ML023370397
| ML023370397 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/21/2002 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML023370397 (187) | |
Text
Tennessee Valley Authonty, Post Office Box 2000, Decatur, Alabama 35609-2000 November 21, 2002 10 CFR Part 50, App E U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D.C. 20555-0001 Gentleman:
In the Matter of
)
Docket Nos.
50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, and 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS TVA is submitting this notification in accordance with the requirements of 10 CFR Part 50, Appendix E, Section V.
Specifically, several EPIPs were revised:
(1) EPIP-2, Revision 25; (2)
EPIP-3, Revision 28; (3)
EPIP-4, Revision 27; (4)
EPIP-5, Revision 32; (5) EPIP-6, Revision 22; (6)
EPIP-7, Revision 20; (7)
EPIP-12, Revision 0; (8)
EPIP-13, Revision 9; and (9)
EPIP-14, Revision 17.
The revisions have an effective date of October 29, 2002.
Additionally, EPIP 17 and EPIP-20 were canceled on October 29, 2002; therefore, please remove EPIP-17 Revision 25 and EPIP-20 Revision 9.
The enclosed information is being sent by certified mail.
The signed receipt signifies that you have received this information.
If you have any questions, please telephone me at (256) 729-2636.
nce ee Manager of L "a
and ustry Af irs cc:
ee Page 2 Prted on recycled paper
U.S. Nuclear Regulatory Commission Page 2 November 21, 2002 cc (Enclosure):
NRC Resident Inspector (Enclosure provided by Browns Ferry Nuclear Plant BFN Document Control Unit) 10833 Shaw Road Athens, Alabama 35611-6970 Mr. Paul E.
Fredrickson, Branch Chief (2 Enclosures)
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street S.W.,
Suite 23T85 Atlanta, Georgia 30303-8931 Mr. Kahtan N. Jabbour, Senior Project Manager (w/o Enclosure)
U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9)
Office of Nuclear Reactor Regulation 11555 Rockville Pike Rockville, Maryland 20852-2738
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2,
AND 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISION EPIP-2, EPIP-3, EPIP-4, EPIP-5, EPIP-6, EPIP-7, EPIP-12, EPIP-13, EPIP-14, EPIP-17 and EPIP-20 SEE ATTACHED
GENERAL REVISIONS FILING INSTRUCTIONS FILE DOCUMENTS AS FOLLOWS:
PAGES TO BE REMOVED PAGES TO BE INSERTED Revision 24 Revision 27 Revision 26 Revision 31 Revision 21 Revision 19 Revision 8
Revision 16 Revision 25 Revision 9
EPIP-2 EPIP-3 EPIP-4 EPIP-5 EPIP-6 EPIP-7 EPIP-12 EPIP-13 EPIP-14 NONE NONE Revision Revision Revision Revision Revision Revision Revision Revision Revision EPIP-2 EPIP-3 EPIP-4 EPIP-5 EPIP-6 EPIP-7 NONE EPIP-13 EPIP-14 EPIP-17 EPIP-20 25 28 27 32 22 20 0
9 17
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-2 NOTIFICATION OF UNUSUAL EVENT REVISION 25 PREPARED BY: TONY FELTMAN RESPONSIBLE ORGANIZATION-EMERGENCY PREPAREDNESS APPROVED BY:
GILBERT V. LITTLE EfTECTIVEDATE. 10/29/2002 I
I LEVEL OF USE: REFERENCE USE PHONE: 2038 DATE: 10/25/2002 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-2 Revision Number:
25 Pages Affected: 2,4,7,11,12 Description of Change:
IC-27 This change is being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713. to remove the Public Infonration Officer from the notification form and to human factor the notification and followx-up notification forms.
Page 2 - change to step 3.1.1 invol es human factonng the Notification Form Title.
Page 7 - changes in\\ olves removing the -'NRC Commitment Brackets to step requinng the review of PORC and the human factonng of applicable steps.
Page 7 - change involves human factoring attachment title Page 8 - change involves human factoring attachment title and modifying information to ensure consistency xi ith NRC guidance Page 9 - change involves removing the Public Information Officer from the Attachment B notifications along with the NRC Commitment Brackets Page 10 - change invoh ed adding a clarify statement concerning the appropriate use of the Follow up Notification Fonr IC-28 EPIP-2. re ismon 23 is being issued to incorporate changes resulting from the letter, NEI to NRC (to Mr. Bruce A. Boger) dated December 18, 2001 requesting confirmation for EAL basis change to include response to a Site-Specific Security Credible Threat. This letter was de eloped in response to the NRC's October 6, 2001 Safeguards Advisory The change to this EPIP is a consequence to the EAL change. Under specific conditions this change will actiN ate the ERO along NN ith assenmbl/accountability. The revision also incorporates standardization of telephone numbers and actions taken by the Unit 1. Unit Operator during ERO staffing.
