Unit #2 Main Vent U2-RE-5415 Room 526 (3) Unit #1 Containment Room 224 (4) Unit #2 Containment Room 203 (5) Unit #1 ECCS Pump Room Vent. Ex. Room 524 (6) Unit #2 ECCS Pump Room Vent. Ex. Room 526 (7) Gaseous Waster Discharge (inline) 69' Eval. Aux.

Bldg. By U-2 Cntmt Personnel Access (8) Fuel Handling Area Vent. Ex. Room 524 (9) Access Control Area Vent. Ex. Room 526 (10) Unit #1 Waste Processing Area Vent. Ex. U1-RE-5410 Room 524 (11) Unit #2 Waste Processing Area Vent. Ex. Room 526 (12) Control Room Ventilation Supply Room 524 (13) Unit,#1 Condenser Vacuum Pump Discharge Room 524 (14) Unit #2 Condenser Vacuum Pump Discharge Room 526

a. Detector G.M. 30 mg/cm 2 Cathode Wall
b. Shielding 4.5 inches of lead
c. Check Source 10 pCi Cs 137
d. Range 1OE0 to 10E6 CPM
3. Liquid Monitors (1) Unit #1 Steam Generator Blowdown Tank Room 408 (2) Unit #2 Steam Generator Blowdown Tank Room 408 (3) Unit #1 Component Cooling Water Room 228 (4) Unit #2 Component Cooling Water Room 201 (5) Unit #1 Service Water Room 224 (6) Unit #2 Service Water Room 224 (7) Liquid Waste Discharge (inline) Room 108 (8) Unit 1 Blowdown Recovery Unit (inline) Room 227 (9) Unit 2 Blowdown Recovery Unit (inline) Room 206
a. Detector Scintillation Nal(T1)
b. Shielding 7.5 inches of lead
c. Check Source 10 pCi Cs 137
d. Range 10E0 to 10E6 CPM

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 18 of 25 Page 2 of 2 ATTACHMENT 2, PROCESS AND AREA RADIATION MONITORS (RADIATION MONITORING SYSTEM)

4. Area Radiation Monitors (1) Unit#1 ECCS Pump Rooms Rooms 118 & 119 (2) Unit #2 ECCS Pump Rooms Rooms 101 & 102 (3) Unit #1 Sample Room Room 424 (4) Unit #2 Sample Room Room 413 (5) Unit #1 Refueling Machine Service Platform Room 230 (6) Unit #2 Refueling Machine Service Platform Room 229 (7) Boric Acid Rooms Rooms 215 & 217 (8) Unit #1 Penetration Room Room 221 (9) Unit #2 Penetration Room Room 211 (10) Unit #1 Containment (4) Room 230 (11) Unit #2 Containment (4) Room 229 (12) Miscellaneous Waste Receiver Tank Room 113 (13) Reactor Coolant Waste Pump Area Room 110 (14) Waste Gas Equipment Room Room 208 (15) Decontamination Room Room 210 (16) Spent Fuel Pool Heat Exchanger Room 320 (17) Drum Storage Area Room 418 (18) Liquid Waste Evaporator Area Room 420 (19) Chemistry Laboratory Room 522 (20) Spent Fuel Pool Area Room 530 (21) Spent Fuel Pool Service Platform Room 530 (22) Unit #1 Blowdown Tank Area Room 429 (23) Unit #2 Blowdown Tank Area Room 409 (24) Unit #1 In-Core Instrumentation Area Room 230 (25) Unit #2 In-Core Instrumentation Area Room 229 (26) New Fuel Storage Area Room 533 (27) Gas Analyzing Equipment Room. Room 111 (28) Miscellaneous Waste Evaporator Area Miscellaneous Waste Evap. 69' Elev.
a. Detector G:M. 90 mg/cm 2 Cathode Wall
b. Shielding - thin sheet of lead for energy response
c. Check Source I pCi Sr 90
d. Range 1OE-4 to 10 R/Hr

RADIATION PROTECTION DIRECTOR ERevIPion0090 Revision 00904 Page 19 of 25 ATTACHMENT 3, PAGS FOR THE EARLY PHASE OF A NUCLEAR INCIDENT Evacuation 1-5 rem b Evacuation (or, for some (or shelteringa) situations, shelteringa) should normally be initiated at 1 rem.

Administration of stable iodine 25 rem c Requires approval of State medical officials.

a. Sheltering may be the preferred protective action when it will provide protection equal to or greater than evacuation, based on consideration of factors such as source term characteristics, and temporal or other site-specific conditions.
b. The sum of the effective dose equivalent resulting from exposure to external sources and the committed effective dose equivalent incurred from all significant inhalation pathways during the early phase. Committed dose equivalents to the thyroid and to the skin may be 5 to 50 times larger, respectively.
c. Committed dose equivalent to the thyroid from radioiodine.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Paqe 20 of 25 ATTACHMENT 4, GUIDANCE ON DOSE LIMITS FOR WORKERS PERFORMING EMERGENCY SERVICES 5 all 10 protecting valuable lower dose not property practicable 25 lifesaving or protection lower dose not of large populations practicable

>25 lifesaving or protection only on a voluntary basis of large populations to persons fully aware of the risks involved

a. Sum of external dose equivalent and committed effective dose equivalent to nonpregnant adults from exposure and intake during an emergency situation. Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and body extremities) to ten times the listed value. These limits apply to all doses from an incident, except those received in unrestricted areas as members of the public during the intermediate phase of the incident.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Paqe 21 of 25 ATTACHMENT 5, ONSITE EVACUATION CRITERIA cQT0'~bk' (a ICONTROLLED AR A$(gV)K Any Personnel not Personnel in Emergency Emergency Organization Organization Precautionary Evacuation Exposure Rate > 0.5 (lasting 10h) > 2.5 > 1000 (b)

(mrem/h)

Airborne3 Activity > 2.OE-10 > 2.0E-8 > 8.0E_7(c)

)

(pCi/cm unevaluated Mandatory Evacuation Exposure Rate > 2.5 (lasting 10h) > 100 (mrem/h)

Airborne Activity > 8.4E-9 (d) > 2.OE-8 > 1.OE-5 (e)

(pCi/cm3) ..

unevaluated NOTES: (a) Controlled areas may be established by the Radiation Protection Director as warranted by the situation.

(b) As deemed necessary, the Emergency Director/Recovery Manager (ED/RM) may elect to 0 use higher exposure rate based on pre-planned occupational radiation exposures.

(c) Equal to 40 DAC*h unevaluated. Respiratory protection should be used, if feasible (f).

(d) Equal to 25% of weekly exposure (unrestricted area).

(e) Equal to 500 DAC*h unevaluated (25% Annual Limit 10 CFR 20.1201).

Respiratory protection should be used, iffeasible (f).

(f) Respirator reserves:

Control Room 23 MSA 4500 SCBAs Farm Demo Building 36 MSA 4500 SCBAs Operational Support Center 5 MSA 4500 SCBAs Total 64 Air cylinder reserves:

Materials Processing Facility 135 spare cylinders Farm Demo Building, 72 spare cylinders Total 207 Reserves can accommodate a maximum of 64 people.

Reserves must be obtained from storage.

SEC will make final decision on which personnel will be accommodated by reserves ifevacuation criteria is reached.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 22 of 25 Page 1 of 4 ATTACHMENT 6, POTASSIUM IODIDE ISSUE [B2367]

Action levels for issuance of potassium iodide (KI) and evaluation of radiological conditions.

NOTE Emergency workers include police, fire, rescue, medical, paramedical, radiation monitoring personnel, and others performing an emergency function under governmental direction.

Potassium iodide may be made accessible to offsite emergency workers according to this attachment, Potassium Iodide Issue, by Calvert Memorial Hospital Administrators, dispensed by public health officials, and continued as directed by public health officials.

5000 doses of potassium iodide are stored at the Calvert Memorial Hospital Pharmacy.

Administration of potassium iodide is within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, if practical. Administration after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will still reduce the biological half-life of radioiodine.

1. EVALUATE reported Offsite Monitoring Team/Onsite Monitoring Team radioiodine concentrations down wind from plant.
a. Action level for administration is 4.89E-5 pCi/cm 3iodine.
2. EVALUATE computer projected adult thyroid dose rates down wind from plant.
a. EVALUATE projected duration of exposure,
b. CALCULATE projected dose using the relationship:

dose = dose rate

  • projected time

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 23 of 25 Page 2 of 4 ATTACHMENT 6, POTASSIUM IODIDE ISSUE [B-1]

POTASSIUM IODIDE (KI) ISSUE LOG.

Recommended by: At time Date (Radiological Assessment Director) 0,q 04 C) 0)

Approved by: At time Date (Emergency Director/Recovery Manager)

Authorized dispensers (in person or over the phone) may delegate any responsible person to dispense potassium iodide to facilitate distribution. Person dispensing potassium iodide shall log employee information below for any employee accepting 1 dose. Only 1 dose per employee shall be dispensed.

Document any refusal by entering "R" in the dose block. Enter "1" if employee accepts the dose.

Notify the RAD ifa refusal is documented offsite; notify the RPD if a refusal is documented onsite.

Ensure the PGM, GSNO, and Center Directors are aware of dispensing KI.

Personnel authorized to dispense KI:

Calvert Cliffs Medical Staff 0 03 C)

CEG Medical Personnel RAD DISPENSED BY: AT TIME DATE (AUTHORIZED PERSON OR PERSON DELEGATED TO DISPENSE)

T 1T r 1 Dos Time Employee Name Control Dose Time Employee Name Control Control Dos e

4 I.

4 4 I-

  • + 4 FORWARD completed records to Supervisor-Emergency Preparedness at emergency termination.

Authorized dispenser shall NOTIFY CEG Medical Director of Usage.

  • 2

RADIATION PROTECTION DIRECTOR ERevIPion0090 Revision 00904 Page 24 of 25 Page 3 of 4 ATTACHMENT 6, POTASSIUM IODIDE ISSUE [B-1]

POTASSIUM IODIDE (KI) STORAGE.

NOTE CCNPP potassium iodide storage and protocol Office Training Facility, Medical Suite

  • Controlled by CCNPP Medical Personnel 1 case (1400 doses)
  • Recommended by Radiological Assessment Director and approved by Site Emergency Coordinator.
  • Dispensed by Authorized Personnel or Emergency Operation Facility, Status Room persons delegated to dispense by 1 case (1400 doses) Authorized Personnel Farm Demo Building 1 case (1400 doses) 4 Calvert County potassium iodide storage and protocol Calvert Memorial Hospital Pharmacy
  • Controlled by Hospital Administrator
  • Recommended by Radiological Assessment Director
  • Dispensed by Public Health Officials (Facility Phone Numbers List)

RAD AND RPD shall NOTIFY (as soon as practical) CEG Medical Director of all actions taken with regard to potassium iodide, use the Facility Phone Numbers List.

RADIATION PROTECTION DIRECTOR ERPIP-303 Revision 00904 Page 25 of 25 Page 4 of 4 ATTACHMENT 6, POTASSIUM IODIDE ISSUE [B-1]

POTASSIUM IODIDE (KI) INFORMATION SHEET.

This information sheet is designed to help you learn about potassium iodide (KI). It will answer questions you may have about potassium iodide like what is it, who should take it, when should it be taken, and are there any side effects. Potassium iodide can help protect you in a radiation emergency.

This information is provided in General Orientation Training.

Q. What is potassium iodide?

A. Potassium iodide is a form of iodine. Certain forms of iodine help the thyroid gland work correctly. Most people get the iodine they need from foods like iodized salt or fish.

Q. Why is potassium iodide used in a radiation emergency?

A. In a radiation emergency, radioactive iodine could be released into the air. Potassium iodide (a form of iodine) can help protect you because the thyroid can "store" or hold only a certain amount of the iodine. The idea behind taking potassium iodide is to "flood" the body with a supply of stable iodine so that the risk of the thyroid "picking up" radioactive iodine is very low.

Q. Who should not take potassium iodide?

A. The only people who should not take potassium iodide are people who know they are allergic to iodine. Those who know they are allergic to iodine should consult the medical representative onsite immediately or call 410-495-4022 Q. Can I take potassium iodide if I am on other thyroid medications?

A. Yes. You may safely take potassium iodide ifyou are taking medication for a thyroid problem (for example, a thyroid hormone or anti-thyroid drug).

Q. When should I take potassium iodide?

A. One dose of potassium iodide should be taken as soon as possible after the onsite medical representative tells you to. One dose of KI is equivalent to 130 mg.

Q. What are the side effects of potassium iodide?

A. Usually, side effects of potassium iodide happen when people take higher doses for a long time.

These side effects include skin rashes, swelling of the salivary glands, and "iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes a stomach upset and diarrhea). If you have a reaction to iodine, it usually manifests itself as fever, joint pains, or swelling of parts of the face and body. Rarely, there is severe shortness of breath that requires immediate attention.

Q. What should I do if side effects occur?

A. If side effects occur, stop taking the medication and consult the onsite medical representative.

(Prepared and required by Occupational Health.)

Constellation Energy, Calvert Cliffs Nuclear Power Plant TECHNICAL PROCEDURE ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR Revision 01204 Safety Related CONTINUOUS USE Applicable To:

Calvert Cliffs Nuclear Power Plant Approval Authority:

Plant General Manager

RADIOLOGICAL ASSESSMENT DIRECTOR ERPIP-51 I Revision 01204 Page 2 of 55

SUMMARY

OF ALTERATIONS Revision Char ige Summary of Revision or Change 012 00 Added new basis to procedure [8-5]. Added names of Radiological Assessment Directors to Attachment 11, Potassium Iodide Issue, as personnel authorized to dispense KI.

012 01 (403-287) Corrected the revision number in the header on Attachments 13 through

22. Revision bars not used.

012 02(4 03-291) Corrected the page numbers on Attachment 22. Change bars have not been used.

012 03 Editorial correction to perform the following: Change Site Emergency Coordinator to Emergency Director. Removed definition of "fully staffed" and left it up to RAD to determine if needed. Removed Attachment 22, which is covered by the HU procedures.

012 04 Procedure reformatted to the new template per the requirements of CNG-PR-1.01-1005, Control of Constellation Nuclear Generation Technical Procedure Format and Content.

Changed Section 3.1.6 from PR-1-101, Preparation and Control of Calvert Cliffs Technical Procedures to CNG-PR-1.01-1005, Control of Constellation Nuclear Generation Technical Procedure Format and Content.

PR-1-101 is no longer used.

Changed Section 3.1.7 from PR-1-103, Use of Procedures to CNG-PR-1.01-1009, Procedure Use and Adherence Requirements.

PR-1-103 is no longer used. CNG-PR-1.01-1009 is the new fleet procedure.

Changed Section 3.2.2 from SE-1-100, Fitness for Duty Program, to CNG-SE-1.01-1001, Fitness for Duty. SE-1-100 is no longer used.

CNG-SE-1.01-1001 is the new fleet procedure.

Under Sections 9.1 and 9.3 changed PR-3-1 00, Records Management to CNG-PR-3.01-1000, Records Management. PR-3-100 is no longer used.

CNG-PR-3.01-1000 is the new fleet procedure.

Editorial Correction to Attachment 11, Potassium Iodide Issue, Page 3 of 5.

Removed names. Only positions should be listed. Names of people to distribute KI are no longer at CCNPP. These actions should be assigned to the person qualified hence names are not needed. RPA-2009-0161.

