LIC-03-0098, Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP)

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Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP)
ML032040588
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 07/14/2003
From: Ridenoure R
Omaha Public Power District
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-03-0098 EPIP-EOF-11
Download: ML032040588 (12)


Text

Onma bic Powr DOitct 444 South 16th Street Mall Omaha NE 68102-2247 July 14,2003 LIC-03-0098 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

Transmittal of Changes to Emergency Plan Implementing Procedures (EPIP)

In accordance with 10 CFR 50.54(q), 10 CFR 50, Appendix E, Section V, and 10 CFR 50.4(b)(5), please find EPIP packages enclosed for the Document Control Desk (holder of Copy 165) and the NRC Region IV Plant Support Branch Secretary (holder of Copies 154 and 155).

The document update instructions and summary of changes are included on the Confirmation of Transmittal from (Form EP-1) attached to each controlled copy change package. Please return the Confirmation of Transmittal forms by August 29, 2003.

The revised documents included in the enclosed package are:

EPIP Index page 1 of 3 issued 07/02/03 EPIP EOF-l 1 R20 issued 07/02/03 If you have any questions regarding the enclosed changes, please contact Mr. Carl Simmons at (402) 533-6430.

V-W Sincerely, c:

NRC Region IV Plant Support Branch Secretary (2 sets)

Alan Wang, NRC Project Manager (w/o enclosures)

J. G. Kramer, NRC Senior Resident Inspector (w/o enclosures)

Emergency Planning Department (w/o enclosures)

Employment with Equal Opportunity 4045 4171

FORM EP-1 Rev. 6 (04/29/99)

OMAHA PUBLIC POWER DISTRICT Confirmation of Transmittal for Emergency Planning Documentsflnformation m Radiological Emergency Z Emergency Plan e

s Emergency Planning Response Plan (RERP)

(EPIP)

Forms (EPF)

LI Emergency Planning Department Manual i1 Other Emergency Planning Document(s)/

(EPDM)

Information Transmitted to:

Name:

Document Control Desk CODy No: 165 Division of Reactor Safety Copy No: 154 Attn: Senior Emergency Preparedness Inspector Division of Reactor Safety CoDv No: 155 Attn: Senior Emergency Preparedness Inspector Date:

The following document(s) I Information are forwarded for your manual:

REMOVE SECTION INSERT SECTION EPIP Index page 1 of 3 issued 06/19/03 EPIP Index page 1 of 3 issued 07/02103 EPIP EOF-11 I R19 issued 04/03/03 EPIP EOF-11 R20 Issued 07/02/03 Summary of Changes:

EPIP EOF-1 I was revised per writers guide. Also revised to clarify how emergency worker extensions are made.

ISi' Supervisor - Emergency Planning I hereby acknowledge receipt of the above documentslinformation and have Included them In my assigned manuals.

Signature:

Date:_

Please sign above and return by 08129103 to:

Beth Nagel Fort Calhoun Station, FC-2-1 Omaha Public Power District 444 South l 6 h Street Mall Omaha. NE 68102-2247 NOTE: If the document(s)/information contained in this transmittal Is no longer requested or needed by the recipient, or has been transferred to another individuals, please fill out the Information below.

i Document(s)/Information No Longer Requested/Needed I Document(s)/lnformation Transferred to:

Name:

Mailing Address:

Fort Calhoun Station Emergency Plan Implementing Procedure Index EPIP Page 1 of 3 Document Document Title Revislon/Date EPIP-OSC-1 Emergency Classification R35 05-02-02 EPIP-OSC-2 Command and Control Position Actions/Notifications R42 05-28-03 EPIP-OSC-9 Emergency Team Briefings R7 12-09-99 EPIP-OSC-15 Communicator Actions R22 10-24-OOa EPIP-OSC-21 Activation of the Operations Support Center R12 10-29-02a EPIP-TSC-1 Activation of the Technical Support Center R24 06-19-03 EPIP-TSC-2 Catastrophic Flooding Preparations R3 01-23-03 (RO 03-22-95) DELETED (05-09-95)

REINSTATED EPIP-TSC-8 Core Damage Assessment R14 01-19-01 EPIP-EOF-1 Activation of the Emergency Operations Facility R13 10-29-02 EPIP-EOF-3 Offsite Monitoring R18 11-12-02 EPIP-EOF-6 Dose Assessment R32 01-23-02a EPIP-EOF-7 Protective Action Guidelines R14 04-15-03 EPIP-EOF-10 Warehouse Personnel Decontamination Station RIO 01-13-OOa Operation EPIP-EOF-11 Dosimetry Records, Exposure Extensions and R20 07-02-03 Habitability July 2, 2003 7:27:10am