Page 2 - provide the action to staff the ERO wi hen a credible site secunty threat notification exists Page 3 - provide the action to assembly/account site personnel for the purpose of establishing the
"'Tiwo Person (Line of Sight) Rule" Page 4 - standardize the reN iew' of PORC for actual eN ents.
Page 7 - add attachment D.
Page 11 - add attachment D. actions taken by the Unit I Unit operator to staff the ERO.
IC-29 EPIP-2. reN ision 24. page 3 is being conducted to add clanfication to the caution note regarding on site security conditions for assembly/accountability Additionally page 2 and 5 was re, ised to update telephone information regarding the Office of Radiation Control.
IC-30 EPIP-2. rei ision 25. pages 2. 7. 11 and 12 are being conducted to remoN e the acti% ation of the ERO upon declaratlon of an Unusual E\\ent based upon a credible threat Page 4 is being rexised to change thie reference for Dose Assessment from EPIP-14 to EPIP-13
NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT nrlr-z NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate individuals or organizations when the Shift Manager has determined by EPIP-1 that an incident has occurred which is classified as a NOTIFICATION OF UNUSUAL EVENT.
1.2 Provide for periodic analysis of the current situation by the Shift Manger/Site Emergency Director (SED) to determine whether the NOTIFICATION OF UNUSUAL EVENT should be terminated, continued, or upgraded to a more serious classification 2.0 SCOPE This procedure applies to emergency events that are classified as a Notification of Unusual Event by EPIP-1, Emergency Classification Procedure PAGE 1 OF 10 REVISION 25
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS 3.1 Notification of the Operations Duty Specialist (ODS)
Note-The ODS should be notified within 5 minutes after the emergency event is declared Date:
/
/
3.1 1 Complete Attachment A (Initial Notification Form).
3.1.2 Notify the ODS and Provide the information from Attachment A.
Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS Telephone Numbers 5-751-1700 5-751-2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly by requesting the Office of Radiation Control at Day Shift 8 a m - 5 p m. (Central Time)
Primary 9-1-334-206-5391 Backup:
9-1-800-582-1866 Holidays-Weekends-Offshifts Montgomery State Trooper Post 9-1-334-242-4378 3.1.3 Fax a copy of Attachment A to the ODS for confirmation of information or state if contacted directly ODS Fax 5-751-8620 Office of Radiation Control 9-1-334-206-5387 PAGE 2 OF 10
- INITLAL, TuME INITLUS TIME INITLULS TLME I
REVISION 25
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.1.4 Receive confirmation call from the ODS (to verify notification of the State of Alabama) (NA this step if the State was contacted directly).
3.2 NOTIFICATION OF SITE PERSONNEL 3.2.1 Provide the Unit 1, Unit Operator with a completed copy of Attachment A.
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notifications), utilizing information from Attachment A 3.2.3 MvIake the following plant P.A. announcement:
THIS IS (NAME), SHIFT MANAGER A NOTIFICATION OF UNUSUAL EVENT HAS BEEN DECLARED ON UNIT I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR 3.2.4 Notify the Plant Manager or alternate INITLULS TInE INTrIA.S TLME INITLMS TLNnF INITLUS TmiE INITLIALS
'I.IE CAUTION:
Do not initiate Assembly and Accountability if:
- 1.
A severe weather condition exist or projected on-site, such as a Tornado.
- 2.
An on-site security risk condition exists that may present a danger to site personnel during the assembly/accountability process (Consult with Nuclear Security) 3.3 ACCOUNTABILITY 3.3.1 Tf the NOUE has been declared due to Security EAL, 6.7-U, and Nuclear Security recommends Accountability to establish the "Two Person (Line of Sight) Rule",
Then implement EPIP-8, Appendix C, for Assembly and Accountability only.
1,INTLALS TmIE PAGE 3 OF 10 REVISION 25
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 OFFSITE DOSE ASSESSMENT 3.4.1 Evaluate the need for offsite dose assessment.
(N/A STEP IF NOT APPLICABLE) 3.4.1.1 When offsite dose assessment is required obtain the information from the CECC when operational 3.4.1.2 If the CECC is not operational, contact the TSC, when staffed or the RADCON Shift Supervisor and request the implementation of EPIP 13, for dose assessment.
3.5 NOTIFICATION OF THE NRC 3.5.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if requested by the NRC maintain an open and continuous communications channel Note Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, by dialing 9-1 "The Ten Dioit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No access codes are required.
IanLLS T
E I.NITL'L%
TLME PAGE 4 OF 10
'-I REVISION 25
NOTIFICATION OF I
BROWNS FERRY UNUSUAL EVENT Erlr-L NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 PERIODIC EVALUATION OF THE EVENT 3.6.1 Continue to Evaluate the event by using EPIP-1 as conditions warrant.