RADIOLOGICAL ASSESSMENT DIRECTOR ERPIP-511 Revision 01204 Page 3 of 55 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPO SE .................................................................................................................................. 5 2.0 APPLICABILITY/SCO PE ..................................................................................................... 5 2.1 Scope ............................................................................................................................. 5

3.0 REFERENCES

AND DEFINITIONS ....................................................................................... 5 3.1 Developm ental References ........................................................................................ 5 3.2 Perform ance References ............................................................................................ 6 3.3 Definitions ........................................................................................................................ 6 3.4 Specifications .................................................................................................................. 7 4.0 PREREQ UISITES ....................................................................................................................... 7 4.1 Training and Q ualification ............................................................................................ 7 4.2 Initial Conditions ......................................................... .................................................... 7 4.3 Docum entation and Support ....................................................................................... 7 5.0 PRECAUTIONS ......................................................................................................................... 7 6.0 PERFO RMANCE ....................................................................................................................... 8 6.1 Activation ....................................................................................................................... 8 6.2 O peration ...................................................................................................................... 12 6.3 Deactivation .................................................................................................................. 25 7.0 POST PERFO RMANCE ACTIVITIES ................................................................................... 26 8.0 BASES ..................................................................................................................................... 26 9.0 RECORDS ............................................................................................................................... 27 ATTACHM ENT 1, INTERIM DOSE ESTIMATE ................................................ ................... .............. 28 ATTACHMENT 2, CORE DAMAGE ASSESSMENT AND CONTAINMENT INTEGRITY STATUS ..... 29 ATTACHM ENT 3, MONITO R ALARM TABLE ............................................................................... 30 ATTACHM ENT 4, ACCIDENT TYPE SELECTION .......................................................................... 31 ATTACHMENT 5, DOSE ASSESSMENT MONITOR SELECTION ................................................. 32 ATTACHM ENT 6, LEAK RATE TABLE .............................................. .............................................. 33 ATTACHMENT 7, PROJECTED GROUND DEPOSITION WORK SHEET ...................................... 34 ATTACHM ENT 8, PROTECTIVE ACTIO N GUIDES ....................................................................... 35 ATTACHMENT 9, PROTECTIVE ACTION RECOMMENDATION DATA SHEET ........................... 37 ATTACHM ENT 10, O NSITE EVACUATION CRITERIA ................................................................. 38 ATTACHM ENT 11, POTASSIUM IO DIDE ISSUE [B-1] [B-4] ........................................................... 39 ATTACHM ENT 12, SURVEY RESULTS ......................................................................................... 44 ATTACHMENT 13, REFINED SOURCE TERM ESTIMATES ......................................................... 45

RADIOLOGICAL ASSESSMENT DIRECTOR ERPIP-51 I Revision 01204 Page 4 of 55 TABLE OF CONTENTS (Continued)

SECTION TITLE PAGE ATTACHMENT 14, ACCIDENT SOURCE TERM BASIC METHOD ................................................ 48 ATTACHMENT 15, TABLE IA (BG&E-EP9) (CORE) FISSION PRODUCT INVENTORY (FPI) ..... 49 ATTACHMENT 16, TABLE 1B (BG&E-EP9) (NORMAL COOLANT) FISSION PRODUCT INVENTORY (FP I)......................................................................................................................... 50 ATTACHMENT 17, TABLE 2 (NUREG-1228) (1-HOUR RELEASE) CORE RELEASE FRACTIONS (C R F ) . ..................................................................................................................... 51 ATTACHMENT 18, TABLE 3A (NUREG-1228) RELEASE PATHWAY NON-NOBLE GAS REDUCTION FAC TO RS (R DF) .............................................................................................. 52 ATTACHMENT 19, TABLE 3B (NUREG-1228) RELEASE PATHWAY NON-NOBLE GAS REDUCTION FACTO RS (RDF) ............................................................................................. 53 ATTACHMENT 20, TABLE 4 (NUREG-1 228) (1 HOUR RELEASE) CONTAINMENT AND STEAM GENERATOR TUBE RUPTURE ESCAPE FRACTIONS (EF) ...................... ......... 54 ATTACHMENT 21, GROUND DEPOSITION FIELD SURVEY DATA REDUCTION ........................ 55

RADIOLOGICAL ASSESSMENT DIRECTOR ERPIP-511 Revision 01204 Page 5 of 55 1.0 PURPOSE This procedure provides emergency response instructions for the Radiological Assessment Director (EOF) for use during an emergency action level called at Calvert Cliffs Nuclear Power Plant.

2.0 APPLICABILITYISCOPE This procedure applies to the Radiological Assessment Director (EOF) in the Dose Assessment Office.

2.1 Scope Performance of the actions in the order they are presented in Subsection 6.2, Operations,is not mandatory provided Subsection 6.1, Activation, has been accomplished.

3.0 REFERENCES

AND DEFINITIONS 3.1 Developmental References 3.1.1 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency response Plans and Preparedness in Support of Nuclear Power Plants 3.1.2 10 CFR 20, Standards for Protection Against Radiation 3.1.3 10 CFR 50.47, Emergency Plans 3.1.4 10 CFR 50*Appendix E to Part 50, Emergency Planning and Preparedness for Productions and Utilization Facilities 3.1.5 Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.1.6 CNG-PR-1.01-1005, Control of Constellation Nuclear General Technical Procedure Format and Content. CD 3.1.7 CNG-PR-1.01-1009, Procedure Use and Adherence Requirements. C 3.1.8 Technical Procedures Writer's Manual

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paqe 6 of 55 3.2 Performance References 3.2.1 Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.2.2 CNG-SE-1.01-1001, Fitness for Duty.

(I-C) 3.2.3 RSP 1-117, Issuance and Wearing of RespiratoryProtectionDevices Used to Protect Against Aireborne Radioactivity 3.2.4 ERPIP-B.2, Offsite Survey Points 3.2.5 ERPIP-3.0, Immediate Actions 3.2.6 ERPIP-107, Chemistry Shift Technician 3.2.7 ERPIP-504, EnvironmentalAssessment Director 3.2.8 ERPIP-507, Offsite Monitoring Team 3.2.9 ERPIP-810, Main Steam System Radioactivityrelease Rate Estimate 3.2.10 ERPIP-821, Accidental RadioactivityRelease Monitoring and Sampling Method 3.2.11 ERPIP-822, Initial Dose Assessment Manual CalculationMethods 3.2.12 ERPIP-823, Dose Assessment Computer 3.2.13 ERPIP-824, Dose Assessment Reference 3.2.14 ERPIP-825, MeteorologicalData Acquisition Methods 3.2.15 RADDOSE V, DetailedDesign Manual 3.3 Definitions Radiological Assessment Director (EOF)

This position evaluates radiological conditions and makes recommendations to the Emergency Director (EOF). The principal responsibility of the Radiological Assessment Director (EOF) is to provide Protective Action Recommendations to the Emergency Director (EOF) and to perform as the principal communicator with the NRC and the State of Maryland.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paqe 7 of 55 3.4 Specifications 3.4.1 Performance of the actions in the order they are presented in this procedure is not mandatory. Implement only appropriate actions considering accident situation.

4.0 PREREQUISITES 4.1 Training and Qualification Personnel performing this procedure shall be qualified on the tasks or activities contained in this procedure.

4.2 Initial Conditions One of the following emergency action levels is called at Calvert Cliffs Nuclear Power Plant:

  • Alert
  • Site Emergency
  • General Emergency 4.3 Documentation and Support Forms needed to implement this procedure are contained as attachments to this procedure. Forms may be computer generated or revised without requiring a change or revision to this procedure, providing the intent is not changed, and the required information is not deleted from the existing forms.

5.0 PRECAUTIONS Declared pregnant women and minors are not authorized to perform emergency functions.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 6.0 PERFORMANCE NOTE Action order is not mandatory for Subsection 6.1, Activation, and 6.2, Operation.

6.1 Activation 6.1.1 REPORT to the Emergency Operations Facility.

1. NOTIFY the Emergency Operations Facility Director (EOF) of the RAD.
2. NOTIFY the Site Emergency Director (EOF) of the RAD.

6.1.2 OBTAIN AND EVALUATE plant and accident conditions.

1. CALL the Chemistry Shift Technician (CR) in the Control Room or Technical Support Center Annex for interim dose estimate status.

OBTAIN briefing using the topics provided on Attachment 1, Interim Dose Estimate.

IF produced, THEN DIRECT Chemistry Shift Technician (CR) to send the following information via facsimile machine to Emergency Operations Facility Dose Assessment:

A copy of ERPIP-107, Attachment 2, Plume Exposure Emergency Planning Zone Dose Estimate Work Sheet.

A copy of the RADDOSE Computer Centerline Dose Rates.

6.1.3 CALL the Technical Support Center Director (TSC) in the Technical Support Center for core damage assessment and containment integrity assessment.

1. OBTAIN briefing using the topics provided on Attachment 2, -

Core Damage Assessment and ContainmentIntegrity Status.

6.1.4 OBTAIN AND EVALUATE accident instrumentation and plant conditions.

i

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 9 of 55 6.1 (Continued)

NOTE Plant Parameters Data is available via the Emergency Response Web Page, via fax, and via phone.

6.1.5 REVIEW the readings for high range radiation monitors provided by the Emergency Operations Facility Plant Parameter Communicator (EOF).

.1. DETERMINE which monitors are in alarm using Attachment 3, MonitorAlarm Table.

2. SELECT accident type for dose modeling using Attachment 4, Accident Type Selection.
3. SELECT the monitor to be assessed using Attachment 5, Dose Assessment Monitor Selection.
4. SELECT leak ratesi
a. IF' modeling dose with the CHRRM, THEN SELECT a leak rate using Attachment 6, Leak Rate Table.
b. IF modeling dose with the MSSRM, THEN USE default leak rate for an open safety valve (2.44E+6 cm 3/s) or an open atmospheric dump valve (1.33E+6 cm 3/s).

6.1.6 STATION AND ASSIGN duties to Radiological Assessment Specialists (EOF) reporting to Emergency Operations Facility.

1. STATION Radiological Assessment Specialist (EOF) staff to complete the following:
  • PERFORM real time assessment of the release
  • PERFORM hypothetical assessment of the release
  • OBTAIN data AND PERFORM meteorological data tracking and radiological monitoring system data tracking OPERATE Health Physics Network communications link with NRC Headquarters/Region I C

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paue 10 of 55 6.1 (Continued) 6.1.7 COMMUNICATE expectations to crew.

6.1.8 ENSURE that Dose Assessment Office equipment works.

1. ASSIGN Radiological Assessment Specialist (EOF) to ensure the Dose Assessment Office equipment works.
a. CONFIRM Emergency Operations Facility dose assessment computers, printers, and meteorological data recording and display terminal are working.
b. IF the Emergency Operations Facility dose assessment computers or meteorological data recording and display terminal are not working, THEN:

(1) DIRECT Radiological Assessment Specialist (EOF) to use backup methods.

(a) REFER to the following procedures to assist in determining the types of calculations required:

ERPIP-821, Accidental Radioactivity Release Monitoring And Sampling Methods ERPIP-822, Initial Dose Assessment Manual Calculation Methods ERPIP-824, Dose Assessment Reference ERPIP-825, Meteorological Data Acquisition Methods (b) REPORT computer problems to the Emergency Operations Facility Computer Support (EOF) or the Telecommunications Support Manager (EOF) for repair.

c. IF the primary computer dose model is not available, THEN DIRECT Radiological Assessment Specialist (EOF) to use backup method for projecting ground deposition PER Attachment 7, Projected GroundDeposition Work Sheet, when needed.

6.1.9 RELIEVE the Chemistry Shift Technician (CR) of interim radiological dose assessment when Dose Assessment Office is ready.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 6.1 (Continued) 6.1.10 Dose Assessment readiness is attained when RAD determines all key Dose Assessment functions can be performed as required.

1. CALL the Chemistry Shift Technician (CR) in Control Room OR the Technical Support Center Annex.
a. OBTAIN final turnover from the Chemistry Shift Technician (CR).
2. COMMUNICATE Dose Assessment Office readiness to the Radiological Assessment Director (EOF) or Emergency Operations Facility Director (EOF) and Emergency Director (EOF).

6.1.11 DIRECT Offsite Monitoring Team (EOF) to assemble AND MAKE the Offsite Monitoring Team (EOF) ready for assignment.

6.1.12 DOCUMENT appropriate dose assessment activities in the Radiological Assessment Director (EOF) logbook or web based log.

6.1.13 REVIEW Attachment 8, Protective Action Guides, page 1, EPA PAGs for Early Phase of a Nuclear Incident.

6.1.14 Be prepared to inform the Emergency Director (EOF) of basis for Protective Action Recommendations, when or if required.

6.1.15 REVIEW Attachment 8, Protective Action Guides, page 2, Guidance on Dose Limits for Workers Performing Emergency Services.

6.1.16 Be prepared to inform the Emergency Director (EOF) and Radiation Protection Director (OSC) of the basis for allowing exposures above normal administrative limits, when or if required.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 12 of 55 ER!~'o 4.4 6.2 Operation 6.2.1 SUPERVISE Radiological Assessment Specialist (EOF) collection and assessment of radiological monitoring system data.

NOTE RMS data is available on the Emergency Response Web Page at 15 minute intervals (approx.). RMS data can be obtained by facsimile or telephone from the Radiation Monitoring System Communicator (CR) if the Emergency Response Web page is not available.

1. DIRECT Radiological Assessment Specialist (EOF) to complete the following:
a. IF Emergency Response Web Page is unavailable, THEN ENSURE monitor readings are posted on status boards. (Radiological Assessment Director (EOF) may direct Radiological Assessment Specialist (EOF) to record readings on forms if desired by Radiological Assessment Director (EOF)).
b. MONITOR high range monitorreadings (available from the Emergency Operations Facility Plant Parameter Communicator (EOF) via the Emergency Response Web page).
c. ENSURE radiation monitor(s) selected are assessed considering accident type.

6.2.2 EVALUATE plant monitor information.

1. REVIEW monitor readings with respect to Attachment 3, MonitorAlarm Table.
2. REVIEW appropriateness of monitor choice with respect to Attachment 5, Dose Assessment Monitor Selection.
3. REVIEW monitor reading levels with respect to Attachment 4, Accident Type Selection.
4. REVIEW leak rate assumptions with respect to Attachment 6, Leak Rate Table.

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 6.2 (Continued) 6.2.3 SUPERVISE Radiological Assessment Specialist (EOF) collection and evaluation of meteorological data.

1. ENSURE Radiological Assessment Specialist (EOF) obtains appropriate meteorological data, as specified in ERPIP-825, MeteorologicalData Acquisition Methods.
2. DIRECT Radiological Assessment Specialist (EOF) to ensure the following activities are completed:
a. UPDATE dose assessment status board.
b. CAPTURE dose assessment information on meteorological data tracking forms, as needed.
3. DIRECT Radiological Assessment Specialist (EOF) to take the following actions:
  • DETERMINE weather forecast (local and regional).
  • FORECAST information may also be obtained from the National Weather Service (see Facility Phone Number List) or internet.

6.2.4 EVALUATE meteorological data.

1. REVIEW wind direction for shifts towards populations or monitoring teams.
2. REVIEW wind speed for plume arrival times.
3. REVIEW effects of elevated and ground level releases according to ERPIP-825, MeteorologicalData Acquisition Methods.
4. REVIEW stability class shifts impacting dose consequences.
5. REVIEW precipitation effects on deposition and washout of nuclides.

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 14 of 55 6.2A4 (Continued)

6. DETERMINE if meteorological conditions are conducive to bay breeze.

Daylight hours (period between the time of sunrise and sunset for the RADDOSE release date).

Ground surface temperature is greater than the water surface temperature (bay breeze season is April through September).

Surface Water Temperature Table Jan 4.3°C May 15.7°C Sept 24.7 0 C Feb 5.40C June 22.90C Oct 20.9°C March 7.1°C July 27.00C Nov 13.50C April 14.9°C Aug 27.0°C Dec 8.7 0 C Wind detected by the onsite meteorological tower is onshore (that is, winds estimated from between 125 to 180 degrees).

6.2.5 SUPERVISE Radiological Assessment Specialist (EOF) computer usage to define the magnitude and location of the offsite impact of a release and 6.2.6 EVALUATE assessment results.

1. DIRECT Radiological Assessment Specialist (EOF) to operate the computer according to ERPIP-823, Dose Assessment Computer, using:
  • Trip time data
  • Release time data
  • Meteorological data according to ERPIP-825, MeteorologicalData Acquisition Methods Radiation monitoring system data

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paae 15 of 55 6.2.6 (Continued)

2. EVALUATE computer dose assessment report to:
a. MAKE an initial estimate of the fission product inventory that may be released.

OR

b. MAKE an initial estimate of the fission product inventory that may be available for release.

(1) ENSURE Radiological Assessment Specialist (EOF) performs forecast if required by RADDOSE.

(2) REVIEW any real time high dose rates and high dose areas forecasted.

(3) REPORT to the Radiological Assessment Director (EOF) or the Emergency Director (EOF) or both any Radioactivity Release Emergency Action Levels (according to ERPIP-3.0, Immediate Actions, Attachment 1, Emergency Action Level (EAL) Criteria) that have been or may be exceeded based on dose assessment.

(4) REVIEW Protective Action Zones and any sector and zone in which Protective Action Guides may be exceeded according to Attachment 9, Protective Action Recommendation Data Sheet.

3. ESTIMATE the uncertainties of the dose assessment calculations. Be prepared to discuss uncertainties with the Radiation Assessment Director (EOF) the Emergency Director (EOF) or both as needed.
a. Is the isotopic mix of nuclides in the release certain or uncertain?
b. Is the release pathway certain or uncertain?
c. Is the magnitude of core damage certain or uncertain?
d. Is the release pathway monitored or unmonitored?
e. Is the leak rate certain or uncertain?
f. Are all the isotopic reduction mechanisms accounted for or unaccounted for?

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paqe 16 of 55 6.2.6.3 (Continued)

g. Are the meteorological variables measured or assumed?

6.2.7 EVALUATE AND RECOMMEND protective actions based on dose projections.

1. Emergency Director (EOF): DOCUMENT CCNPP Protective Action Recommendations within 15 minutes of calculations or changing conditions that led to the decision to make the recommendation. [B-3]
2. For offsite Protective Action Recommendations:
a. EVALUATE the need for offsite Protective Action Recommendations by comparing Attachment 8, ProtectiveAction Guides, to dose projections for Protective Action Zones outside of the initially evacuated Protective Action Zones including sectors/zones beyond the 10 mile EPZ.
b. COMPLETE Attachment 9, Protective Action Recommendation Data Sheet, to document offsite Protective Action Recommendations.
c. RECOMMEND offsite Protective Action Recommendations to Emergency Director (EOF).
3. For onsite Protective Action Recommendations:
a. EVALUATE the need for onsite Protective Action Recommendations using Attachment 10, Onsite Evacuation Criteria.
b. COMPLETE Attachment 9, ProtectiveAction Recommendations Data Sheet, to document onsite Protective Action Recommendations, if not already documented with offsite Protective Action Recommendations.
c. RECOMMEND onsite Protective Action Recommendations to Emergency Director (EOF).