FORT CALHOUN STATION EPIP-EOF-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 1 OF 9 DOSIMETRY RECORDS, EXPOSURE EXTENSIONS AND HABITABILITY NON-SAFETY RELATED

1. PURPOSE 1.1 This procedure provides instruction for issuing dosimetry, maintaining dosimetry records and habitability during declared emergencies.
2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Code of Federal Regulations (10 CFR 20 and 10 CFR 50) 2.2 RP-201, Radiation Work Permits 2.3 RP-203, Air Sample Collection and Analysis 2.4 RP-204, Radiological Area Controls 2.5 RPI -6, Alternate Access Control of Radiologically Controlled Area 2.6 FC-RP-214-3, RCA Access Refresher Briefing 2.7 EPIP-EOF-21, Potassium Iodine Issuance 2.8 SAP-19, Dosimetry Issue Emergency Personnel 2.9 EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.10 Ongoing Commitment Documents AR 11809, LIC-91-189R
3. DEFINITIONS None
4. PREREQUISITES None R20

FORT CALHOUN STATION EPIP-EOF-1 I EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 2 OF 9

5. PROCEDURE NOTE: Radiation Work Permits are required for all normal entries into a Radiation Controlled Area. Entries under emergency conditions may be exempted from the RWP requirement if approved by Radiation Protection personnel. This approval may be granted by a Shift Radiation Protection Technician, a Radiation Protection Coordinator or a Protective Measures Coordinator. Radiation Protection personnel must accompany any personnel making an entry without an approved RWP.

NOTE: TLDs will normally be obtained from Security when reporting to the site. Extra TLDs are available at the Security buildings, and will be issued to those who need them per SAP-1 9.

5.1 To perform dosimetry issuance in the Control Room, use Attachment 6.1.

5.2 To perform dosimetry issuance in the Technical Support Center, use Attachment 6.2.

5.3 To perform dosimetry issuance in the Operations Support Center, use.3.

5.4 To perform dosimetry issuance in the Emergency Operations Facility use.4.

5.5 To approve emergency worker exposure, use Attachment 6.5.

5.6 To perform habitability surveys, use Attachment 6.6.

5.7 Retain all documentation (logs, assessments, etc.) generated or used during the emergency. At the termination, deliver all documentation to the TSC Administrative Logistics Coordinator in the TSC, or the EOF Administrative Logistics Manager in the EOF.

6. ATTACHMENTS 6.1 Dosimetry Issuance in the Control Room 6.2 Dosimetry Issuance in the Technical Support Center 6.3 Dosimetry Issuance In the Operations Support Center 6.4 Dosimetry Issuance in the Emergency Operations Facility 6.5 Approving Emergency Worker Exposure 6.6 Performing Habitability Surveys R20

FORT CALHOUN STATION EPIP-EOF-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 3 OF 9.1 - Dosimetry Issuance in The Control Room

1. Obtain the Dosimetry Issue Kit from the Control Room Emergency Gear Locker.
2. IF a Radiation Control Area (RCA) access point has been established at the Control Room exit, THEN perform the following. Otherwise, go to Step 3.

2.1 Determine the range of the SRDs (Self Reading Dosimeters) to be issued, from the Shift Radiation Protection Technician or the Radiation Protection Coordinator.

2.2 Zero all dosimeters prior to issue.

NOTE: If the individual is leaving site or reporting to the TSC, OSC or another location not requiring an RWP, determine dosimetry requirements per the Shift Radiation Protection Technician or the Radiation Protection Coordinator.

2.3 Issue a self reading dosimeter to all personnel who are entering the RCA and do not have an electronic alarming dosimeter (EAD).

2.4 Record dosimetry issue and RCA access information on Form FC-RP-214-2.

2.5 Upon return of the individual(s), record the RCA exit and accumulated dose information on Form FC-RP-214-2.

3. For personnel who are dispatched to an RCA to perform a job that requires a Radiation Work Permit, perform the following:

3.1 Determine if a SRD is required to be worn while in transit to the normal RCA access point, and issue per Step 2.

3.2 Instruct personnel to go to the main access control point to obtain an EAD and sign in on the required RWP.

3.3 For personnel who were issued a SRD per Step 2.1, report any difference in the SRD versus EAD dose to the Shift RP Technician, as this may indicate that dose was accumulated while in transit to and from the normal RCA access point.

4. If Radiation Protection personnel determine it is necessary for all individuals to wear a TLD, issue TLDs to personnel who do not have a TLD using Form FC-1 189.