3.6.2 If other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred since the last update to the ODS, and the CECC is not staffed, Then, Complete the "Follow-Up" Notification Form (Attachment C), notify the ODS and provide the new information Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS 751-1700 5-751-2495 Note If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Office of Radiation Control at:
Day Shift 8 a m - 5 p m (Central Time)
Primary 9-1-334-206-5391 Backup.
9-!1800-582-1866 Holidays'-Weekeidts-offshifts Montgomery State Trooper Post 9-1-334-242-4378 3.6.3 If the conditions warrants upgrading to a higher classifications, Then initiate the appropriate EPIP.
3.6.4 If the conditions warrant termination of the classification, Then enter the Termination section of this procedure at step 3 7.
3.6.5 Re-enter this procedural section as conditions warrant at step 3.6.1 or until directed to exit this procedure by steps 3.6 3 or 3 6 4.
REVISION 25 1
PAGE 5 OF 10
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 TERMINATION OF THE EVENT If the situation no longer exists terminate the event and notify the following:
Date:
/
/
3.7.1 Notify the ODS of the termination of the emergency or the state directly if the ODS cannot be contacted.
3.7.2 Notify the NRC of the termination of the emergency 3.7.3 Notify the Plant Manager or Alternate of the termination of the emergency 3.7.4 Complete Attachment A by providing the time and date of termination.
3.7.4 Notify the Unit 1, Unit Operator. Provide the Unit 1, Unit Operator with the termination time and date and direct the Unit 1, Unit Operator to notify the individuals contacted on Attachment B of the termination of the emergency.
L%1TLLS, TLwE INITL%.S TLmE IN]TLIAL%
TLME INI1 LL%
TIME 1MI I,L I LIME PAGE 6 OF 10 REVISION 25
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 CLOSURE OF THE NOTIFICATION OF UNUSUAL EVENT 3.8.1 Upon termination of the Notification of Unusual Event, the Shift Manager shall send the completed EPIP-2 and all attachments to Emergency Preparedness (EP).
3.8.2 Upon receipt of completed EPIP-2 and all attachments, Emergency Preparedness shall forward documents for the purpose of documentation storage 1NITILUS TEFIE INITLUS TmE 4.0 ATTACHMENTS Attachment A - Initial Notification Form Notification of Unusual Event Attachment B - Unit 1, Unit Operator Notifications Attachment C - Follow Up Information Form Notification of Unusual Event PAGE 7 OF 10 REVISION 25
NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORNM NOTIFICATION OF UNUSUAL EVENT
[-I THIS IS AN ACTUAL EVENT
-- THIS IS AN EXERCISE This is NAM1E A NOTIFICATION OF UNUSUAL EVENT has been declared at Browns Ferry affecting
[-- Unit 1
-]
Unit 2 n-Unit 3 E] Common Event Declared Time:
Date EAL Designator.
Brief Description of the Event Radiological Conditions:
I-No Abnormal Releases Offsite
-] Airborne Release Offsite
[] Liquid Release Offsite K] Release Information Not Known at this time F-- There is no Protective Action Recommendation at this time.
F-] Ask,_"Please repeat the information you have received to ensure accuracy PAGE 8 OF 10 REVISION 25
NOTIFICATION OF UNUSUAL EVENT
- EPIP-2 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 1)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
/
Note All notifications should be made utilizing the information located on EPIP 2, Attachment A Received a completed copy of EPIP 2, Attachment A from the Site Emergency Director LN-1ThXLS m
Personnel Notifications Notify the Operations Manager (from the weekly duty list)
Notify the Vice President (from the weekly duty list)
Notify the REP manager (from the weekly duty list)
Notify the Nuclear Security Shift Supervisor Ext 3150 or 2219 Notify the NRC Resident Ext 2573, or 2572 or from the weekly duty list Initial Notifications
- 1-
+
Initials Time Intials
- Time Initials Time Initials Time Initials Time Termination Notifications Initials Time Initials Tine Initials Time Initials Time Initials Time PAGE 9 OF 10 REVISION 25
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
FOLLOW-UP INFORMATION FORM NOTIFICATION OF UNUSUAL EVENT
[-"
THIS IS A REAL EVENT
[I] THIS IS A DRILL Note This form is for conducting Follow-up Information only This is at Browns Ferry.
Name There has been a NOTIFICATION OF UNUSUAL EVENT declared at Browns Ferry affecting
-- Unit I F-1 Unit 2 F--
Unit 3 E-Common The Reactor is R Shutdown L"- At Power Plant Conditions are E] Stable Deteriorating "Follow-Up" Information (e.g, Key Events, Status Changes)
Current Radiological Conditions are F1-No Abnormal Releases Offsite FD Airborne Release Offsite F1-Liquid Release Offsite F1-Release Information Not Known Additional Rad information: (e g, release duration)
F1-There is no Protective Action Recommendation at this time Please repeat the information you have received to ensure accuracy.