6.2.8 IF directed by Emergency Director (EOF), THEN COMMUNICATE with appropriate organizations.

6.2.9 RECOMMEND to the Emergency Director (EOF) the use of potassium iodide for workers according to Attachment 11, PotassiumIodide Issue. [B4].

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 17 of 55 6.2.9 (Continued)

1. EVALUATE Attachment 11, Potassium Iodide Issue, page 1 of 5, for action levels met.
2. COMPLETE Attachment 11, Potassium Iodide Issue, page 2 of 5.
3. OBTAIN Emergency Director (EOF) approval.
4. IMPLEMENT approved Attachment 11, Potassium Iodide Issue, page 2 of 5, actions.

6.2.10 SUPERVISE the Offsite Monitoring Team (EOF) AND PROVIDE direction to Offsite Monitoring Team (EOF) (via the Offsite Monitoring Team Leader (EOF)).

1. DETERMINE transportation needs for Offsite Monitoring Team (EOF).
2. ENSURE correct Emergency Work Permits for offsite monitoring
a. SPECIFY to the Offsite Monitoring Team (EOF), the Emergency Work Permits to be used by the Offsite Monitoring Team (EOF) according to ERPIP-832, Emergency Work Permits.

NOTE PRE-APPROVED copy of the Emergency Work Permit is in monitoring kits.

'(1) CONSULT with the Radiation Protection Director (OSC) regarding implementation of Emergency Work Permits (on full augmentation).

(2) DIRECT Offsite Monitoring Team Leader (EOF) to have the Offsite Monitoring Team (EOF) read and sign pre-approved Emergency Work Permits (for use before full augmentation) at vehicles.

3. EVALUATE actions to minimize Offsite Monitoring Team Leader (EOF) radiation exposure.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 6.2.10.3 (Continued)

a. DIRECT Offsite Monitoring Team Leader (EOF) to give periodic up dates on the accident conditions to the Offsite Monitoring Team (EOF), as necessary.
b. DIRECT Offsite Monitoring Team Leader (EOF) to minimize Offsite Monitoring Team (EOF) radiation exposure, as necessary.

(1) DIRECT Offsite Monitoring Team Leader (EOF) to have Offsite Monitoring Team (EOF) use respiratory protection according to RSP 1-117, Issuance And Wearing Of Respiratory ProtectionDevices Used To ProtectAgainst Airborne Radioactivity.

(2) DIRECT Offsite Monitoring Team Leader (EOF) to report to Radiological Assessment Director (EOF) if exposures are projected to exceed 80 percent of 10 CFR 20 limits (10 CFR 20 has a limit 5 rem TEDE).

(3) NOTIFY the Radiation Protection Director (OSC) and Emergency Director (EOF) if exposures are projected to exceed 80 percent of 10 CFR 20 limits (10 CFR 20 has a limit 5 rem TEDE for year).

4. DETERMINE scope of gamma plume surveys, beta/gamma ground surveys and air samples.
a. ESTABLISH survey locations, preferably at established survey points identified in ERPIP-B.2, Offsite Survey Points, coinciding with prevailing wind directions during or following the radioactive release or both.
5. DIRECT Offsite Monitoring Team Leader (EOF) to complete the following actions:
a. OBTAIN readings and samples at selected survey points.
b. VERIFY the release of radioactivity by a traverse of plume centedine to obtain readings and samples.
c. RECORD survey data on Attachment 12, Survey Results, as needed.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paae 19 of 55 6.2 (Continued) 6.2.11 EVALUATE AND RECOMMEND protective actions based on field survey results.

1. Emergency Director (EOF): DOCUMENT CCNPP Protective Action Recommendations within 15 minutes of calculations or changing conditions that led to the decision to make the recommendation. [B-3]
2. For offsite Protective Action Recommendations:
a. EVALUATE the need for offsite Protective Action Recommendations by comparing Attachment 8, Protective Action Guides, to field monitoring for contaminated areas outside of the initially evacuated Protective Action Zones including sectors/zones beyond the 10 mile EPZ.

(1) BASE the evaluation on ambient dose from ground contamination to determine ifa PAG will be reached within the projected duration of the accident.

b. COMPLETE Attachment 9, Protective Action Recommendations Data Sheet, to document Protective Action Recommendations.
c. RECOMMEND offsite Protective Action Recommendations to Emergency Director (EOF).
3. For onsite Protective Action Recommendations:
a. EVALUATE the need for Protective Action Recommendations using Attachment 10, Onsite Evacuation Criteria.
b. COMPLETE Attachment 9, ProtectiveAction Recommendations Data Sheet, to document Protective Action Recommendations, if not already documented with offsite Protective Action Recommendations.
c. RECOMMEND onsite Protective Action Recommendations to Emergency Director (EOF).

6.2.12 SUPERVISE Radiological Assessment Specialist (EOF) dose assessment computer usage to define the magnitude and location of the offsite impact of a hypothetical release based on projected deteriorating plant conditions or projected changes in meteorology or both.

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Pane 20 of 55 6.2.12 (Continued)

1. SUPERVISE Radiological Assessment Specialist (EOF) computer usage to define the magnitude and location of the offsite impact of a hypothetical release.
a. DIRECT Radiological Assessment Specialist (EOF) to operate the computer according to ERPIP-823, Dose Assessment Computer,using hypothetical:
  • Trip time data
  • Release time data
  • Meteorological data
  • Accident type data
  • Radiation monitoring system data
b. EVALUATE hypothetical computer dose assessment report to:

(1) MAKE a hypothetical estimate of the fission product inventory that may be released.

OR (2) MAKE a hypothetical estimate of the fission product inventory that may be available for release from the core.

(3) ENSURE Radiological Assessment Specialist (EOF) performs a hypothetical forecast if required by RADDOSE.

(4) REVIEW any hypothetical high dose rates and high dose areas forecasted.

(5) REPORT to the Radiological Assessment Director (EOF) or the Emergency Director (EOF) any Radioactivity Release EALs (according to ERPIP-3.0, Immediate Actions, Attachment 1, Emergency Action Level (EAL)

Criteria) that have been or may be exceeded based on hypothetical dose assessment.

(6) REVIEW hypothetical Protective Action Zones and any sector and zone in which Protective Action Guidelines may be exceeded according to Attachment 9, ProtectiveAction Recommendation Data Sheet.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 6.2 (Continued) 6.2.13 SUPERVISE Radiological Assessment Specialist (EOF) to determine refined source term estimates according to the following attachments:

  • Attachment 13, Refined Source Term Estimates
  • Attachment 14, Accident Source Term Basic Method
  • Attachment 15, Table 1A (BGE-EP9) (Core) Fission Product Inventory (FPI)

Attachment 16, Table 1B (BGE-EP9) (Normal Coolant) Fission Product Inventory (FPI)

  • Attachment 17, Table 2 (NUREG-1228) (1-Hour Release)

Core Release Fractions (CRF)

  • Attachment 18, Table 3A, (NUREG-1228) Release Pathway Non-Noble Gas Reduction Factors (RDF)
  • Attachment 19, Table 3B (NUREG-1228) Release Pathway Non-Noble Gas Reduction Factors (RDF)
  • Attachment 20, Table 4 (NUREG-1228) (1 Hour Release)

Containment And Steam Generator Tube Rupture Escape Fractions (EF)

1. CONSULT with Technical Support Center Director (TSC) on accident release path, reduction mechanisms in effect and magnitude of core damage.
2. SUPERVISE Radiological Assessment Specialist (EOF) refinement of the source term estimates using one or more of the following methods, as appropriate:

Estimate of effluent noble gas versus iodine ratios for the given set of plant conditions.

Estimate of effluent noble gas verses iodine ratios based on multichannel analyzer Main Vent release sample results from the Chemistry Director (TSC).

Main steam radioactivity release estimate based on Chemistry Director's (TSC) implementation of ERPIP-810, Main Steam System Radioactivity Release Rate Estimate.

Estimate of effluent noble gas versus iodine ratios based on Offsite Monitoring Team (EOF) survey data.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paue 22 of 55 6.2.13 (Continued)

3. EVALUATE the consequences of the refined assessment.
a. REVIEW the refined dose assessment report with respect to the earlier estimates that were calculated for the same time period.
b. DETERMINE if the consequences have been under or over estimated by earlier dose assessments.
c. UPGRADE protective action recommendations if refined dose assessment indicates a need for it.

6.2.14 SUPERVISE the Offsite Monitoring Team (EOF) to obtain ground deposition surveys and 6.2.15 PROVIDE direction to the Offsite Monitoring Team (EOF) (via the Offsite Monitoring Team Leader (EOF)).

1. DETERMINE scope of beta/gamma ground surveys.
a. ESTABLISH survey locations preferably at established survey points identified in ERPIP-B.2, Offsite Survey Points.
b. ESTABLISH survey locations to coincide with prevailing wind directions during or following (or both) the radioactive release.
c. ESTABLISH survey locations to coincide with projected RADDOSE ground deposition report.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 m

6.2.15 (Continued)

2. IMPLEMENT ground deposition survey.
a. WHEN deemed appropriate (that is, after plume passage), THEN DIRECT the Offsite Monitoring Team Leader (EOF) to perform ground deposition survey according to ERPIP-507, Offsite Monitoring Team.
b. OBTAIN readings and samples at selected survey points.

(1) IF 137 Cs or 131 I presence is suspected, THEN DIRECT Offsite Monitoring Team Leader (EOF) to have Offsite Monitoring Team (EOF) perform ground survey with gamma radiation detector (SPA-9). [B-2]

(a) Attachment 13, Refined Source Term Estimates, may be used to determine if 137 Cs or 131 I is suspect.

NOTE Net meter readings are reported (actual minus background). No beta correction factor is applied.

(2) IF 89 S, or 90 Sr presence is suspected, THEN DIRECT Offsite Monitoring Team Leader (EOF) to have Offsite Monitoring Team (EOF) perform ground survey with beta radiation detector (SHP-270). [B-2]

(a) Attachment 13, Refined Source Term Estimates, may be used to determine if 89 Sr or 90 Sr is suspect.

c. DIRECT Offsite Monitoring Team Leader (EOF) to

-reduce ground survey deposition field data according to Attachment 21, Ground Deposition FieldSurvey Data Reduction.

d. COMPARE ground survey reduced data with projected RADDOSE ground deposition report to determine areas of potential ground contamination.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 6.2 (Continued) 6.2.16 PROVIDE Environmental Assessment Director (EOF) with ground survey reduced data and RADDOSE ground deposition report and DISCUSS areas of potential ground contamination.

6.2.17 EVALUATE AND RECOMMEND long term release effects.

NOTE Environmental Assessment Director (EOF) is responsible for sampling in assumed uncontaminated areas. Radiological Assessment Director (EOF) is responsible for sampling in areas with suspected or known contamination..

1. DIRECT Environmental Assessment Director (EOF) to develop an environmental monitoring plan according to ERPIP-504, EnvironmentalAssessment Director(EOF).

NOTE Environmental sampling teams are not qualified occupational radiological workers. These teams will take samples from uncontrolled areas for verification of background.

Snow or ice samples or both may require special handling by Chemistry personnel. Chemistry Director (TSC) is the contact for onsite samples.

a. The plan should include the following:
  • Soil, vegetation, and water samples
  • Snow and ice samples, as needed
  • Collection of environmental monitoring media
  • Request for radiological workers
  • Protective clothing, respiratory protection, and radiation protection

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 6.1.16.1 (Continued)

b. COMPARE ground contamination survey according to Attachment 21, GroundDeposition Field Survey Data Reduction, and computer estimates of projected deposition with Radiation Safety Procedure limits to determine need for occupational radiological controls.

(1) IF ground contamination reaches 0.045 pCi/m 2 ,

THEN REQUIRE protective clothing.

(2) IF ground contamination reaches 13.5 pCi/m 2 ,

THEN CONSIDER respirators (particulate).

2. INTEGRATE protective action planning in Plume Emergency Planning Zone with protective action planning in Ingestion Emergency Planning Zone.

6.3 Deactivation 6.3.1 ON notification of event termination, THEN:

1. COLLECT radiological assessment records generated during the event.
a. PERFORM quality checks including, but not limited to the following:
  • Verification of computer data inputs.
  • Second check of manual calculations.
  • Second check of infrequent methods.
  • Self-assessment of radiological assessment process.
2. ENSURE return of equipment and unused material to the designated storage locations AND
3. DISPOSAL of trash in the appropriate locations.
4. ENSURE radiological assessment and related documentation are handled according to standard practices for those records and documentation unless otherwise specified.
5. FORWARD records to the Emergency Operations Facility Director (EOF) for turnover to the Director - Emergency Preparedness.

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 7.0 POST PERFORMANCE ACTIVITIES 7.1 CONDUCT self-assessment of Dose Assessment Activities for the event.

8.0 BASES

[B-1] IR3-034-566, clarify guidance in Attachment 12 for the administration of KI including correcting typographical errors.

[B-2] 1R3-051-226, AIT IR200001056, replace aging ERO radiological survey instruments.

[B-3] IR3-053-291, AIT IR200100721, missed DEP performance indicator, NEI 99-02, 15 minute requirement for PAR upgrade.

[B-4] IR3-044-111, AIT IR200100687, Clarify guidance on process for administration of potassium iodide.

[B-5] 66FR Notice #5427-5440, Licensees

,must provide a PAR for public administration of (KI) Potassium Iodide in states that have distributed KI to plume

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 27 of 55 9.0 RECORDS Records generated by this procedure may be permanent, non-permanent, or lifetime radiological records depending on the circumstances under which they are generated.

Records shall be captured and controlled as follows:

9.1 During an actual event as described in the purpose statement of this procedure, records shall be considered permanent records and submitted to the Emergency Preparedness Unit for final disposition according to CNG-PR-3.01-1000, Records Management.

9.2 During an actual event as described in the purpose statement of this procedure, dosimetry records, that is, any dose-related record including access history records, are considered radiological lifetime records and are to be handled and maintained according to standard practices and unit procedures.

a Interim Dose Estimate

  • Core Damage Assessment and Containment Integrity Status
  • Projected Ground Deposition Work Sheet
  • Protective Action Recommendation Data Sheet
  • Action levels for issuance of potassium iodide (KI) to Calvert Cliffs radiological workers and recommendation of potassium iodide for State and local emergency workers [B-1] [B-4]
  • Survey Results
  • Ground Deposition Field Survey Data Reduction 9.3 During a drill or exercise, records shall be considered non-permanent records and submitted to the Emergency Preparedness Unit for evaluation and retention according to CNG-PR-3.01-1001, Records Management. 0
  • Interim Dose Estimate
  • Core Damage Assessment and Containment Integrity Status
  • Projected Ground Deposition Work Sheet
  • Protective Action Recommendation Data Sheet
  • Action levels for issuance of potassium iodide (KI) to Calvert Cliffs radiological workers and recommendation of potassium iodide for State and local emergency workers [B-1] [B-4]

S'Potassium Iodide (KI) Issue Log [B-I] [8-4]

  • Survey Results
  • Ground Deposition Field Survey Data Reduction

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 ATTACHMENT 1, INTERIM DOSE ESTIMATE For interim dose estimate, ask the Chemistry Shift Technician (CR) for a briefing on the following:

1. Release status
2. Accident description
3. Known plant conditions
4. Plant trip time
5. Dose reports
6. Radiological Monitoring System (RMS)
7. Sampling status
8. Protective Actions related to offsite dose assessment
9. Met data
10. Other information pertinent to dose assessment
11. Time of last dose assessment projection Briefing notes:

Radiological Assessment Director (EOF) Date/Time FORWARD completed records to Director - Emergency Preparedness at emergency termination.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 29 of 55-ATTACHMENT 2, CORE DAMAGE ASSESSMENT AND CONTAINMENT INTEGRITY STATUS For core damage and containment integrity status, ask the Technical Support Center Director (TSC) for a briefing on the following:

1. RVLMS indications
2. Core exit thermocouple temperatures
3. Containment temperature
4. Containment pressure
5. Decay heat removal function
6. Likelihood of core uncovery
7. Results of Core Damage Assessment ERPIP using:
a. CTMT Radiation Dose Rates
b. Core Exit Thermocouples
c. CTMT Hydrogen
d. Radiological Analysis of Samples Briefing notes:

Radiological Assessment Director (EOF) Date/Time FORWARD completed records to Director - Emergency Preparedness at emergency termination.