R20

FORT CALHOUN STATION EPIP-EOF-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 4 OF 9.2 - Dosimetry Issuance In The Technical Support Center (TSC)

1. Obtain the Dosimetry Issue Kit from the TSC Emergency Gear Locker.
2. IF a Radiation Control Area (RCA) access point has been established at the TSC exit, THEN perform the following. Otherwise, go to Step 3.

2.1 Determine the range of the SRDs (Self Reading Dosimeters) to be issued, from the Shift Radiation Protection Technician or the Radiation Protection Coordinator.

2.2 Zero all dosimeters prior to issue.

NOTE: If the individual is leaving site or reporting to the OSC, Control Room or another location not requiring an RWP, determine dosimetry requirements per the Shift Radiation Protection Technician or the Radiation Protection Coordinator.

2.3 Issue a self reading dosimeter to all personnel who are entering the RCA and do not have an electronic alarming dosimeter (EAD).

2.4 Record dosimetry issue and RCA access information on Form FC-RP-214-2.

2.5 Upon return of the individual(s), record the RCA exit and accumulated dose information on Form FC-RP-214-2.

3. For personnel who are dispatched to an RCA to perform a job that requires a Radiation Work Permit, perform the following:

3.1 Determine if a SRD is required to be worn while in transit to the normal RCA access point, and issue per Step 2.

3.2 Instruct personnel to go to the main access control point to obtain an EAD and sign in on the required RWP.

3.3 For personnel who were issued a SRD per Step 2.1, report any difference in the SRD versus EAD dose to the Shift RP Technician or the Radiation Protection Coordinator, as this may indicate that dose was accumulated while in transit to and from the normal RCA access point.

4. If Radiation Protection personnel determine it is necessary for all individuals to wear a TLD, issue TLDs to personnel who do not have a TLD using Form FC-1 189.

R20

FORT CALHOUN STATION EPIP-EOF-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 5 OF 9.3 - Dosimetry Issuance In The Operations Support Center (OSC)

1. Obtain the Dosimetry Issue Kit in the OSC.
2. IF a Radiation Control Area (RCA) access point has been established at the OSC exit, THEN perform the following. Otherwise, go to Step 3.

2.1 Determine the range of the SRDs (Self Reading Dosimeters) to be issued, from the Shift Radiation Protection Technician or the Radiation Protection Coordinator.

2.2 Zero all dosimeters prior to issue.

NOTE: If the individual is leaving site or reporting to the TSC, Control Room or another location not requiring an RWP, determine dosimetry requirements per the Shift Radiation Protection Technician or the Radiation Protection Coordinator.

2.3 Issue a self reading dosimeter to all personnel who are entering the RCA and do not have an electronic alarming dosimeter (EAD).

2.4 Record dosimetry issue and RCA access information on Form FC-RP-214-2.

2.5 Upon return of the individual(s), record the RCA exit and accumulated dose information on Form FC-RP-214-2.

3. For personnel who are dispatched to an RCA to perform a job that requires a Radiation Work Permit, perform the following:

3.1 Determine if a SRD is required to be worn while in transit to the normal RCA access point, and issue per Step 2.

3.2 Instruct personnel to go to the main access control point to obtain an EAD and sign in on the required RWP.

3.3 For personnel who were issued a SRD per Step 2.1, report any difference in the SRD versus EAD dose to the Shift RP Technician or the Radiation Protection Coordinator, as this may indicate that dose was accumulated while in transit to and from the normal RCA access point.

4. If Radiation Protection personnel determine it is necessary for all individuals to wear a TLD, issue TLDs to personnel who do not have a TLD using Form FC-1 189.

R20

FORT CALHOUN STATION EPIP-EOF-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 6 OF 9.4 - Dosimetry Issuance in the Emergency Operations Facility (EOF)

1. Obtain the Dosimetry Issue Kit.
2. Issue a self reading dosimeter to all personnel that must pass a Radiation Controlled Area Control Point:

2.1 The Radiation Protection Coordinator shall determine what range of SRDs should be issued for the entry(ies).

2.2 Ensure the SRD indicates approximately zero and issue to the individual(s).

2.3 Record the dosimetry issue and RCA access information on Form FC-RP-214-2.

2.4 Upon return of the individual(s), record the accumulated dose and RCA exit information on Form FC-RP-214-2.

3. If going to the plant site report to the TSC upon arrival.
4. If Radiation Protection personnel determine it is necessary for all individuals to wear a TLD, issue TLDs to personnel who do not have a TLD using Form FC-1 189.

R20

FORT CALHOUN STATION EPIP-EOF-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 7 OF 9.5 - Approving Emergency Worker Exposure NOTE: Verbal authorization may be given to emergency responders and Form FC-EPF-5 may be completed afterwards.