The time for this follow up is Time Date:
SIGNATURE:
LAST PAGE PAGE 10 OF 10 REVISION 25
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-3 ALERT REVNISION 28 PREPARED BY: T. W. CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY:
GILBERT LITTLE EFFECTIVE DATE: 10/29/2002 LEVEL OF USE: REFERENCE USE PHONE. 2038 DATE-10/18/2002 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-3 Revision Number:
28 Pages Affected:
4 Description of Change:
IC-30 This change is being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713. and to human factor the notification and follow-up notification forns Page 2 - change to step 3.2 1 iN oh es human factoring the Notification Form Title Page 6 - changes invol% es remoN ing the "NRC Commitment Brackets to step requiring the revmevi of PORC and the human factoring of applicable steps.
Page 7 - change min olh es human factoring attachment title and modifN ing information to ensure consistency with NRC guidance.
Page 8 - change mn oh es adding information regarding the support of the Unit I Operator in staffing the ERO Page 9 - Updated information for the Unit Operator to use during the ERO staffing process Page 10 - change mn oh ed adding a clarify statement concerning the appropriate use of the Follow up Notification Form IC-31 EPIP-3. re% ision 26 is being issued to incorporate changes regarding assembly and accountability actions. All actions to initiate the accountability and evacuation processes are now located in EPIP-8 The re* ision addiuionally standardizes telephone numbers, and PORC reviews This re, ision also adds clarification for the actions taken b. the Unit 1 Unit Operator during their staffing of the ERO process.
Page 3 - added a statement to the caution information regarding security threat Clarified steps 3 4 1 and 3 4 2 to implement EPIP-8 regarding actions to be taken for assembly/accountability and evacuation Page 6 - standardize Alert procedure closure information Page 8.9 - Clarify actions taken bN the Unit I Unit Operator dunng the notification attachment.
IC-32 EPIP-3. re ismon 27 is being conducted to incorporate changes regarding actions to be taken when dangerous conditions exist on site that w ould require the assembly of the ERO at the staging area.
AdditionallN page 3 and 5 wNere revised to update telephone infornation regarding the Office of Radiation Control Page 2 - change instruct the SED w, hen to direct the Unit 1 Unit Operator to assembly the ERO at the staging area Page 4 - reN ision adds clarification to the caution note regarding on-site securit-conditions for assembly/accountablity Page 8 - revision adds option for staging area IC-33 EPIP-3. re% ision is being conduct to change the procedure reference for Dose Assessment from EPIP-14 to EPIP-13. Page 4 of this procedure isbe rem*sed
ALERT BROWNS FERRY EPIP-3 NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate-individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as an ALERT.:
1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the ALERT should be terminated, continued, or upgraded to a more serious classification'.
2.0 SCOPE This procedure applies to emergency events that are classified as Alert by EPIP-1, Emeigehcy Classification Proceddre PAGE 1 OF 10 REVISION 28
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS Date:
/
/
3.1 If all Emergency Centers ARE STAFFED, Then notify the following that an ALERT Emergency Classification has been issued and EPIP 3 is being implemented, and continue in this procedure at Step 3 4. If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure.
Control Rooms
-]
Plant PA Announcement EI Tlus is N XME. Site Emergency Director. an Alert has.
been declared at BFN. Nxe are currentlN implementing EPIP-3 Standby for fuirther updates INITLIL'
'IL\\IE 3.2 Notification of the Operations Duty Specialist (ODS) & Emer2ency Responders Note: The ODS should be notified within 5 minutes after the emergency event is declared.
3.2.1 Complete Attachment A (Initial Notification Form) 3.2.2 Activating Emergency Response Organization (ERO) 3.2.2.1 If ongoing/anticipated on-site security events may present a danger to the emergency responders, Then consult with Nuclear Security 3.2.2.2 If ongoing/anticipated events present a danger to emergency responders, Then direct the Unit 1 Unit Operator to make notifications per Attachment B and select "Staging Area" as the option for the Emergency Paging System.
3.2.2.3 If there are no ongoing/anticipated danger to emergency responders, Then direct the Unit 1 Unit Operator to make notifications per Attachment B and select as applicable, "Drill" or "Emergency" as the option for the Emergency Paging System INITLXLS ruL'w7 INITMLL TInE INITIALS TLuE IN1] L\\IS TIME REVISION 28 CECC TSC OSC LI LI LI I
PAGE 2 OF 10
ALERT
- EPIP-3 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2.3 Notifv the ODS and Provide the information from Attachment A Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS Telephone Numbers 751-1700,or 2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly,by requesting the Office of Radiation Control at:
- iNULSL.