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 ATTACHMENT 3, MONITOR ALARM TABLE UNIT I Monitor Device Reading Alarm Set Point MSSRM 1-RIC-5421 or 22 R/hr 5.7E-4 RPhr (Alert) 1.OE-2 R/hr (High)

WRNGM i-RIC-5415 piCi/sec 1.4E4 laCi/sec (Alert) 1.4E5 gCi/sec (High)

CHRRM 1-RI-5317 A or B R/hr 6 R/hr UNIT 2 Monitor Device Reading Alarm Set Point MSSRM 2-RIC-5421 or 22 R/hr 5.7E-4 R/hr (Alert) 1.OE-2 R/hr (High)

WRNGM 2-RIC-5415 lxCi/sec 1.1 E4 gCi/sec (Alert) 1.1 E5 giCi/sec (High)

CHRRM 2-RI-5317 A or B R/hr 6 R/hr

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paae 31 of 55 ATTACHMENT 4, ACCIDENT TYPE SELECTION Monitor If the monitor And the accident then the accident type reading description is... is at least..

is...

CTMT CHRRM: Loss of Coolant Accident. LOCAR: releasing RCS

>_ 5 R/h < 3500 R/h activity.

HIGH CHRRM: Loss of Coolant Accident. LOCAG: releasing gap

_ 3500 R/h < 14000 activity.

R/h RANGE CHRRM: Loss of Coolant Accident. LOCAC: releasing core

> 14000 R/h activity from melted fuel.

MAIN MSSRM: S/G tube rupture. SGTRR: releasing RCS

< 4 R/h activity.

STEAM MSSRM: S/G tube rupture. SGTRG: releasing gap

Ž4 R/h < 40 RJh activity.

SYSTEM MSSRM: S/G tube rupture. SGTRC: releasing core

>40 R/h activity from melted fuel.

WIDE Waste Gas Decay Tank WGDTR

> 1.1 E+4 RCi/s Rupture release RANGE Fuel Handling Incident in FHI

> 1.1 E+4 jiCi/s spent fuel pool or refuel pool, releasing fuel pin activity NOBLE Steam Generator tube SGTRR

> 1.1 E+4 p.Ci/s rupture releasing activity via condenser GAS Loss of Coolant Accident LOCAR

> 1.1 E+4 ICi/s releasing activity to the Auxiliary Building directly or via Containment leak NO N/A Loss of Coolant Accident SAST MONITOR releasing core activity from melted fuel into containment J

ERPIP-51 I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paqe 32 of 55 ATTACHMENT 5, DOSE ASSESSMENT MONITOR SELECTION then the MONITOR to use for If the accident description is.... dose assessment is...

S/G tube rupture releasing activity via condenser. WRNGM S/G tube rupture releasing activity via stuck open Safety MSSRM Valve SIG tube rupture releasing activity via stuck open Atmospheric Dump Valve Loss of Coolant Accident releasing activity to the CHRRM Containment only.

Loss of Coolant Accident releasing activity directly to the CHRRM environment via a containment leak.

Loss of Coolant Accident releasing activity to the Auxiliary WRNGM Building directly or via Containment leak.

Waste Gas Decay Tank Rupture release. WRNGM Fuel Handling Incident in spent fuel pool or refuel pool, WRNGM releasing fuel pin activity.

ERPIP-51 1 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 ATTACHMENT 6, LEAK RATE TABLE IF CHRRM (Containment High Range Radiation Monitor) is used for dose assessment: THEN USE the table below to estimate a leak rate.

INDICATION LEAK RATE (approximate) (circle one)

  • 1% volume per day (Design @ 25 psig) 1.OE+3 cm3/s 1% volume per day (Design @ 50 psig) 5.8E+3 cm 3/s 10% volume per day (For example, <6- 6.6E+4 cm 3/s square inch hole) 100% volume per day (For example, 6 6.6E+5 cm 3/s square inch hole) 100% volume per hour (For example 1- 1.6E+7 cm3/s square foot hole)

IF MSSRM (Main Steam System Radiation Monitor) is used for dose assessment THEN USE the table below to estimate leak rate.

INDICATION LEAK RATE PER VALVE Stuck Open Safety Valve 2.44E+6 cm 3/s Open Atmospheric Dump Valve 1.35E+6 cm 3/s

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 ATTACHMENT 7, PROJECTED GROUND DEPOSITION WORK SHEET A. Estimate total accident radioactivity release projected to end of accident. Use.

one of the following methods: default accident total, current release rate multiplied by duration, or total release estimated by Technical Support Center analysis. Post appropriate map isopleth overlay on Emergency Planing Zone map based on stability class and wind direction.

1. Record total release I-Ci
2. Record release start time. 5. Record release stop time.
3. Record stability class. 6. Record distance used.
4. Record sector affected. 7. Record xu/q.

B. Estimate deposition by multiplying total release (A.1) by Xu/Q (A.7) (from isopleth map overlay) by deposition conversion factor for specific nuclides.

1. Estimating element iodine deposition

__ pCi

  • m 1E-2 - __ __ pCim 2
2. Estimating methyl iodine deposition m -2 *r 2.5E-3 = 2 g___jCi/m

___ fici *

3. Estimating cesium deposition

____ pc m -2

4. Estimating strontium deposition

___ pCi

  • m- 2
5. Estimating particulates deposition

_ Ci

  • m -2 - 2E-3 = ___ Ci/m2 C. Evaluate calculations for initial activity to estimate areas of potential ground contamination.

Record Time:

Date:

Name:

FORWARD completed form to Emergency Preparedness at event termination.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paae 35 of 55 Page 1 of 2 ATTACHMENT 8, PROTECTIVE ACTION GUIDES (a) EPA PAGs For The Early Phase Of A Nuclear Incident

.0.1 04 F-4 Willse)ro Evacuation 1-5 rem b Evacuation (or, for some situations, sheltering a) should normally be initiated at 1 rem Administration of stable 25 remc Requires approval of State iodined medial officials.

a. Sheltering may be the preferred protective action when it will provide protection equal to or greater than evacuation, based on consideration of factors such as source term characteristics, and temporal or other site-specific conditions.
b. The sum of the effective dose equivalent resulting from exposure to external sources and the committed effective dose equivalent incurred from all significant inhalation pathways during the early phase. Committed dose equivalents to the thyroid and to the skin may be 5 and 50 times larger, respectively.
c. Committed dose equivalent to the thyroid from radioiodine.
d. An agreement with the state of Maryland and CCNPP provides that CCNPP will recommend that the public should be notified to take Potassium Iodide ýKl) if their Protective Action Zone (PAZ) was evacuated. Potassium Iodide will be distributed by the state of Maryland to the Plume Planning Zone. [B-5]

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paqe 36 of 55 Page 2 of 2 ATTACHMENT 8, PROTECTIVE ACTION GUIDES (2) Guidance On Dose Limits For Workers Performing Emergency Services 5 All 10 protecting valuable property lower dose not practicable 25 lifesaving or protection of large lower dose not practicable populations

>25 lifesaving or protection of large only on a voluntary basis to populations persons fully aware of the risks involved

a. Sum of external dose equivalent and committed effective dose equivalent to nonpregnant adults from exposure and intake during an emergency situation.

Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and body extremities) to ten times the listed value. These limits apply to all doses from an incident, except those received in unrestricted areas as members of the public during the intermediate phase of the incident.

ERPIP-51I RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Paae 37 of 55 ATTACHMENT 9, PROTECTIVE ACTION RECOMMENDATION DATA SHEET OFFSITE PROTECTIVE ACTION RECOMMENDATIONS P.A.R. based on: (circle one)

Current Met. Wind dir. (from) _ degrees Wind Spd. _ mph Stabil. Class _ Precip. mm Forecast Met. Wind dir. (from) - degrees Wind Spd. __ mph Stabil. Class__ Precip. mm

@t=

Plume EDE (cloud shine] [Dose Rate] or [ground sh] [Dose Thyroid CDE [organ] [Dose Rate]

Rate] Site Boundary Dose Rate rem/h Site Boundary Dose Rate rem/h (Other) miles rem/h (Other) miles rem/h Method Used: Field reading Method Used: Field Reading PAR based on: rem/h for hours =

PAR based on: rem/h for hours = rem rem EDE & CEDE (TEDE) [includes 4 days of ground sh EDE] Thyroid CDE (organ dose) 0.7 miles rem 0.7 miles rem 1 mile rem 1 mile rem 2 miles rem 2 miles rem 5 miles rem 5 miles rem 10 miles rem 10 miles _ _rem 50 miles rem 50 miles rem (Other) miles rem (Other) miles ased on hours exposure Based on hours exposure Method used (circle one): Computer CaIc. or Manual Calc. Method used (circle one): Computer Calc. or Manual Calc.

PAR based on: Protective Action Guides Guides emEE&

1- 5 remn11EDE EE

& CEDE PAR based on: 52 e Action Protective hri D Protective Action Guides reached (hours) 5-25 rem Thyroid CDE Protective Action Guides reached (miles) Protective Action Guides reached (hours)

Protective Action Guides reached (zones) Protective Action Guides reached (miles)

Protective Action Guides reached (zones)

Recommend following protective actions: E] NONE [] SHELTER E] EVACUATE& TAKE KI Protective Action Zones (Circle appropriatezones) 1 2 3 4 5 6 7 8 1 2 3 4 5 6 7 8 Beyond 10 mile EPZ Sector _ zone Sector - zone miles miles ONSITE PROTECTIVE ACTION RECOMMENDATIONS Outside Controlled Areas Inside Controlled All Persons Areas Not in ERO In ERO Precautionary Evacuation: Ul F-1.

Mandatory Evacuation:

Time: Comments:

Date:

Name:

FORWARD completed form to Emergency Preparedness at event termination.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 ATTACHMENT 10, ONSITE EVACUATIPN CRITERIA

,ersonnei not in Emergency Emergency Organization Organization Precautionary Evacuation Exposure Rate (mrem/h) > 0.5 (lasting 10h) > 2.5 > 1000 (b)

Airborne Activity > 2.OE-10 > 2.OE-8 > 8.OE-7 (c)

(pCi/cm 3) unevaluated Mandatory Evacuation Exposure Rate (mrem/h) > 2.5 (lasting 1Oh) > 100 Airborne Activity > 8.4E-9 (d) > 2.0E-8 >1.OE-5 (e) 3

([LCi/cm )

unevaluated NOTES:

(a) Controlled areas may be established by the Radiation Protection Director (OSC) as warranted by the situation.

(b) As deemed necessary, Emergency Director (EOF) may elect to use higher exposure rate based on pre-planned occupational radiation exposures.

(c) Equal to 40 DAC*h unevaluated. Respiratory protection should be used, iffeasible (f).

(d) Equal to 25% of weekly exposure (unrestricted area).

(e) Equal to 500 DAC*h unevaluated (25% Annual Limit 10 CFR 20.1201). Respiratory protection should be used, if feasible (f)

(f) Respirator reserves:

Control Room 23 MSA 4500 SCBAs Farm Demo Building 36 MSA 4500 SCBAs Nnr'l ganr in l nni Z" rrf Innfar r, C~A ArAA 4Zr'EPAc Total 64 Air cylinder reserves:

Materials Processing Facility 135 spare cylinders Farm Demo Building 72 sPare cylinders Total 207

" Reserves can accommodate a maximum of 64 people.

  • Reserves must be obtained from storage.
  • Emergency Director (EOF) will make final decision on which personnel will be accommodated by reserves if evacuation criteria is reached.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 39 of 55 Page 1 of 5 ATTACHMENT 11, POTASSIUM IODIDE ISSUE [B-l] [B-4]

Action levels for issuance of potassium iodide (KI) and evaluation of radiological conditions.

NOTE Emergency workers include police, fire, rescue, medical, paramedical, radiation monitoring personnel, and others performing an emergency function under governmental direction.

Potassium iodide may be madeaccessible to offsite emergency workers according to this attachment, Potassium Iodide Issue, by Calvert Memorial Hospital Administrators, dispensed by public health officials, and continued as directed by public health officials.

5000 doses of potassium iodide are stored at the Calvert Memorial Hospital Pharmacy.

Administration of potassium iodide is within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, if practical. Administration after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will still reduce the biological half-life of radioiodine.

1. EVALUATE reported Offsite Monitoring Team (EOF)/Onsite Monitoring Team (OSC) radioiodine concentrations down wind from plant.
a. 'Action level for administration is 4.89E-5 gCi/cm 'iodine.
2. EVALUATE computer projected adult thyroid dose rates down wind from plant.
a. EVALUATE projected duration of exposure.
b. CALCULATE projected dose using the relationship:

dose = dose rate

  • projected time NOTE Either action level is valid 3

RADIOIODINE CONCENTRATION ACTION LEVEL 4.89E-5 ttCi/cm

(

Reference:

ERPIP-824, Attachment 11, Committed Thyroid Dose Conversion FactorsFor Iodine Inhalation).

Equivalent to 25 rem CDE for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> exposure to radioiodine concentration beginning 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after reactor shutdown. Default value is given. More precise value can be obtained from reference table given below ADULT THYROID DOSE ACTION LEVEL:

25 rem

(

Reference:

EPA 400-R-92-001, Table 2-1)

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 2 of 5 ATTACHMENT 11, POTASSIUM IODIDE ISSUE [B-l] [B-4]

Action levels for issuance of potassium iodide (KI) to Calvert Cliffs radiological workers and recommendation of potassium iodide for State and local emergency workers.

(a) POTASSIUM IODIDE ISSUE ACTION LEVEL RECOMMENDATIONS CONDITION WORKERS ACTIONS

1. Projected thyroid dose is CCNPP Radiological Workers Notify Emergency Director (EOF),

less than 10 rem Radiological Protection Director (OSC), and Authorized Dispensers.

State & Local Emergency Workers Recommend sheltering where possible.

2. Projected thyroid dose is CCNPP Radiological Workers Notify Emergency Director (EOF),

greater than 10 rem and < Radiation Protection Director 25 rem. (OSC) and Authorized Dispensers.

State & Local Emergency Workers Recommend to consider administration of potassium iodide for workers not evacuated from the affected zones.

3. Projected thyroid dose is CCNPP Radiological Workers Notify Authorized Dispensers to

> 25 rem. administer potassium iodide according to page 3 of this attachment. Notify Radiation Protection Director (OSC) and Offsite Monitoring Team (EOF) of approval to administer.

State & Local Emergency Workers Recommend to administer potassium iodide for workers not evacuated from the affected zones.

4. One hour exposure to CCNPP Radiological Workers Notify Authorized Dispenser to radioiodine concentration administer potassium iodide

> 4.89-5 .iCi/cm 3 according to page 3 of this attachment. Notify Radiation Protection Director (OSC) and Offsite Monitoring Team (EOF) of approval to administer.

State & Local Emergency Workers Recommend to administer potassium iodide for workers not evacuated from the affected zones.

Recommendation: Condition (Check One)

El 1 If potassium iodide issue action level is met for conditions i 2 3 and/or 4, then recommend that potassium iodide to be issued within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, if practical. Administration of

[] 3 potassium iodide after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will still reduce the Q 4 biological half life of radioiodine.

Justification:

Radiological Assessment Director (EOF)/ Date/Time Emergency Director (EOF)/ Date/Time

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 41 of 55 Page 3 of 5 ATTACHMENT 11, POTASSIUM IODIDE ISSUE [B-l] [B-4]

Potassium iodide (KI) issue log.

Recommended by: At time Date (Radiological Assessment Director (EOF))

Approved by: At time Date (Emergency Director (EOF))

Authorized dispensers (in person or over the phone) may delegate any responsible person to dispense potassium iodide to facilitate distribution. Person dispensing potassium iodide shall log employee information below for any employee accepting 1 dose. Only 1 dose per employee shall be dispensed.

Document any refusal by entering "R" in the dose block. Enter "1" if employee accepts the dose. Notify the Radiological Assessment Director (EOF) if a refusal is documented offsite; notify the Radiation Protection Director (EOF) if a refusal is documented onsite.

Personnel authorized to dispense KI:

Calvert Cliffs Medical Staff 0

¢,q-CEG Medical Personnel CN RAD DISPENSED BY: AT DATE TIME (AUTHORIZED PERSON OR PERSON DELEGATED TO DISPENSE)

Time Employee Name Control # Dose Time Employee Name Control # Dose 4 4. 4 4 4. 4 4 4. 4 4 4. 4 4 1- 4 FORWARD completed records to Director -Emergency Preparedness at emergency termination.

Authorized dispenser shall NOTIFY CEG Medical Director of Usage

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 4 of 5 ATTACHMENT 11, POTASSIUM IODIDE ISSUE [B-1] [B13]

Potassium iodide (KI) storage.

NOTE CCNPP potassium iodide storage and protocol Office Training Facility, Medical Suite

  • Controlled by CCNPP Medical Personnel 1 case (1400 doses)
  • Recommended by Radiological Assessment Director (EOF) and approved by Emergency Director (EOF).