1. Obtain a Form FC-EPF-5 for each individual.

NOTE: The facility directors, Control Room Coordinator or Shift Manager in the Control Room, Site Director, or the TSC Director in the TSC, the OSC Director in the OSC or the Emergency Director in the EOF may authorize dose extension up to 5 REM TEDE per year during declared events for workers in their facility. The Command and Control position must authorize doses exceeding 5 Rem TEDE in a year using the criteria per RERP-Section K.

2. Upon authorization by the Command Control Position, complete Form FC-EPF-5. If the authorization is a verbal complete the form as soon as practical.

2.1 Fill-in the top section as stated. Completed the description of the work or task section as much as possible.

2.2 Fill-in the recommended TEDE increase, and if the exposure is to exceed 25 REM have the individual check the box.

2.3 Have the authorizing signature filled-in. If it is a verbal authorization, have the signature filled-in as soon as possible. Then go to Step 3.

2.4 The section for Dosimeter readings is to be filled-in only for exposures that are over 5 REM.

2.5 After the individual's TLD has been read, the dose received will be updated on the individual's form 5.

3. Forward the completed Form FC-EPF-5 to the OSC RP Coordinator.

R20

FORT CALHOUN STATION EPIP-EOF-1 EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 8 OF 9.6 - Performing Habitability Surveys [AR 11809]

1. Perform habitability surveys for radiation and radioactive material as directed by the Radiation Protection Coordinator or the Protective Measures Coordinator.
2. Use the following as guidelines in the performance of habitability surveys:

2.1 A complete habitability survey should include a general area radiation survey, airborne particulate sample, airborne iodine sample, and a contamination survey.

The survey results should be documented on a formal survey diagram, but a log entry of the results is acceptable.

2.2 Consult with the Radiation Protection Coordinator and/or Protective Measures Coordinator to determine if continued habitability surveys are necessary. Plant conditions may not require periodic surveys.

2.3 Habitability surveys, when necessary, should be performed at least once per hour.

When levels start to increase, more frequent surveys should be made.

2.4 Installed equipment, such as a PING (Particulate, Iodine and Noble Gas monitor) and an area radiation monitor may be used for initial habitability determination when it is known that there is little possibility of a contamination control problem.

2.5 Should installed equipment be used, and any alarms occur, a complete habitability survey as described above must be performed.

2.6 Consult with the Radiation Protection Coordinator and/or Protective Measures Coordinator to determine if continued habitability surveys are necessary. Plant conditions may not require routine surveys.

2.7 If emergency conditions and/or background radiation levels prevent effective counting of samples, move to a lower background area, or retain the samples for counting at a later date.

2.8 If emergency conditions and/or background radiation levels interfere with whole body counting operations, this function may have to be postponed or performed at a counter located outside the Protected Area.

2.9 Survey results should be reported to the Radiation Protection Coordinator upon completion.

3. For general area dose rates, use the following as guidelines for protecting personnel:

3.1 For general area dose rates >15 mRem/hr, issue SRDs (Self Reading Dosimeters).

R20

FORT CALHOUN STATION EPIP-EOF-1I EMERGENCY PLAN IMPLEMENTING PROCEDURE PAGE 9 OF 9.6 - Performing Habitability Surveys (AR 1180911180913.2 For general area dose rates >100 mRem/hr, consider relocating to areas of lower dose rates.

3.3 For general area dose rates >1000 mRem/hr, relocate to an area of lower dose rate.

Only personnel needed to mitigate the consequences of the accident, save plant equipment or a human life should remain.

4. For airborne radioactivity levels, use the following as guidelines for protecting personnel:

4.1 For airborne radioactivity levels >30% of the Derived Air Concentration, post and control the area as an Airborne Radioactivity Area per RP-204.

4.2 For radioiodine concentrations >3.3E-8pCi/cc, perform the following:

4.2.1 Multiply the concentration times 1.25E6 to determine the Thyroid dose rate in Rem/hr.

4.2.2 Multiply the Thyroid dose rate times the projected stay time to determine the projected Thyroid Committed Dose Equivalent (CDE) in Rem.

4.2.3 If the projected Thyroid CDE is >1 Rem, consider relocation of personnel to an area of lesser concentration or the issue of SCBAs to exposed personnel.

4.2.4 If the projected Thyroid CDE is 25 Rem, issue potassium iodide per EPIP-EOF-21, or ensure exposed personnel wear SCBAs.

5. For loose surface contamination, use the following as guidelines for protecting personnel:

5.1 For Contaminated Areas (per RP-204), consider relocation of personnel to an area of lesser contamination.

5.2 For Highly Contaminated Areas (per RP-204), monitor and relocate non-essential personnel to an area of lesser contamination.

R20