TwME Day Shift 8 a m. - 5 p m (Central)
Primary. 9-1-334-206-5391 Backup: 9-1-800-582-1866 Holidays-Weekends-Off-Shifts Montgomery, State Trooper Post 9-1-334-242-4378 3.2.4 Fax a copy of Attachment A to the ODS for confirmation of information or state if the state was contacted directly.-
ODS Fax 5-751-8620 Office of Radiation Control Fax 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify notification of the State of Alabama)(NA this step, if the state was contacted directly).
3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A announcement.
THIS IS (NAME), SHIFT MANAGER A ALERT HAS BEEN DECLARED ON UNIT
. I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME.
INTIALS TnuE PAGE 3 OF 10 I,"NTLU-% - '
TBIE IN1TL*LS Tt'IE
- k I REVISION 28
ALERT EPIP-3 3.0 INSTRUCTIONS (CONTINUED)
CAUTION:
Do
- 1.
2 not initiate Assembly and Accountability if A severe weather condition exist/projected on-site, such as a Tornado An on-site security risk condition exists that may present a danger to site personnel during the assembly/accountability process (Consult with Nuclear Security).
3.4 ACCOUNTABILITY 3.4.1 If the emergency situation warrants an Assembly, Accountability, Then implement EPIP-8, Appendix C, concurrently with this procedure (N/A STEP IF NOT APPLICABLE) 3.4.2 If the emergency situation does not warrant an Assembly, Accountability at this time, Continue to assess the situation, implementing EPIP-8 when necessary 3.5 OFFSITE DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment (N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is required obtain the information from the CECC when operational 3.5.1.2 If the CECC is not operational, contact the TSC, when staffed or the RADCON Shift Supervisor and request the implementation of EPIP 13, for dose assessment
- INMTL4U, FIFE IlnrILs TmIE PAGE 4 OF 10 BROWNS FERRY NUCLEAR PLANT I
REVISION 28
ALERT BROWNS FERRY EPIP-NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if requested by the NRC maintain an open and continuous i_,,TLs.
S r
TME communications channel Note. Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, by dialing 9-1 "The Ten Diqgi Number Listed on the ENS Telephones".
If the number is busy, Then select in order,' the alternate.
numbers until a connection is achieved. No access codes are required.
3.7 PERIODIC EVALUATION OF THE EVENT 3.7.1 Continue to Evaluate the event using EPIP-1 as conditions warrant 3.7.2 If plant conditions warrant the need for follow up information, Complete the Follow Up Notification Form, Attachment C.
Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred 3.7.3 If the CECC is not staffed, Then notify the ODS and provide follow up, information from the completed Attachment C form Utilize the direct ring-down ODS phone when making this notification or-as applicable dial direct.,
ODS 751-2495, 1700 ;
Note: If the ODS cannot be reached;,Then contact the State of Alabama directly by requesting the Office of Radiation Control at.
Day Shift 8 a m - 5 p m (Central Time)
Holidays-Weekends-Off-shifts Primary:
9-1-334-206-5391 Montgomery State Trooper Post Backup:
9-1-800-582-1866 9-1-334-242-4378 3.7.4 If the conditions warrant upgrading to a higher classification,.Then initiate the appropriate EPIP.
PAGE 5 OF 10 REVISION 28
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7.5 If the conditions warrants termination of the classifications, Then enter EPIP-16, Termination and Recovery Procedure.
3.7.6 After the evaluation has been completed, if staffed, Notify the following of the status
"* CECC
"* NRC (ENS)
"* TSC
"* OSC
"* CONTROL RooMis
" PLANT PA ANNOUNCEMENT 3.7.7 Re-enter this procedural section as conditions warrant at step 3 7 1 or until directed to exit this procedure by steps 3.7 4 or 3.7 5.
3.8 CLOSURE OF THE ALERT 3.8.1 Upon termination of the Notification of Alert, the Shift Manager shall send the completed EPIP-3 and all attachments to Emergency Preparedness (EP) 3.8.2 Upon receipt of completed EPIP-3 and all attachments, Emergency Preparedness shall forward documents for the purpose of documentation storage.
4.0 ATTACHMENTS Attachment A - Initial Notification Form Alert Attachment B - Unit 1, Unit Operator Notifications Attachment C - Follow Up Information Form Alert I\\ITLt'.L TIME INITI %L%
TLME PAGE 6 OF 10 I
REVISION 28
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM ALERT -
-' THIS IS A REAL EVENT
[],'THIS IS A DRILL This is A
An ALERT, has been declared at Browns Ferry, affecting
-] Unit 1 LI Unit 2
[n Unit 3 El Common Event Declared:
Time: _
Date:
EAL Designator:
Brief Description of the Event Radiological Conditions.