Emergency Operation Facility, Status Room

  • Dispensed by Authorized Personnel or 1 case (1400 doses) persons delegated to dispense by Authorized Farm Demo Building 1 case (1400 doses)

Calvert County potassium iodide storage and protocol Calvert Memorial Hospital Pharmacy

  • Controlled by Hospital Administrator
  • Recommended by Radiological Assessment Director (EOF) o Dispensed by Public Health Officials (Facility Phone Numbers List)

Radiological Assessment Director (EOF) and Radiological Protection Director (OSC) shall NOTIFY (as soon as practical) CEG Medical Director of all actions taken with regard to potassium iodide, use the Facility Phone Numbers List.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 43 of 55 Page 5 of 5 ATTACHMENT 11, POTASSIUM IODIDE ISSUE [B-1] [b-4]

Potassium iodide (KI) information sheet.

This information sheet is designed to help you learn about potassium iodide (KI). It will answer questions you may have about potassium iodide like what is it, who should take it, when should it be taken, and are there any side effects. Potassium iodide can help protect you in a radiation emergency. This information is provided in General Orientation Training.

Q. What is potassium iodide?

A. Potassium iodide is a form of iodine. Certain forms of iodine help the thyroid gland work correctly. Most people get the iodine they need from foods like iodized salt or fish.

Q. Why is potassium iodide used in a radiation emergency?

A. In a radiation emergency, radioactive iodine could be released into the air. Potassium iodide (a form of iodine) can help protect you because the thyroid can "store" or hold only a certain amount of the iodine. The idea behind taking potassium iodide is to "flood" the body with a supply of stable iodine so that the risk of the thyroid "picking up" radioactive iodine is very low.

Q. Who should not take potassium iodide?

A. The only people who should not take potassium iodide are people who know they are allergic to iodine. Those who know they are allergic to iodine should consult the medical representative onsite immediately or call 410-495-4022 Q. Can I take potassium iodide if I am on other thyroid medications?

A. Yes. You may safely take potassium iodide if you are taking medication for a thyroid problem (for example, a thyroid hormone or anti-thyroid drug).

Q. When should I take potassium iodide?

A. One dose of potassium iodide should be taken as soon as possible after the onsite medical representative tells you to. One dose of KI is equivalent to 130 mg.

Q. What are the side effects of potassium iodide?

A. Usually, side effects of potassium iodide happen when people take higher doses for a long time. These side effects include skin rashes, swelling of the salivary glands, and "iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes a stomach upset and diarrhea). If you have a reaction to iodine, it usually manifests itself as fever, joint pains, or swelling of parts of the face and body. Rarely, there is severe shortness of breath that requires immediate attention.

Q. What should I do if side effects occur?

A. If side effects occur, stop taking the medication and consult the onsite medical representative.

,(Prepared and required by Manager, Safety and Medical Services Department.)

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 44 of 55 ATTACHMENT 12, SURVEY RESULTS TIME TEAM LOCATION EXPOSURE Radiological Emergency LEADER/NO. RATE Assessment Director (SHIELDED) Director (EOF) (EOF)

NOTIFIED NOTIFIED

+ + 4 4 1- t + 4 1 FORWARD completed form to Emergency Preparedness at event termination.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 ER *P rPage 45 of 55 Page 1 of 3 ATTACHMENT 13, REFINED SOURCE TERM ESTIMATES th..etimteof effuen nblegasverusiodinie ratios

-1. o-Rfinmen for the given se:t~'- 4..... .

USE isotopes and quantities in the Table 1A (BG&E-EP9) (CORE) FISSION PRODUCT core or coolant INVENTORY (FPI) [Attachment 15].

Table 1B (NORMAL COOLANT) FISSION PRODUCT INVENTORY (FPI) is from BG&E-EP9, Calvert Cliffs Nuclear Power Plant Accident Source Terms, copies in Dose Assessment Office desks) as selected by the Radiological Assessment Director (EOF)

[Attachment 16].

USE core damage magnitude Table 2 (NUREG-1228) (1-HOUR RELEASE)

FISSION PRODUCT INVENTORY (FPI)), intact fuel, spiked fuel, gap release, grain boundary release, or core melt release as selected by the Radiological Assessment Director (EOF) [Attachment 17].

USE an accident release path Table 3A, (NUREG-1228) RELEASE PATHWAY NON-NOBLE GAS REDUCTION FACTOR (RDF)),

RELEASE PATHWAY DIAGRAM) as selected by the Radiological Assessment Director (EOF)

[Attachment 18].

USE non-noble gas reduction Table 3B, (NUREG-1228) RELEASE PATHWAY mechanisms in operation NON-NOBLE GAS REDUCTION FACTOR (RDF))

filters, water, steam generator partitioning, containment spray, containment holdup, etc.) as selected by the Radiological Assessment Director (EOF) [Attachment 19].

USE an escape fraction Table 4B, (1-HOUR RELEASE) CONTAINMENT AND STEAM GENERATOR TUBE RUPTURE ESCAPE FRACTION (EF))containment failure/leakage and steam generator tube rupture pathways) as selected by the Radiological Assessment Director (EOF)

[Attachment 20].

MULTIPLY each and every isotope in the core or coolant inventory by the selected CRF (Core Release Fraction) for the assumed core condition [Attachment 171.

MULTIPLY only the non-noble gas isotopes in the core inventory by the selected RDF (non-noble gas Reduction Factor) that corresponds to the assumed leak path, reduction mechanisms in effect and accident conditions [Attachment 191.

MULTIPLY each and every isotope in the core inventory by the appropriate EF (Escape Fraction for a one hour release) for the assumed release pathway [Attachment 201.

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 SPage 46 of 55 Page 2 of 3 ATTACHMENT 13, REFINED SOURCE TERM ESTIMATES 1.0 ýRefinement of the estimate pf~eftlnt nroble'ga's-v'ersus iodinie ratios ,-

. for

.. the given set of plant co itio...Continie * ".

ENTER each and every reduced isotope and quantity into the dose assessment model by using the model's accident isotopic distribution change function.

DETERMINE the ratio of noble gas to iodine after application of reduction factor(s) from the computer output by running a new computer model calculation with the input isotopic distribution.

PROVIDE the results of the calculations to the Radiological Assessment Director (EOF).

2.0 ~Reflpenemnt-of the estimateoýdfeffl uent'nobl gversu~sjoifr~~ij o CALL the Chemistry Director (TSC) in the Technical Support Center.

OBTAIN multichannel analyzer release sample data.

ENTER multichannel analyzer data into dose assessment model using the grab sample effluent analysis function.

USE meteorology appropriate to actual sample time.

RECALCULATE the dose consequences of the release.

PROVIDE the results of the calculation to the Radiological Assessment Director (EOF).

3.0 Refineen*t of m ainS te m* rakdl*atl.1j9*t~i'v i*e" s 0*

  • he*im is *uty* redto rý (TSC),*.*.*:::*:

imuefrnierittio oERIPi810d,'MA1'tE-A'r SYSE lOkTll(R~ESELRATEEST1MATE-1, CALL the Chemistry Director (TSC) in the Technical Support Center.

REQUEST the Chemistry Director (TSC) provide a steam release duration estimate.

REQUEST the Chemistry Director (TSC) provide a radioactivity release rate estimate for the main steam system.

REQUEST the Chemistry-Director (TSC) provide a source term category (RCS activity, GAP activity, or CORE MELT activity)'for the steam system contamination level.

CHANGE the dose assessment model release assumptions based on the Chemistry Director (TSC) input.

ENTER the release rate data into the dose assessment model using the direct input of release rate function.

RECALCULATE the dose consequences of the release.

PROVIDE the results of the calculations to the Radiological Assessment Director (EOF).

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12

!Page 47 of 55 Page 3 of 3 ATTACHMENT 13, REFINED SOURCE TERM ESTIMATES 40 R efinemen oftheestimate of effluent nnoble gas versus iodine ratio' based on .

-. reY ata.-- -

OBTAIN Offsite Monitoring Team (EOF) survey data from Offsite Monitoring Team (EOF) and use results to redefine, as directed by Radiological Assessment Director (EOF), the source term and projected doses calculated with the dose assessment computer.

USE ERPIP-822, Initial Dose Assessment Manual CalculationMethods, to back calculate a release rate equivalent to field measurements of external exposureand thyroid dose rate for the given meteorological conditions.

ENTER the assumed noble gas and iodine release rate into the dose assessment model using the direct input of release rate function.

USE meteorology appropriate to actual sample time.

RECALCULATE the dose consequences of the assumed release rate based on field sampling.

PROVIDE the results of the calculation to the Radiological Assessment Director (EOF).

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12

.~...... Page 48 of 55 ATTACHMENT 14, ACCIDENT SOURCE TERM BASIC METHOD To approximate a severe accident source term, follow the (NUREG-1 228) method below:

(1) Estimate the amount of fission products in the core or coolant.

(2) Estimate the fraction of the fission product inventory released from the core for a normal coolant release, spiked coolant release, gap release, grain boundary release or melt release.

(3) Estimate the fraction of the fission product inventory released from the core or coolant that is removed on the way to the environment.

(4) Estimate the amount of the available fission product inventory actually released to the environment.

Source estimation for the calculations uses the following formula:

Source termi = FPI,

  • CRFI *j I"1RDF(i4 1
  • EFj for radionuclide i and n reduction mechanisms where:

FPII = element i core or coolant inventory (Attachments 15 &16

-Table 1A & IB)

(Attachment 17 -

CRFi = element i released from core (based on core damage Table 2) state) element i inventory in core (Attachment 18 -

RDFi = element i after reduction mechanisms available for Table 3A & 3B) release element i before reduction mechanisms available for release (Attachment 19 -

EFI = element i released Table 4) element i available for release

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12

.... ~' .Page 49 of 55 ATTACHMENT 15, TABLE 1A (BG&E-EP9) (CORE) FISSION PRODUCT INVENTORY (FPI)

Fission Inventory (Attachment 17) (Attachment 19) (Attachment 20) Source Product (Ci) Table 2 Table 3B Table 4. Term CRF RDF EF Kr-85 6.45E+05 N/A Kr-85m 2.77E+07 N/A Kr-87 5.42E+07 N/A Kr-88 7.84E+07 N/A Xe-133 1.96E+08 N/A Xe-1 35 3.92E+07 N/A 1-131 9.79E+07 1-132 1.38E+08 1-133 1.96E+08 1-134 2.19E+08 1-135 1.73E+08 Cs-1 34 8.64E+06 Cs-1 36 3.46E+06 Cs-1 37 5.42E+06 Te-132 1.38E+08 Sr-89 1.08E+08 Sr-90 4.26E+06 Ba-140 1.84E+08 Mo-99 1.84E+08 Ru-103 1.27E+08 Ru-106 2.88E+07 La-140 1.84E+08 Ce-144 9.79E+07 Np-239 1.84E+09 Total 4.14E+09 Total Noble 3.96E+08 Gases Total lodines 8.24E+08 Total 2.92E+09 Particulates 1: 1 1_1 _1_1

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 Page 50 of 55 NOT~A i i ATTACHMENT 16, TABLE 1 B (BG&E-EP9) (NORMAL COOLANT)

FISSION PRODUCT INVENTORY (FPI)

Fission Inventory (Attachment 17) (Attachment 19) (Attachment 20) Source Product (Ci) Table 2 Table 3B Table 4 Term CRF RDF EF Kr-85 9.17E+01 N/A Kr-85m 3.41E+01 N/A Kr-87 3.20E+01 N/A Kr-88 5.97E+01 N/A Xe-1 33 5.54E+02 N/A Xe-1 35 1.81E+02 N/A 1-131 9.59E+00 1-132 4.48E+01 1-133 2.98E+01 1-134 7.25E+01 1-135 5.54E+01 Cs-134 1.51E+00 Cs-136 1.85E-01 Cs-1 37 2.00+00 Te-132 3.62E-01 Sr-89 2.98E-02 Sr-90 2.56E-03 Ba-1 40 2.77E+00 Mo-99 1.36E+00 Ru-103 1.60E+00 Ru-106 1.92E+01 La-140 5.33E+00 Ce-144 8.53E-01 Np-239 4.69E-01 Total 1.20E+03 Total Noble 9.53E+02 Gases Total lodines 2.12E+02 Total 3.57E+01 Particulates

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 EPage 51 of 55 ATTACHMENT 17, TABLE 2 (NUREG-1228) (1-HOUR RELEASE) CORE RELEASE FRACTIONS (CRF)

Core conditions Fuel cladding Fission product Assumed release temperature fraction from fuel Fuel pin cladding 600OF Use Table 1B 1.0 intact- (normal leakage) normal coolant Spikes resulting from 600OF Use Table 1B 100 x normal rapid shutdown or normal coolant non- coolant non-noble depressurization( core noble gases gases remains covered)

Gap release (cladding 1300°F-2100OF Xe, Kr 0.03 failure) I 0.02 Cs 0.05 Te, Sb 1E-04 Grain boundary release >3000°F Xe, Kr 0.5 I, Cs 0.5 Te 0.1 Sb 0.02 Ba 0.01 Mo 0.01 Sr 1E-03 Ru 1E-04 Core Melt >4500°F Xe, Kr 1.0 (in-vessel) (1)(2) Cs 1.0 I 1.0 Sb 0.02 Te(3) 0.3 Ba 0.2 Sr(3) 0.07 Mo 0.1 Ru 7E-03 La 1E-04 Y 1 E-04 Ce 1E-04 Np 1E-04 (1) Based on Tables 4.8 and 4.9 of NUREG-0956.

(2) For La, Y, Np, and Ce, the Zr release fraction was used, based on BMI-2104, Vol. VI, page 6-24 grouping, Battelle Columbus Laboratories, 1984.

.(3) Ex-vessel (melt-through) melt release fractions may be much larger (0.4 to 0.8).

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12

- ~Page 52 of 55 ATTACHMENT 18, TABLE 3A (NUREG-1228) RELEASE PATHWAY NON-NOBLE GAS REDUCTION FACTORS (RDF)

ELV4 ?ttO RoLa~r"

_aJW~

At9.g4Uez REUEF VALV" - SPRAY CLOSED VAL VE r4ULTER CHECK VALvE -O RELEASE PATAY REFERENCE PUMP I-. 50ISOLAT(ON yALVE RELEASE PATHWAY KEY:

A. Reactor coolant system A-1 Breaks and leaks A-2 Power operated relief valves (PORV)

A-3 Steam generator tube rupture A-4 Bypass (failure into low-pressure system)

B. Containment B-1 Design leakage 0-2 Small isolation valve seal failure B-3 Catastrophic (> lsq. ft.)*

B-4 Bypass C. Other, C-1 Secondary side relief/safety valve or turbine exhaust C-2 Building leakage - unfiltered C-3 Building leakage - filtered C-4 Condenser steam-jet air-ejector

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 4Page 53 of 551 ATTACHMENT 19, TABLE 3B (NUREG-1228) RELEASE PATHWAY NON-NOBLE GAS REDUCTION FACTORS (RDF)

Fission product Table 3A Reduction Non-noble barrier breached Pathway reference mechanism Condition assumed RDF Reactor coolant Break/leak and A-1 None 1.00 system: open PORV A-2 Steam generator A-3 SG partitioning "U" tube secondary side 0.02 tube rupture boiling (dry steam)

'U" tube secondary side solid, 0.50 no boiling Dry steam generator 1.00 Bypass (failure A-4 Primary system For bypass accidents only 0.40 into low-pressure retention system)

Primary containment: Design leakage B-1 Containment 0.5-hour holdup in 0.03 (0.1%-0.25%/day) sprays containment or Small isolation B-2 2- to 12-hour holdup in 0.02 valve seal failure containment (100%/day) or Catastrophic B-3 24-hour holdup in 0.002 failure (100%/hr) containment Natural 0.5-hour holdup in 0.40 processes in containment containment (no spray) 2- to 12- hour holdup in 0.04 containment 24-hour holdup in 0.01 containment Bypass B-4 Same as A-4 Same as A-4 Same as A-4 Other: Secondary side C-1 None 1.00 relief/safety valves and turbine exhaust Building C-2 Natural 0.5-hour holdup in building 0.40 failure/leakage processes 2- to 12-hour holdup in 0.04 (not filtered) (no spray) building 0.01 24-hour holdup in building Through-building C-3 Filters Small release into building 0.01 filters (filters effective)

Large release into building 1.0 (filters blow out)

Steam-et air- C-4 Condenser All noble gases are assumed 0.00 ejector to be released (no non-noble gases released)

ERPIP-511 RADIOLOGICAL ASSESSMENT DIRECTOR (EOF) Revision 12 S . Page 54 of 55 A, 00#,541R, *NE-a-.I ATTACHMENT 20, TABLE 4 (NUREG-1 228) (1 HOUR RELEASE) CONTAINMENT AND STEAM GENERATOR TUBE RUPTURE ESCAPE FRACTIONS (EF)

Release Pathway Escape fraction*

Primary containment failure/leakage Typical design leakage:

PWR - large dry (0.1% day) 4E-5 Failure to isolate (100%:day):

Failure of isolation valve seal 0.04 Catastrophic failures:

1-hr puff release 1 Steam generator tube rupture 1 tube at full pressure (coolant leak) 0.35 1 tube at low-pressure single charging pump 0.03 flow (coolant leak)

  • Fraction of containment volume or primary system coolant inventory released in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

RADIOLOGICAL ASSESSMENT DIRECTOR ERPIP-511 Revision 01204 Page 55 of 55 ATTACHMENT 21, GROUND DEPOSITION FIELD SURVEY DATA REDUCTION A. Select survey point according to ERPIP-B.2, Offsite Survey Points, to perform ground deposition survey according to Offsite Monitoring Team (EOF) procedure.