-- No Abnormal Releases Offsite
[-I Airborne Release Offsite A,
[- Liquid Release Offsit'e
-- Release Infor'mation-Not Known at this time L-There is no Protective Action Recomhmendation at this time.
L-Ask "Please repeat the informhtion you have received to ensure accurac PAGE 7 OF 10 REVISION 28
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
/
NOTES: (1) The Emergency Paging System (EPS) consists of a dedicated touch screen CRT Activation of any screen feature requires the user place their fingertip within the boundary of the select button and leave it there for at least I second The CRT Screen will normally display a large rectangle that indicates that the paging system is available but currently inactive.
(2) If the EPS fails to operate, contact the SM/SED immediately Request that the ODS be contacted to initiate the system from his location If the system fails to operate from the ODS area, then utilize the Weekly Duty List and Call-Out List to manually staff the Emergency Responders, implementing this attachment at step E.
- 1. Activation A
of the Emergency Paging System (EPS)
PRESS the EPS CRT Screen once to activate the paging options.
INITIALS TIME B.
PRESS the appropriate option as instructed by the SED
"* PAGER TEST
"* DRILL
"* EMERGENCY
"* STAGING AREA
"* ABORT C.
PRESS the START Button to initiate the option or ABORT to deny the option request.
D.
MONITOR the Paging System Terminal Display 1
IF. A "NO" response is observed OR The position being paged has not responded within approximately 20 minutes THEN. Utilize the Weekly Duty List and attempt to contact the position representative with available information (No Fitness for Duty Question Required)
- 2.
IF.. The individual cannot be reached utilizing the Weekly Duty List THEN.. Utilize the Call-Out List and attempt to contact an alternate position representative (Fitness for Duty Question Required)
PAGE 8 OF 10 INITIALS TIME INITIALS TIME INITIALS TIME REVISION 28
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 2 of 2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
/
E.
--Manual Call-Out (N/A step if EPS operates normally)
- 1.
Utilize the current Weelky Duty List and contact positions as listed
- 2.
Ifra position can not be reached from the current Weekly Duty list, then refer-to the Call-out List as applicable to fill all vacant positions F.
CONTINUE until all positions have been filled
'INITIALS TIME INITIALS TIME 2.
Notify the Unit Supervisors on shift.
- 3. Notify Nuclear Security Shift Supervisor and state "AN ALERT HAS BEEN DECLARED" and direct to activate EPIP-1 1, Security and Access Control.
INITIALS TIME INITIALS TIME Plant Extension 3150 or 2219
- 4. Notify the Chemistry Lab Supervisor and state "AN ALERT, HAS BEEN DECLARED" and direct to implement 2/3-TI-33 1, Post Accident Sampling Procedure and CI-900 series, Analysis Procedures.
Plant Extension 2367 or 2368
- 5. Notify the RADCON Shift Supervisor and state "AN ALERT HAS BEEN DECLARED" and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension 7865 or 3104
- 6. Notify the "On-Call" NRC Resident and state "AN ALERT HAS BEEN DECLARED," per BFN-EPIP-03.
0
- Plant Extension 2572 [Secretary] or-from weekly duty list t
INITIALS TIME INITIALS TIME
,PAGE 9 OF 10 K-'
INITIALS TIME REVISION 28
ALERT EPIP-3 ATTACHMENT C (Page I of 1)
FOLLOW-UP INFORIMATION FORIM ALERT
[-I THIS IS A REAL EVENT
-] THIS IS A Note. This form is for conducting Follow-up Information only.
This is at Name There has been a Alert declared at Browns Ferry affecting n
Unit I n
Unit 2 E-Unit3 The Reactor is -- Shutdown D At Power Plant Conditions are ] Stable ZI Deteriorating "Follow-Up" Information (e g, Key Events, Status Changes)
BROWNS FERRY NUCLEAR PLANT DRILL Browns Ferry
--1 Common Current Radiological Conditions are
-- No Abnormal Releases Offsite
-- Airborne Release Offsite
[- Liquid Release Offsite LI Release Information Not Known Additional Rad information (e g, release duration) n There is no Protective Action Recommendation at this time Please repeat the information you have received to ensure accuracy The time for this follow up is Time Date SIGNATURE:
LAST PAGE PAGE 10 OF 10 REVISION 28
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-4 SITE AREA EMERGENCY REVISION 27 PREPARED BY: T. W. CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE: 10/29/2002 LEVEL OF USE 'REFERENCE USE PHONE. 2038 DATE-10/18/2002 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-4 Revision Number: 27 Pages Affected: 4 Description of Change:
IC-31 This change is being conducted to incorporate a manual method of ex acuating on-site. non emergency response personnel during emergenc-situations In addition changes to the procedure are being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713. and to human factor the notification and follow-up notification forms.
Page 2 - change to step 3 2.1 in% ol' es human factoring the Notification Form Title Page 3- -changes to steps 3.4.1 - 3 4.5 im olh es information regarding steps for the SED to take NN hen conducting an Accountably/Assembly and Evacuation.
Page 6 - changes inA oh es remmoi ing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps Page 7 - change inN ol% es human factoring attachment title.
Page 8 - change in, oh es human factonng attachment title and mnodif ing information to ensure consistency xith NRC guidance Page 9 - change involes adding information for Unit 1 Operator regarding ERO staffing support.
Page 10 - updated information for the Unit Operator to use during the ERO staffing process.
Page 11 - change in olh ed adding a clanfN statement concerning the appropriate use of the Follo*\\
tip Notification Form.
IC-32 EPIP4. revision 25 is being issued to incorporate changes regarding assemblN and accountablity actions All actions to initiate the accountability and evacuation processes are now%' located in EPIP 8 The re, isiom additionally standardizes telephone numbers, and PORC re' icws This rem ision also adds clarification for the actions taken by the Unit I Unit Operator during their staffing of thie ERO process Page 3 - added a statement to the caution information regarding security threat Clarified steps 3.4.1 and 3.4.2 to implement EPIP-8 regarding actions to be taken for assembly/accountabilitA and evacuation Page 6 - standardize Site Area Emergency procedure closure information Page 8.9 - ClarifN actions taken bN the Unit 1 Unit Operator during the notification attachment IC-33 EPIP-4. reN ision 26 is being conducted to incorporate changes regarding actions to be taken ii hen dangerous conditions emist on site that wiould require the assembly of the ERO at the staging area Additionally page 3 and 5 wiere reN ised to update telephone information regarding the Office of Radiation Control.
Page 2 - change instruct the SED ihlien to direct the Unit I Unit Operator to assenlblN thie ERO at the staging area Page 4 - re% ision adds clarification to the caution note regarding on-site securitN conditions for asseimbly/accountability Page 8 - reN ision adds option for staging area IC-34 EPIP-4. revision 27 is being conduct to change the procedure reference for Dose Assessment from EPIP-14 to EPIP-13 Page 4 of this procedure is be rexsed.
SITE AREA EMERGENCY SEPIP-4 BROWNS FERRY NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as a SITE AREA EMERGENCY (SAE) 1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the SAE'should b6 terminated, continued, or upgraded to a more serious classification' 2.0 SCOPE This procedure applies to emergency events that are classified as Site Area Emergency by EPIP-I Emergenicy Classification Piocedure--
I.'
S
-PAGE 1 OF1O REVISION 27
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS Date:
/
/
3.1 If all Emergency Centers ARE STAFFED, Then notify the following that a SITE AREA EMERGENCY Emergency Classification has been issued and EPIP 4 is being implemented, and continue in this procedure at Step 3 4. If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure CECC TSC OSC F-1 E]
Control Rooms E
Plant PA Announcement E
Thi's i% Ns
'ME.
Site Emergenc\\ Director. an S AE has been declared al I1FN. %%e are currentli itmplemnenting EPIP-4 StandbN ]or further updates 3.2 Notification of the Operations Duty Specialist (ODS) & Emergency Responders Note The ODS should be notified within 5 minutes after the emergency event is declared 3.2.1 Complete Attachment A (Initial Notification Form).
3.2.2 Activating Emergency Response Organization (ERO) 3.2.2.1 If ongoing/anticipated on-site security events may present a danger to the emergency responders, Then consult with Nuclear Security 3.2.2.2 If ongoing/anticipated events present a dangzer to emergency responders, Then direct the Unit I Unit Operator to make notifications per Attachment B and select "Staging Area" as the option for the Emergency Paging System.
3.2.2.3 If there are no ongoing/anticipated danger to emergency responders, Then direct the Unit I Unit Operator to make notifications per Attachment B and select as applicable, "Drill" or "Emergency" as the option for the Emergency Paging System.
PI i r ILL%
rtIME INI11 U1%
TLME IN] I LL%
TIME INITI id,%
TIME REVISION 27 INITUL\\S TIME PAGE 2 OF 10
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2.3 Notify the ODS and Provide the information from,,
'Attachment A.
Note:, Utilize thedirect ring-down ODS phone when making this notification or as applicable -dial direct.
ODS Telephone Numbers -.
5-751-1700, 2495 If the ODS cannot be reached within 10 minutes,`ýThen..
contact the State of Alabarfia directly by reqcubsting the Rad Health Duty Officer at:-
INrTIAUS Tms Day Shift 8 a m - 5 p m.(Central)
Primary: 9-1-334-206-5391 Backup: 9-1-800-582-1866 Holidays-Weekends-Off-Shifts Montgomery State Trooper Post 9-1-334-242-4378, 3.2.4 Fax a copy of Attachment Ato the ODS for cohfirmation of information or if the state is contacted rectly.