1. Record survey point _, zone , and distance
2. Record survey time _. Record survey date_.
3. Record monitoring team designation B. Record raw instrument readings.
1. Record beta exposure rate from SHP-270 beta detector with shield open using no beta correction factor. mremnh.
2. Record three gamma count rates from SPA-9 gamma detector and take the average.

1/3 (. cpm + - cpm + - cpm) = average cpm.

C. Multiply raw instrument readings by conversion factors to obtain estimates of ground contamination for specific nuclides.

1. Estimating Sr-90 and Sr-89. (Assume Sr-90/Y-90 equilibrium).
a. Multiply beta reading (B.1) by conversion factor.

2 mrem/h

b. Multiply beta reading (B.1) by conversion factor.

2 mrem/h * -3.4 E-2 = lRCi/m Sr-89

2. Estimating 1-131 and Cs-1 37.
a. Multiply average gamma reading (B.2) by conversion factor.

cpm

  • 6.48 E-5 = tCi/m2 1-131
b. Multiply average gamma reading (B.2) by conversion factor.

cpm

  • 9.36 E-5 = ICi/m2 Cs-1 37 D. Evaluate calculations for initial activity to estimate areas of potential ground contamination.

Record Time:

Date:

Name:

FORWARD completed form to Director - Emergency Preparedness at event termination.

Constellation Energy, Calvert Cliffs Nuclear Power Plant TECHNICAL PROCEDURE ERPIP-822 INITIAL DOSE ASSESSMENT CALCULATION METHODS Revision 00403 Safety Related CONTINUOUS USE Applicable To:

Calvert Cliffs Nuclear Power Plant Approval Authority:

Plant General Manager

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 2 of 27

SUMMARY

OF ALTERATIONS Revision Change Summary of Revision or Change 004 03 Procedure reformatted to new template per the requirements of CNG-PR-1.01-1005, Control of Constellation Nuclear Generation Technical Procedure Format and Content.

Editorial Corrections to Attachment 1, EDE and CEDE Dose Projection Based on Release Rate and Attachment 3, Thyroid CDE Dose Projection Based on Release Rate. Each block in the fill table under Xu/Q/windspeed requires a space for a numerator and a denominator. The division underscore was inadvertently left out of the 2.0, 5.0, and 10.0 mile rows.

Expanded these sections to allow for a numerator and denominator.

RPA-2007-0803 Sections 9.1.1 and 9.1.2., changed PR-3-100 to CNG-PR-3.01-1000, Records Management. PR-3-100 no longer exists. CNG-PR-3.01-1000 is the new fleet procedure.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 3 of 27 1 .0 P UR P O S E .................................................................................................................................. 4 2.0 APPLICABILITY/SCOPE ........................................................................................................ 4

3.0 REFERENCES

AND DEFINITIONS ....................................................................................... 4 3.1 Developmental References ........................................................................................ 4 3.2 Performance References ........................................................................................... 4 3 .3 D efin itio n s .......................................... ................................................................ 5 4.0 PR E R EQ UIS ITES ............................................................................................................. 5 4.1 Training and Q ualifications ......................................................................................... 5 4 .2 Initial C onditions ....................................................................................................... . .5 4.3 Documentation and Support ....................................................................................... 5 5 .0 P R E C AUT IONS .......................................................................... . ............................................ 5 6 .0 P E R FO R MANC E ....................................................................................................................... 6 6.1 Meteorological Data and Release Rate Data ............................................................. 6 6.2 Effecti.e Dose Equivalent and Committed Effective Dose Equivalent (EDE &

C EDE) ............................................................................................................................ 6 6.3 Thyroid Committed Dose Equivalent (CDE) ................................................................ 8 6.4 Simple Site Boundary Dose Rate Calculations Based on Stability Class and Control Room Monitor Reading .................................................................................. 11 7.0 POST-PERFORMANCE ACTIVITIES .................................................................................. 11 8 .0 BAS ES ..................................................................................................................................... 12 9 .0 R E C O R DS ................................................................................................................................ 12 9.1 R ecord R etention ..................................................................................................... 12 ATTACHMENT 1, EDE & CEDE DOSE PROJECTION BASED ON RELEASE RATE ..................... 13 ATTACHMENT 2, WHOLE BODY DOSE PROJECTION BASED ON FIELD DOSE RATE ............. 14 ATTACHMENT 3, THYROID CDE DOSE PROJECTION BASED ON RELEASE RATE .................. 15 ATTACHMENT 4, THYROID DOSE PROJECTION BASED ON FIELD SAMPLE ......................... 16 ATTACHMENT 5, SIMPLE SITE BOUNDARY DOSE RATE CALCULATION FOR MAIN VENT R E LE AS E ............................................................................................................... 17 ATTACHMENT 6, SIMPLE SITE BOUNARY DOSE RATE CALCULATION FOR MAIN STEAM R E LE A S E ............................................................................................................... 20 ATTACHMENT 7, SIMPLE SITE BOUNDARY DOSE RATE ESTIMATE FOR CONTAINMENT LEAKAGE RELEASE .......................................................................................... 24 ATTACHMENT 8, DELETED ............................................................................................................... 26 ATTACHMENT 9, AVERAGE RELATIVE AXIAL CONCENTRATION BY STABILITY CLASS FOR GROUND LEVEL RELEASES ........................................................................... 27

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 4 of 27 1.0 PURPOSE This procedure provides initial dose assessment manual calculation methods for use when an emergency action level is called at Calvert Cliffs Nuclear Power Plant.

2.0 APPLICABILITYISCOPE This procedure applies to the following Emergency Response Organization positions:

  • Radiological Assessment Director (EOF)
  • Radiological Assessment Specialist (EOF)
  • Shift Chemistry Technician (CR)

3.0 REFERENCES

AND DEFINITIONS 3.1 Developmental References 3.1.1 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency response Plans and Preparedness in Support of Nuclear Power Plants 3.1.2 10 CFR 50.47, Emergency Plans 3.1.3 10 CFR 50 Appendix E to Part 50, Emergency Planning and Preparedness for Productions and Utilization Facilities 3.1.4 Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.2 Performance References 3.2.1 ERPIP-107, Chemistry Shift Technician (CR) 3.2.2 ERPIP-507, Off-Site Monitoring Team (EOF) 3.2.3 ERPIP-51 1, Radiological Assessment Director (EOF) 3.2.4 ERPIP-512, Radiological Assessment Specialist (EOF) 3.2.5 ERPIP-821, Accidental Radioactivity Release Monitoring and Sampling Methods 3.2.6 ERPIP-825, Meteorological Data Acquisition Methods

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERevIsion0040 Revision 00403 Page 5 of 27 3.3 Definitions None 4.0 PREREQUISITES 4.1 Training and Qualifications Personnel performing this procedure shall be qualified on the tasks or activities contained in this procedure.

4.2 Initial Conditions One of the following emergency action levels is called at Calvert Cliffs Nuclear Power Plant:

  • Radiological Event
  • Unusual Event

" Alert

" Site Area Emergency

  • General Emergency 4.3 Documentation and Support Forms needed to implement this procedure are contained as attachments to this procedure.

Forms may be computer generated or revised without requiring a change or revision to this procedure, providing the intent is not changed, and the required information is not deleted from the existing form.

5.0 PRECAUTIONS None

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 6 of 27 6.0 PERFORMANCE NOTE Actions are listed in preferred order.

Not all actions are required.

Manual calculations may be used as alternate to computer calculations.

6.1 Meteorological Data and Release Rate Data 6.1.1 DETERMINE stability class using ERPIP-825, MeteorologicalData Acquisition Methods, Attachment 2, Met Data Record.

6.1.2 COMPLETE appropriate attachment in ERPIP-821, Accidental RadioactivityRelease Monitoring and Sampling Methods, for selected monitoring method to determine release rate.

6.2 Effective Dose Equivalent and Committed Effective Dose Equivalent (EDE & CEDE) 6.2.1 CALCULATE combined exposure pathway (EDE & CEDE) using Attachment 1, EDE & CEDE Dose Projection Based on Release Rate.

1. RECORD input data at top of Attachment 1.
a. DETERMINE met data using ERPIP-825, Meteorological Data Acquisition Methods.
b. DETERMINE affected Protective Action Zone (PAZ) from ERPIP-3.0, Immediate Actions, Attachment 5, Protective Action Recommendations.
c. DETERMINE monitoring method using one of the following ERPIPs:
  • ERPIP-107, Chemistry Shift Technician (CR)
  • ERPIP-51 1, Radiological Assessment Director (EOF)
  • ERPIP-512, Radiological Assessment Specialists (EOF)
d. WRITE IN "WRNGM," "CHRRM," or "MSSRM" for monitoring method.
e. DETERMINE release rate using ERPIP-821, Accidental Radioactivity Release Monitoring and Sampling Methods.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Pane 7 of 27 6.2.1.1.e (Continued)

(1) ENTER release rate from ERPIP-821 for each distance (0.7 mi, 2 mi, 5 mi, and 10 mi).

(2) DETERMINE XW./Q (m 2)values based on stability class from table at bottom of Attachment 1 AND ENTER values corresponding to each distance.

(3) ENTER wind speed in meter/second (m/s) for each distance.

(4) DETERMINE dose conversion factor (DCF) value based on time after shutdown, monitoring method and accident type from table at bottom of Attachment 1 AND ENTER value for each distance.

(5) SOLVE:

Release Rate x Dispersion XpdQ (RCi/s) (m-2) X Dose Conversion Factor = Dose Rate Windspeed g (Rem/h)/(gCi/m3) (Rem/h)

(m/s)

NOTE For projected time use 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless otherwise indicated.

(6) PROJECT time that plume will be in affected PAZ AND ENTER value for each distance.

(7) SOLVE:

Dose Rate X Projected Time = Dose (Rem/h) (h) (Rem) 6.2.2 CALCULATE whole body dose using Attachment 2, Whole Body Dose Projection Based on Field Dose Rate.

1. RECORD input data at top of Attachment 2.
a. DETERMINE met data using ERPIP-825, Meteorological Data Acquisition Methods.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 8 of 27 6.2.2.1 (Continued)

b. DETERMINE affected Protective Action Zone (PAZ) from ERPIP-3.0, Immediate Actions, Attachment 5, Protective Action Recommendations.
c. DETERMINE the appropriate hand-held meter to use according to ERPIP-507, Offsite Monitoring Team.
d. WRITE IN "field readings" for monitoring method.
e. IF desired, THEN BACK-CALCULATE release rate using Attachment 1.

(1) OBTAIN monitor readings at selected downwind locations AND ENTER values corresponding to each distance.

NOTE For projected time use 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless otherwise indicated.

(2) PROJECT time that plume will be in affected PAZ AND ENTER value for each distance.

.(3) SOLVE:

Field Dose Rate X Projected Time = Dose (Rem/h) (h) (Rem) 6.3 Thyroid Committed Dose Equivalent (CDE) 6.3.1 CALCULATE thyroid dose (CDE) using Attachment 3, Thyroid CDE Dose ProjectionBased on Release Rate.

1. RECORD input data at top of Attachment 3.
a. DETERMINE met data using ERPIP-825, Meteorological Data Acquisition Methods.
b. DETERMINE affected Protective Action Zone (PAZ) from ERPIP-3.0, Immediate Actions, Attachment 5, Protective Action Recommendations.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 9 of 27 6.3.1.1 (Continued)

c. DETERMINE monitoring method using one of the following ERPIPs:
  • ERPIP-1 07, Chemistry Shift Technician (CR)
  • ERPIP-51 1, Radiological Assessment Director (EOF)
  • ERPIP-512, Radiological Assessment Specialists (EOF)
d. WRITE IN 'WRNGM," "CHRRM," or "MSSRM" for monitoring method.
e. DETERMINE release rate using ERPIP-821, Accidental RadioactivityRelease Monitoring and Sampling Methods.

(1) ENTER release rate from ERPIP-821, Accidental Radioactivity Release Monitoring and Sampling Methods, for each distance (0.7 mi, 2 mi, 5 mi, and 10 mi).

(2) DETERMINE Xp/Q (m-2) values based on stability class from table at bottom of Attachment 3 AND ENTER values corresponding to each distance.

(3) ENTER wind speed in meter/second (Mn/s) for each distance.

(4) DETERMINE dose conversion factor (DCF) value based on time after shutdown, monitoring method and accident type from table at bottom of Attachment 3 AND ENTER value for each distance.

(5) SOLVE:

Release Rate x Dispersion XpIQ X Dose Conversion Factor = Dose Rate (uCi/s) (m"2 ) (Rem/h)/(4iCi/m 3) (Rem/h)

Windspeed g (m/s)

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 10 of 27 6.3.1.1 .e (Continued)

NOTE For projected time use 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless otherwise indicated.

(6) PROJECT time that plume will be in affected PAZ AND ENTER value for each distance.

(7) SOLVE:

Dose Rate X Projected Time = Dose (Rem/h) (h) (Renm) 6.3.2 CALCULATE thyroid dose using Attachment 4, Thyroid Dose Projection Based on Field Sample.

S1. RECORD input data at top of Attachment 4.

a. DETERMINE met data using ERPIP-825, Meteorological Data Acquisition Methods.
b. DETERMINE affected Protective Action Zone (PAZ) from ERPIP-3.0, Immediate Actions, Attachment 5, Protective Action Recommendations.
c. DETERMINE appropriate field method according to ERPIP-507, Off-Site Monitoring Team (EOF).
d. WRITE IN "field sample" for monitoring method.
e. IF desire, THEN BACK-CALCULATE release rate using Attachment 3.

(1) OBTAIN samples at selected downwind locations.

(a) ENTER values corresponding to each distance.

(2) DETERMINE dose conversion factor value based on time after shutdown from table at bottom of Attachment 4.

(a) ENTER value for each distance.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Onrw n 1 ,tf '37 6.3.2.1 .e (Continued)

(3) SOLVE:

Field Dose Conversion Factor Dose Rate Concentrations X (Remlh)I([tCi/cc) (Rem/h)

(Rci/cc)

NOTE For projected time use 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless otherwise indicated.

(4) PROJECT time that plume will be in affected PAZ AND ENTER value for each distance.

(5) SOLVE:

Dose Rate X Projected Time Dose (Rem/h) (h) (Rem) 6.4 Simple Site Boundary Dose Rate Calculations Based on Stability Class and Control Room Monitor Reading.

6.4.1 CALCULATE whole body site boundary dose rate based on main vent monitor readings and stability class using Attachment 5, Simple Site Boundary Dose Rate Calculation ForMain Vent Release.

6.4.2 CALCULATE whole body and thyroid site boundary dose rate based on activity monitor (gross coolant activity) readings and stability class using Attachment 6, Simple Site Boundary Dose Rate Estimate for Main Steam Release.

6.4.3 CALCULATE whole body site boundary dose rate based on containment high range monitor readings and stability class using Attachment 7, Simple Site Boundary Dose Rate Estimate for ContainmentLeakage Release.

7.0 POST-PERFORMANCE ACTIVITIES 7.1 Deactivation 7.1.1 WHEN notified of event termination (that is, center deactivation), THEN COLLECT all records and documentation generated during the event.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 12 of 27 7.1 (Continued) 7.1.2 FORWARD records and documentation to the Director - Emergency Preparedness.

8.0 BASES None 9.0 RECORDS 9.1 Record Retention Records generated by this procedure may be permanent, non-permanent,- or lifetime radiological records depending on the circumstances under which they are generated.

Records shall be captured and controlled as follows:

9.1.1 During an actual event as described in the purpose statement of this procedure, Records shall be considered radiological lifetime records and submitted to the Emergency Preparedness C Unit for final disposition according to CNG-PR-3.01-1000, Records Management.

C

  • Attachment 1, EDE & CEDE Dose Projection Based on Release Rate
  • Attachment 2, Whole Body Dose Projection Based on Field Dose Rate
  • Attachment 3, Thyroid CDE Dose Projection Based on Release Rate
  • Attachment 4, Thyroid Dose Projection Based on Field Sample
  • Attachment 5, Simple Site Boundary Dose Rate Calculation for Main Vent Release Attachment 6, Simple Site Boundary Dose Rate Calculation for Main Steam Release 9.1.2 During a drill or exercise, records shall be considered non-permanent records and submitted to the Emergency Preparedness Unit for evaluation and retention according to C CNG-PR-3.01-1000, Records Management. .C
  • Attachment 1, EDE & CEDE Dose Projection Based on Release.Rate
  • Attachment 2, Whole Body Dose Projection Based on Field Dose Rate
  • Attachment 3,.Thyroid CDE Dose Projection Based on Release Rate
  • Attachment 4, Thyroid Dose Projection Based on Field Sample

" Attachment 5, Simple Site Boundary Dose Rate Calculation for Main Vent Release

" Attachment 6, Simple Site Boundary Dose Rate Calculation for Main Steam Release

. INITIAL DOSE ASSESSMENT CALCULATION METHODS Page i

ERPIP-822 Revision 00403 13 of 27 ATTACHMENT 1, EDE & CEDE DOSE PROJECTION BASED ON RELEASE RATE Stability class Monitoring method Wind speed g(m/s) Release rate (1iCi/s)

Wind direction, degrees from Time of trip or shutdown Affected PAZ Time of release data 0

0 C0 CO XWQ (m-2) DCF (rem/h per jICi/m3)

STABILITY 0.7 2.0 5.0 10.0 TIME AFTER SHUTDOWN (h)

CLASS miles miles miles miles 0. 2 4 6 8 A 5E-6 1.3E-6 6E-7 3E-7 WIDE RANGE NOBLE GAS MONITOR B 1.8E-5 1.8E-6 7.5E-7 4.2E-7 SGTRR 1.4E-4 1.OE-4 7.7E-5 6.1 E-5 5.OE-5 C 5E-5 7E-6 1.5E-6 6.2E-7 SGTRG 3.6E-4 2.6E-4 1.9E-4 1.3E-4 9.7E-5 D 1.5E-4 2.2E-5 6E-6 2E-6 SGTRC 3.5E-4 2.6E-4 1.9E-4 1.3E-4 9.7E-5 E 3E-4 6E-5 1.4E-5 4E-6 WGDTR 4.4E-5 3.6E-5 3.1E-5 2.8E-5 2.6E-5 F 6.5E-4 1.5E-4 4E-5 1.5E-5 FHI 2.3E-5 2.3E-5 2.3E-5 2.3E-5 2.3E-5 G 1.8E-3 4E-4 1E-4 4E-5 LOCAR 1.7E-4 1.3E-4 1.1E-4 9.4E-5 8.4E-5 Use Attachment 9 for XjiIQ beyond 10 miles, if desired LOCAG 4.OE-4 3.1E-4 2.4E-4 1.9E-4 1.6E-4 LOCAC 4.3E-4 3.4E-4 2.7E-4 2.2E-4 1.9E-4 Date CONTAINMENT HIGH RANGE RADIATION MONITOR LOCAR 1.7E-4 1.3E-4 1.1E-4 9.4E-5 8.4E-5 Time LOCAG 4.OE-4 3.1E-4 2.4E-4 1.9E-4 1.6E-4 LOCAC 4.3E-4 3.4E-4 2.7E-4 2.2E-4 1.9E-4 Calculated by MAIN STEAM SYSTEM RADIATION MONITOR SGTRR 4.2E-4 4.OE-4 3.9E-4 3.9E-4 3.9E-4

  • Reviewed by SGTRG 7.7E-4 7.4E-4 7.1E-4 6.9E-4 6.7E-4 SGTRC 4.8E-3 5.6E-3 6.2E-3 6.7E-3 7.OE-3
  • RAD will review Shift Chemistry Technician (CR) calculations at duty turnover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Paqe 14 of 27 ATTACHMENT 2, WHOLE BODY DOSE PROJECTION BASED ON FIELD DOSE RATE Stability class Monitoring method Wind speed !t(m/s) Release rate (gCi/s)

Wind direction, degrees from Time of trip or shutdown Affected PAZ Time of release data Di s'tan~ce" , 'Fielsefate

ý -. Proj. 6~~.rj~se Site Boundary 0.7 X 2.0 x

5.0 x

10.0 x

Other mi X Date Time Calculated by

  • Reviewed by
  • RAD will review Shift Chemistry Technician (CR) calculations at duty turnover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 15 of 27 ATTACHMENT 3, THYROID CDE DOSE PROJECTION BASED ON RELEASE RATE Stability class Monitoring method Wind speed g(m/s) Release rate (VCi/s)

Wind direction, degrees from Time of trip or shutdown Affected PAZ Time of release data 00 C)*

0 XPIQ (m-2) DCF (rem/h per gCi/m*) * (IING)

STABILITY 0.7 2.0 5.0 10.0 TIME AFTER SHUTDOWN (h)

CLASS miles miles miles miles 0 2 4 6 8 A 5E-6 1.3E-6 6E-7 3E-7 WIDE RANGE NOBLE GAS MONITOR B 1.8E-5 1.8E-6 7.5E-7 4.2E-7 SGTRR 0 0 0 0 0 C 5E-5 7E-6 1.5E-6 6.2E-7 SGTRG 0 0 0 0 0 D 1.5E-4 2.2E-5 6E-6 2E-6 SGTRC 0 0 0 0 0 E 3E-4 6E-5 1.4E-5 . 4E-6 WGDTR 0 0 0 0 0 F 6.5E1-4 1.5E-4 4E-5 1.5E-5 FHI 2.4E-9 2.4E-9 2.4E-9 2.4E-9 2.4E-9 G 1.8E-3 4E-4 1E-4 4E-5 LOCAR 2.1E-8 2.1E-8 2.1E-8 2.2E-8 2.2E-8 Use Attachment 9 for XpJQ beyond 10 miles, if desired LOCAG 1.7E-6 2.OE-6 2.3E-6 *2.5E-6 2.6E-6 LOCAC 4.OE-6 5.OE-6 5.4E-6 5.8E-6 6.2E-6 Date CONTAINMENT HIGH RANGE RADIATION MONITOR LOCAR 2.1E-8 2.1E-8 2.1E-8 2.2E-8 2.2E-8 Time LOCAG 1.7E-6 2.OE-6 2.3E-6 2.5E-6 2.6E-6 LOCAC 4.OE-6 5.OE-6 5.4E-6 5.8E-6 6.2E-6 Calculated by_ MAIN STEAM SYSTEM RADIATION MONITOR SGTRR 1.9E-6 2.OE-6 2.OE-6 2.OE-6 2.OE-6

  • Reviewed by t SGTRG 1.6E-4 2.OE-4 2.3E-4 2.4E-4 2.5E-4 SGTRC 2.8E-4 9.6E-4 1.1E-3 1.1E-3 1.2E-3
  • RAD will review Shift Chemistry Technician (CR) calculations at duty turnover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 16 of 27 ATTACHMENT 4, THYROID DOSE PROJECTION BASED ON FIELD SAMPLE Stability class Monitoring method Wind speed Rt(mis) Release rate (liCi/s)

Wind direction, degrees from Time of trip or shutdown Affected PAZ Time of release data DCF (rem/h per iCi/cc)

Time after rem/h Time after rem/h shutdown RCi/cc shutdown RiCi/cc (h) (h) 0.0 2.19E5 5 4.13E5 0.5 2.45E5 6 4.36E5 1 2.72E5 8 4.76E5 1.5 2.97E5 10 5.10E5 2 3.19E5 12 5.45E5 2.5 3.38E5 15 5.85E5 3 3.56E5 24 7.0E5 3.5 3.71E5 48 9.10E5 4 3.87E5 72 1.05E6 4.5 3.99E5 120 1.19E6 Date Time Calculated by

  • Reviewed by
  • RAD will review Shift Chemistry Technician (CR) calculations at duty tumover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 17 of 27 Page 1 of 3 ATTACHMENT 5, SIMPLE SITE BOUNDARY DOSE RATE CALCULATION FOR MAIN VENT RELEASE A. CALCULATE site boundary dose rate based on WIDE RANGE NOBLE GAS MONITOR (1/2-RIC-5415) and MET DRDT delta temperature reading.

1. IF monitor readings are not available, THEN GO TO next page.
2. RECORD monitor Unit 1 WRNG monitor (1-RIC-5415) uCi/s Unit 2 WRNG monitor (2-RIC-5415) uCi/s Total reading - uCi/s..
3. DETERMINE conversion factor based on current stability class.
Aý-0'91 .O.9 -0.8~< Q3,;~+- t2.0,~'~

Stabili Class A B C D E F G Conversion 6E-10 1E-9 3E-9 7E-9 2E-8 8E-8 4E-7 Factor

4. CALCULATE site boundary dose rate as follows:
a. MULTIPLY total reading by conversion factor X REM/H TOTAL (0CI/S) CONVERSION WHOLE BODY SITE FACTOR BOUNDARY DOSE RATE Date Time Calculated by
  • Reviewed by
  • RAD will review Shift Chemistry Technician (CR) calculations at duty turnover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 18 of 27 Page 2 of 3 ATTACHMENT 5, SIMPLE SITE BOUNDARY DOSE RATE CALCULATION FOR MAIN VENT RELEASE A. CALCULATE site boundary dose rate based on MAIN VENT GASEOUS MONITOR (1/2-RE-5415) and MET DRDT delta temperature reading.

1. IF monitor readings not available, THEN GO TO next page.
2. RECORD monitor Unit I Main Vent monitor (I-RE-5415) cpm Unit 2 Main Vent monitor (2-RE-5415) .cpm Total reading --_ _ ._cpm
3. DETERMINE conversion factor based on current stability class.

Stability Class A B C D E F G Conversion 6E-9 1 E-8 3E-8 7E-8 2E-7 8E-7 4E-6 Factor . ...

CALCULATE site boundary dose rate.

a. MULTIPLY total reading by conversion factor.

X = REM/H TOTAL (CPM) CONVERSION WHOLE BODY SITE FACTOR BOUNDARY DOSE RATE Date Time Calculated by

  • Reviewed by
  • RAD will review Shift Chemistry Technician (CR) calculations at duty turnover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 19 of 27 Page 3 of 3 ATTACHMENT 5, SIMPLE SITE BOUNDARY DOSE RATE CALCULATION FOR MAIN VENT RELEASE A. CALCULATE site boundary dose rate based on MAIN VENT PORTABLE RADIATION METER EXPOSURE RATE SURVEY and MET DRDT delta temperature reading.

1. RECORD monitor Unit 1 Main Vent reading R/h Unit 2 Main Vent reading R/h Total reading R/h
2. DETERMINE conversion factor based on current stability class.

DT' 60B,1 to  ; ~to to ~

______-0._~<O9j -0.9 -0.8 -0.3 ~+O8.k& >-2.0 StabilityClass A B C D E F G Conversion 1 E-3 5E-3 1E-2 3E-2 9E-2 3E-1 1 E+Q Factor _ . __

3. CALCULATE site boundary dose rate.
a. MULTIPLY total reading by conversion factor.

X _ REM/H TOTAL (RIH) CONVERSION WHOLE BODY SITE FACTOR BOUNDARY DOSE RATE Date Time Calculated by

  • Reviewed by
  • RAD will review Shift Chemistry Technician (CR) calculations at duty turnover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 20 of 27 Page 1 of 4 ATTACHMENT 6, SIMPLE SITE BOUNARY DOSE RATE CALCULATION FOR MAIN STEAM RELEASE A. CALCULATE site boundary dose rate based on RCS Sample and PRIMARY to SECONDARY LEAK RATE.

NOTE Procedure is valid only if leak rate exceeds Tech. Spec. (3.4.13) limits.

1. IF leak rate and RCS activity during incident is known, THEN GO TO step 5 AND then step 8.
2. OBTAIN primary to secondary leak rate from Control Room Operator(s).
a. IF there is a delay, THEN USE 600 gpm RECORD leak rate:

(A) gpm

3. CALCULATE RCS NOBLE GAS concentration as follows:
a. MULTIPLY recent (before incident) RCS Gas Activity by ratio of ACTIVITY MONITOR (RR-202) gross coolant activity reading taken during incident to ACTIVITY MONITOR (RR-202) gross coolant activity reading taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before incident.
b. IF there is a delay in obtaining (B) or monitor is out of service AND fuel damage is suspected, THEN USE 200 uCi/mL without monitor readings.

(B) x (C) (D) (E) gCI/ML RCS ACTIVITY MONITOR ACTIVITY MONITOR RCS GAS ACTIVITY (RR-202) (RR-202) NOBLE GAS (BEFORE INCIDENT) GROSS COOLANT GROSS COOLANT CONSENTRATION (4CI/ML) ACTIVITY READING ACTIVITY READING (IiCI/ML)

(DURING INCIDENT) (BEFORE INCIDENT)

(CPM) (CPM)

ALSO VALID IF ISOLATED DURING INCIDENT

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 21 of 27 Page 2 of 4 ATTACHMENT 6, SIMPLE SITE BOUNARY DOSE RATE CALCULATION FOR MAIN STEAM RELEASE

4. DETERMINE NOBLE GAS conversion factor based on current stability class.

Stability A B C D E F G Class (F) Conversion 4E-8 9E-8 2E-7 5E-7 2E-6 5E-6 3E-5 Factor

5. CALCULATE WHOLE BODY site boundary dose rate as follows:
a. MULTIPLY leak rate by RCS NOBLE GAS concentration by stability class Conversion Factor.

(A) X (E) X (F) = (G) Rem/h Leak Rat e RCS Conversion Whole Body (gpm) Noble Gas Factor Site Boundary Concentration Dose Rate

([tCi/mL)

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Paae 22 of 27 Page 3 of 4 ATTACHMENT 6, SIMPLE SITE BOUNARY DOSE RATE CALCULATION FOR MAIN STEAM RELEASE

6. CALCULATE RCS IODINE concentration as follows:
a. MULTIPLY most recent (before incident) RCS Iodine Dose Equivalent by ratio of ACTIVITY MONITOR (RR-202) selected isotope reading taken during incident to ACTIVITY MONITOR (RR-202) selected isotope reading taken 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before incident.
b. IF there is a delay in obtaining (H) AND fuel damage is suspected, THEN USE 60 uCi/mL without monitor readings.

(H) X (I) (J) __Ci/mL RCS Iodine ACTIVITY ACTIVITY (+) -- Ci/mL MONITOR MONITOR (spike)

Dose (RR-202) (RR-202) (K) pgCi/mL Equivalent (before selected Selected RCS incident) isotopes isotopes (g*Ci/mL) reading reading Iodine (during incident) (before Concentration incident)

(cpm) (cpm) also valid if isolated during incident

7. DETERMINE IODINE conversion factor based on current stability class.

Stability Class (L) Conversion Factor

8. CALCULATE THYROID site boundary dose rate as follows:
a. MULTIPLY leak rate by RCS IODINE Concentration by stability class Conversion Factor.

(A) X (K) X (L) =(M) Rem/h Leak Rate RCS Conversion Thyroid (gpm) Iodine Factor Site Boundary Concentration Dose Rate (l.Ci/mL)

9. IF RCS sample taken during incident is available, THEN GO TO step 10.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 23 of 27 Page 4 of 4 ATTACHMENT 6, SIMPLE SITE BOUNDARY DOSE RATE CALCULATION FOR MAIN STEAM RELEASE

10. DETERMINE maximum dose rates as follows:
a. OBTAIN RCS sample results obtained during incident.
b. MULTIPLY calculated dose rates by ratio of RCS sample concentration taken during incident to calculated RCS sample concentration.
11. REPEAT steps 5 and 8 of this attachment.

(G) X (N) X (E) () Rem /h Whole Body Total Noble RCS Maximum Gas Site RCS Sample Noble Gas Whole Body Boundary Site Dose Rate (during incident) Concentration Boundary (Rem/h) (IiCi/mL.) (liCi/mL) Dose Rate (M) X (P) X (K)= (Q) Rem/h Thyroid Total Iodine RCS Maximum Site RCS Sample Iodine Thyroid Site Boundary Dose Rate (during incident) Concentration Boundary (Rem/h) (jiCi/mL) (piCi/mL) Dose Rate Date Time Calculated by

  • Reviewed by
  • RAD will review Shift Chemistry Technician (CR) calculations at duty turnover.

FORWARD completed record to Emergency Preparedness Unit at event termination.

A C I I.i rit 1621#1: axis axis 0 i 4'p 4 v 3 a S.*PV II A4 611t V) m cn CAI r-B m 0

axis CI) 0C)

CI cI-stability Class m m m-z z 0:-

A B. IE72 C OK-O2 0 D z - -I E >_m mm z G U)

Meteorology

-0 m

  • axis -IE MZ 0 0 z >
  • + Co IE2 mH m0 m>

CQ.>

`..

Oy Retepae

.axis.

00o3eHate

,axsa m

m C-t Dose Rate axis R/hr 0

cc m CD 0 5.

"1' 0 4%0

A C axis 0

(1n m

B tE-3 axis C,,

CI.

on 1 OCAT.CRIMfssn .xa -~,xis.

buline-fro00. eat.04R L DREa rtics C*)

xI i)t w.p

.W m cwatilr *Stability' 10-2 CO)

Class C' m rn A

B 2, IE-I 0 z

-4 z

--I 0

C D I-E 0 a

F z 0 G I Meteorology U* -1r - z axDS m

-1 0 X 0

I22 -n, mm CO)

ZCO>

m Dose Rate Co axis 16i10Rele~se i(R/hr)

1 1 XeS

.0 m

(D 0 A.* CO

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 26 of 27 ATTACHMENT 8, DELETED USE ERPIP-3.0, IMMEDIATE ACTIONS, ATTACHMENT 5, GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS.

INITIAL DOSE ASSESSMENT CALCULATION METHODS ERPIP-822 Revision 00403 Page 27 of 27 ATTACHMENT 9, AVERAGE RELATIVE AXIAL CONCENTRATION BY STABILITY CLASS FOR GROUND LEVEL RELEASES z

'-U 0

cl:

DISTANCE DOWNWIND

Constellation Energy, Calvert Cliffs Nuclear Power Plant TECHNICAL PROCEDURE ERPIP-508 EMERGENCY OPERATIONS FACILITY PLANTI PARAMETERS COMMUNICATOR (EOF)

Revision 00700 Safety Related, REFERENCE USE Applicable To:

Calvert Cliffs Nuclear Power Plant Approval Authority:

Plant General Manager

EMERGENCY OPERATIONS FACILITY PLANT PARAMETERS ERPIP-508 COMMUNICATOR (EOF) Revision 00700 Page 2 of 13

SUMMARY

OF ALTERATIONS Revision Change Summary of Revision or Change 007 00 This procedure was updated to the Fleet.Technical Procedures Template and included the requirements of CNG-PR-1.01-1 005, Control of Constellation Nuclear Generation Technical Procedure Formatand Content.

Revised procedure to reflect the ERO Web Page to displayinformation.

Existing versionmof procedure had :the Emergency Operations Facility Plant Parameters Communicator (EOF) displayihg information on grease.boards.

This included the removal of all references to using a scanner since the information is now available on the EROWeb Page.

Step 2.3 (from previous version of procedure):

The new Fleet format does not allow for a Responsibilities section. As such, the duties/responsibilities of EOF Plant Parameters Communicator (EOF) have been moved to Section 4.0, Prerequisites.

Step, 3.1:

Arranged list in alphabetical order and updated references to align with those of Fleet. [RPA-2007-1 054]

Stepý 3.2:

Updated Performance-Referencestto align procedures with those of Fleet.

[RPA-2007-1054]

Step 6.2:

Rewrote subsection for using the ERO.Web-Page to,display information.

This was done to support IRE-032-954.

Step 6.3.1.1.g:

Added printer to be turned off. [RPA-2007-1054]

Step 6.3.1.2:

Changed. "SHUTDOWN' to "LOG OFF".

Step 6.3.1.3:

Added step to remind user to turn off the.monitor attached tolthe Emergency Operations Facility Plant. Parameter Commdnicator's computer.

Section 8.0 - updated [B-1] to [B2504].

EMERGENCY OPERATIONS FACILITY PLANT PARAMETERS ERPIP-508 COMMUNICATOR (EOF) Revision 00700 Page13 of 13 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 P UR P O S E ............................................................................................... ........ . . . ....... ...... ..4......

4 2.0 APPLICABILITY/SCOPE ...................................................... 4 2.1 A pplicability .................................................. ....................... ............. 4......................

4 2 .2 S cope . I................... .......... . . ...................................................... 4

3.0 REFERENCES

AND DEFINITIONS ....................................... 4 3.1 Developm ental R eferences ................. ....... ........................ . ........ I........................... 4 3.2 Performance References ..................................... ......... ............ 5 3.3 Definitions ............. ...... "  ;....... ......  :.....5 4.0 PREREQUISITES...... ..... ............................. ........... 5 4.1 Training and.Qualification ............................. .. ............ 5 4.2 Documentation and Support ........ *............ . ............. .......

. 5 4,3. Initial Conditions ........................ ........................ ...... 6 5:0. PRECAUTIONS ...................... I ......................................... 7 6 0 P E R FO R MA NC E ...................................................... ....... .................................................... 7 6.1 Activation .................................... .......... ......7 66.3

.1 O peratio n ..... ....................................

Dpeaciation........... ............  : ..................................................

.. ........................... 77.....................

97 6 .3 . D e a ctivatio n ... -

..................................... .......... * .... ... ...... . .... ......... ...I. ............. ..... ,..... 9 7,0 POST PERFORMANCE ACTIVITIES .......................... ............ 10 8 .0 BA S ES ...... . . ...................................................... . ......

... ... ..... ................. ................... *...... 10 9,0 R EC O R D S ........ ........

.......... . . ............................................................................. ............ ..... 10 ATTACHMENT 1, PLANT PARAMETERS STATUS FORM.*.,.0... .................. . . ...... 1 ATTACHMENT2, ENVIRONMENTAL STATUSiFORM..............................-........ . .......

...... 13

EMERGENCY OPERATIONS FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page 4 of 13 1.0 PURPOSE This procedure provides emergency response instructions to the Emergency Operations Facility Plant Parameters Communicator (EOF) when, responding to an emergency action level called at Calvert Cliffs Nuclear Power Plant.

2.0 APPLICABILITY/SCOPE

.2.1 Applicability 2.1.1 This procedure applies to the Emergency Operations Facility Plant Parameters Communicator (EOF).

2.1.2 Performance of this procedure is in the order of Activation (Subsection .6. 1), Operation (Subsection 6.2) and Deactivation (Subsection 6.3).

2.2 Scope 2.2.1 Performance of the actions in the order they are presented in Subsection 62, Operation, is not mandatory provided Subsection 6.1, Activation, has been completed.

3.0 REFERENCES

AND DEFINITIONS 3.i Developmental References 3.1.1 Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.1.2 CNG-PR-1.01-1005, Control of Constellation Nucleatr Generation Procedure. Format and Content 3.1.3 CNG-PR-1.01-1009, Procedure Use and Adherence Requirements 3.1.4 CNG-PR-01.1-1Q11, Control of Station-Specific ProcedureChange Pr6cess*

3.1.5 CNG-PR-3.01 -1000, Records Management 3.1.6 NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergencyl response Plans and Preparedness in Support of Nuclear.Power Plants

EMERGENCY OPERATIONS FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page 5 of 13 3.1 (Continued) 3.1.7 PR-1-101, Preparation and Control of Calvert Cliffs Technical Procedures 3.1.8 PR-I1-103. Use of Procedures 3.1.9 Technical Procedures Writer's Manual 3.1.10 10CFR 50.47, Emergency Plans 3.1.11 10 CFR 50 Appendix E to Part 50, Emergency PFlanning and'Preparedness for Production and Utilization Facilities 3.2 Performance References 3.2.1 Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.2.2 CNG-PR-3.01 -1000, Records Management 3.2.3 TSC Computer Operators: Guide 3.3 Definitions None 4.0 PREREQUISITES 4.1 Training and Qualification 4.1.1 Personnel performing this procedure shall be qualified on the tasks or activitiescontained in this procedure.

4.2 Documentation and Support 4.2.1 Forms needed toimplement this procedure arecontained as attachments to*this .procedure.

Forms may be computer generated or revised without requiring a changeýorxrevision to this procedure, providing the intent is not changed, and the required information is not deleted from the existing forms.

  • 4.2.2 The Emergency Operation Facility :Plant Parameters Communicator (EOF) shall:
  • Report directly to the Emergency; operations Facility Director (EOF)).
  • *~Obtain plant parameters.
  • Display or make available Plant Parameter status;
  • Maintain documentation for. records .retention.

EMERGENCY OPERATIONS FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page.6 of 13 4.3 Initial Conditions 4.3.1 One of the fo1lowing emergency action levels is called at:Calvert Cliffs

  • Nuclear Power Plant:
  • Alert o Site Area Emergency o General Emergency

EMERGENCY OPERATIONS. FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page, 7 of 13

.5.0 PRECAUTIONS Declared'pregnant women and minors are not authorized to performnemergency functions.

6.0 PERFORMANCE 6.1 Activation 6.1.1 REPORT to the EOF on notification of an Alert, Site AreaEmergency or General Emergency.

6.1.2 NOTIFY EOF of your presence.

NOTE:

The stepsin ;Subsection 6.2 may be performed in any order, 6.2 Operation 6.2.1 RETRIEVE information from the Emergency Response. Web-Page, 6.2.2 DISPLAY or DISTRIBUTE plant parameters status (this may be delegated).

6.2.3 ACTIVATE the Technical Support Center (TSC) computer workstation.

1. TURN on the computer, monitor and printer.
2. RESPOND to screen prompt BY PRESSING -<Ctrl+ Alt + Del> to log on.
3. ENTER password 'BGE" (thisý is .case sensitive) at prompt .AND PRESS <Enter>.

EMERGENCY OPERATIONS FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page 8 of 13 6.2 (Continued) 6.2.4 RETRIEVE plant parameter status.data from the TSC Computer (sample.

form shown as Attachment 1,*Plant Parameters Status Form).

NOTE:

Main Vent Gas Monitor indication for U-1 "R5415A" iS only available from the U-2 TSC point display. The U-2 icon from the "BG&E SDS" grou,p, will need to be selected for R5415A indication.

1. SELECT the affected Unit icon, U-1, U-2 or SIMTSC (for drills), from the. group labeled "BG&E SDS."
2. TYPE "GD PPSTAT1"at the prompt on the main screen (yellow box.at the. top of screen) AND PRESS <Enter>.
3. PRINT data as necessary (Page 1 & 2):
a. SELECT Print from the tool bar.
b. PRESS <Page Up> AND <Page Down> keys. to change from Page 1 to.2.
c. CLICK on Print.
4. REPEAT steps 6.2A4,1 6.2.4,2,. and 6.2.4.3 as necessary for

'GD PPSTAT2."

NOTE Clicking on "REFRESH" will retrieve the most current data..

6.2.5 IF both tthe TSC Computer and the. Emergency Response Web Page are not operable, THEN:'

1. NOTIFY Control Room*Plant Parameters CommunicatOr (CR).
2. REQUEST plant'parameters AND RMS data be transmitted. by facsimile machine, telephone or runner.

6.2.6 CHECK the plant.parameterfacsimile machine for incoming "Initial Notification" forms AND DELIVER them promptly to the Emergency Director (EOF) (this may be delegated). [B2504]

EMERGENCY OPERATIONS FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page 9.of 13 6.2 (Continued) 6.2.7 PROVIDE RMS data (as listed on Attachment 1) to the Dose Assessment Room for delivery to the Radiological Assessment Specialist (EOF) (this.

may be delegated).

1. REPORT the significant plant parameter changes to the Emergency Operations Facilities Director (EOF).

NOTE The Dose Assessment Office electronically updates the eiectronic form for the Environmental Status data.

6.2.8 DISPLAY environmental status data via the Emergency Response Web Page.

6.2.9 IF Emergency Response Web Page is not: operable, THEN:

1. OBTAIN environmental status data (sample shown on Attachment 2, Environmental Stfatus Form). from the Radiological Assessment Director (Dose-Assessment Office).
2. TRANSMIT environmental status data by facsimile mrachine, telephone or runner to the following locations:
  • Technical Support-Center
  • Operational Support Center
3. NOTIFY respective centers of the data transmission method being used, if other than the Emergency Response Web Page.

6.2.10 ASSESSplant parameters data for unexpected values and-trends AND INFORM Emergehcy Director (EOF) AND Radiological Assessment Director (EOF) OR Environmental Assessment Director (EOF) (or both), of aberrant OR noteworthy (or both) data.

6.3 Deactivation 6.3.1 WHEN notified of eventtermination, THEN:

1. DEACTIVATE the T$SC. Computer workstation.
a. PRESS <Esc> to return to main screen.
b. PRESS <X> on ke~rboard- ( will appear at SDS' LOGO on top.

right of screen).

EMERGENCY OPERATIONS FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page 10 of 13 6.3.1.1 (Continued)

c. PRESS <Enter>.
d. SELECT File from Program Manager group.

e, SELECT Shutdown from File Menu.

f. SELECT ShutdoWn from Shutdown Computer window AND THEN OK.
g. TURN OFF computer, CRT and printer.
2. LOG OFF the.Emergency:Operations Facility Plant Parameter Communicator's (EOF) computer used to access the Emergency Response Web.Page.
3. TURN OFF the monitor.
4. COLLECT records generated during the event.
5. RETURN equipment AND unused material-to the designated storage locations AND DISPOSE:of trash in the appropriate locations.
6. FORWARD records toEmergency Operations Facility Director (EOF) for turnover to the Director - Emergency Preparedness.

7.0 POST PERFORMANCE ACTIVITIES None

.8.0 BASES.,

1[B2504] AIT 1R200000788Milesto6he #8;,..CCNPP did not meet the.site target of 97ý5 percent of'NRC Revised Reactor Oversight Process, 9..0 RECORDS Records generated by this procedure may be. permanent, non-permanenti,or lifetime radiological records depending .on thecircumstances under which they are: generated.

Records shall be: captured and.controlled as follows:

9.1 During an actual event-as described in the purpose statement of this procedure, records shall be considered permanent-records and.submitted to the. EmergencyPreparedness:Unit for final disposition adccrding to CNG-PR-3101-1000, Records Managemrent.,

Attachment 1, Plant Parameters Status-Form 40 Attachment 2, Environmental Status Form

EMERGENCY OPERATIONS FACILITY PLANT ERPIP-508 PARAMETERS COMMUNICATOR (EOF) Revision 00700 Page 11 of 13 9.2 During an actual event as described ,in the purpose statement of this procedure; dosimetry records, that is,.any dose-related record including.access, history records, are considered radiological lifetime records and are to be handled.and maintained according to standard' practices-and unit procedures.

  • None 9.3 During a drill or exercise, records generated shall be considered non-permanent records and submitted to.the Emergency Preparedness Unit .for evaluation.

" Attachment 1, Plant Parameters Status Form

  • Attachment-2, Environmental Status Form

EMERGENCY OPERATIONS FACILITY PLANT PARAMETERS COMMUNICATOR (EOF) ERPIP-508 Revision 00700 Page 12 of 13 ATTACHMENT1, PLANT PARAMETERS STATUS FORM EMERGENCY CLASS: TIME DECLAREDI__ AFFECTED UNIT. _. _

R~EACTOR COOLANT SYBlEM*.-- REACTOR: STATUS. CRITICAL SHUTDOWN RCS FLOW S60LED PZR LBIL fCOOLhNTT~b~P. IF P ~rT ClVCS RVLMS LOO________RE -LETDN. Ci-fARGE CHIA CHS

¶ rni)i T% Tc Tm FO F,.OW UNAFFECTED UNIT STATUS T1NE 12 2 HOT CL/ (*F); CF) (¶F)M (Tf). mF) -F) (V) -F) ('F) - (N)mIN UNIT #___._

(gpm) ( IN TSZM TSCM LIlOX T112 TIi2 Tl 12 T122 T122 T122 QICHA 02CHS 03CKA 04CHE LciA- L218-11A F121A LiIOXI PIU5A F2J2 F212 RCSA -RCSB L11O0' HA CA 0B RH A c e mr MA ".' MA L2EA L2EB Li on I OPERATING PW:_  %

SHUTDOWN _

MODE

$TEAM, GENERATOR, STATUS EIVIERGENCY SYSTEMS

- ~PFSTATZ~ ýýZ MISCELLANEOUS DATA S)GLEVEL G RSREAUX( FE FLOW KPS) FLOW LPS21 FLOW CNTMT.,SPRAY RWr OFFSITE POWER: ýAVALABLE . ( I (gpm) LEVL NOTAVAILABE ( )

I 2 1 -2 1 2 I.0l .2 A 8 A a 2 FA609 E4510. F4524 F4534 L4143 cIES.. NON-1.1`141) L1124D. RP91 P4CrO TURB TURB 'rm MTR F31%I 321%, F331% F341 % F306. F4148% F4149%____ ,GEmRcR OPERABLE OPERABLE IA ( I I I 18B ( ) .( )

2c 2A.

OC ()I (.I CONTAIN WENT STATUS - - RMIS ATA Týru' CNTVM TEMP PRESS, 7P- 1 -6 T

F, H2. H, H2 2Y CONT1N'B4 SJP LEVEL LA4148 417J 1.

W#kNTGIAS (KiP1))

tQ2TSC ohhi Hb~lt^

WRN cu~isac)

R6416 j!41t CONTAI NlK:1 Hi RAN E R537421W1 MA I N]

AD. MONITOR (Rfh)

PRh 522.1 SIGNIFICANT PLANT PROBLEMS TIME I ORWARD'record t6oEhiurgency Prepoa ness atmergencylterminatlon, Date

'Itiung Contro) Board indications thien convert tolKCPM byyocisdinat!on.

1000,

EMERGENCY OPERATIONS FACILITY PLANT PARAMETERS COMMUNICATOR (EOF) ERPIP-508 Revision 00700 Pacie 13 of 13 ATTACHMENT 2, ENVIRONMENTAL STATUS FORM METEOROLOGICAL DATA TIME A.T .N.D WIND SPEED STABILITY CLASS (oC) DIRECT.iON .MPH MIS IF BEING USED RADIOLOGICAL RELEASE DATA MPH

_ /8, TIME OFRELEASE:

TYPEMOF.RELEASE:

RELEASE POINT:

EST. RELEASE0DURATION' RELEASECOMPOSITION:

WTCOND.ITIONS. . -

PROTECTIV-EAC2TION RECOMMENDATIONS LOcATiON (SECTORZONE) ACTION TIME DATE FORWARD recordlo-Eme'rgency Preparedness a.it emergency termination. Date

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