ODS Fax 5-751-8620 Office of Radiation Control Fax 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify notification of the State of Alabama)(NA this step, if the IN-%ITI-%LS-TIME state was contacted directly),
3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A., nnoincement:
INITIALS TIME THIS IS (NAME), SHIFT MANAGER A SITE AREA EMERGENCY HAS BEEN DECLARED ON UNIT I HAVE'ASSUMEDTHEDUTIES OF SITE EMERGENCY DIRECTOR REPORT TO YOUR ASSIGNED EMERGENC REsPoNs*E FACILITY AT THIS TIME.
PAGE 3 OF 10 INITLLLS TLIE REVISION 27
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEARPLANT 3.0 INSTRUCTIONS (CONTINUED)
CAUTION: Do not initiate Assembly and Accountability if I A severe weather condition exist or projected on-site, such as a Tornado 2 An on-site security risk condition exists that may present a danger to site personnel during the assembly/accountability process (Consult with Nuclear Security) 3.4 ACCOUNTABILITY AND EVACUATION OF NON-EMERGENCY RESPONDERS 3.4.1 If Assembly and Accountability has not been conducted, Then, implement EPIP-8, Appendix C concurrently with this procedure. If Accountability has been conducted, Then N/A this step and continue in this procedure at step 3.4 2.
3.4.2 If an order to evacuate non-emergency responders has not be issued, Then upon completion of Assembly and Accountability, initiate the order to evacuate non emergency responders, through the implementation of EPIP-8, Appendix F, concurrently with this procedure If the order to evacuate non-emergency responders has been conducted, Then continue in this procedure at step 3.5 1 INITIALS TIME INITIALS TIME 3.5 DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment (N/A STEP IF NOT APPLICABLE) 3.5.1.1 When, offsite dose assessment is required, obtain the information from the CECC when operational 3.5.1.2 If the CECC is not operational, contact the TSC, when staffed, or the RADCON Shift Supervisor and request the implementation of EPIP 13, for dose assessment INITIALS TIME PAGE 4 OF 10 REVISION 27
SITE AREA 4
BROWNS FERRY EMERGENCY rEPIP-+
NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 NOTIFICATION OFTHE NRC.
3.6.1 "Notifv the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, andif,,
requested by the NRC maintain an open and continuous INITIALS TIME communications channel Note: Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, by dialing 9-1 "The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is'achieved. No access codes are required 3.7 PERIODIC EVALUATION OF THE EVENT 3.7.1 Continue to Evaluate the event using EPIP-1 as conditions warrant.
3.7.2 If plant conditions warrant the need for follow up information, Complete the Follow Up Notification Form, Attachment C.
Note: Conditions that war-rant this evaluatioh'are as a minimuifi when other EAL conditions exist indicating the current emergency casscation or significant changes in plant conditions have occurred.
3.7.3 If the CECC is not staffed, Then hotify ttjeODS 'and providefollow up' information from the completedAittachment C form Utilize ihe direct ring-down ODS phone when making this"notifi6atiofi or'as 'ailplicable dial 'direct.
ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by iequesting the Rad Health Duty Office6r at:- "
Day Shift 8 a m - 5 p m (Central'Tine)
Hohdays-Weeed-Off-hfts Primary 9-1-334-206-5391 Montgomery State Trooper Post Backup:`' 9-1-800-582-1"866 9-1-334-242-4378 REVISION 27
,PAGE 5 01710
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PERIODIC EVALUATION OF THE EVENT (CONTINUED) 3.7.4 If the conditions warrants upgrading to a higher classification, Then initiate EPIP-5, General Emergency 3.7.5 If the conditions warrant termination of the classification, Then enter EPIP-16, Termination and Recovery Procedure 3.7.6 After the evaluation has been completed, if staffed, Notify the following of the status
"* CECC
"* NRC (ENS)
"* TSC
"* OSC
"* CONTROL RooMts 0
PL-N'TPA ANNOUNCE\\MENT 3.7.7 Re-enter this procedural section as conditions warrant at step 3.7 1 or until directed to exit this procedure by steps 3 7 4 or 3 7 5.
3.8 CLOSURE OF THE SITE AREA EMERGENCY 3.8.1 Upon termination of the Notification of Site Area Emergency, the Shift Manager shall send the completed EPIP-4 and all attachments to Emergency Preparedness (EP) 3.8.2 Upon receipt of completed EPIP-4 and all attachments, Emergency Preparedness shall forward documents for the purpose of documentation storage.
4.0 ATTACHMENTS Attachment A - Initial Notification Form Site Area Emergency Attachment B - Unit 1, Unit Operator Notifications Attachment C - Follow Up Information Form Site Area Emergency INITIALS TIME INITIALS TIME PAGE 6 OF 10 REVISION 27
SITE AREA
'EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM SITE AREA EMERGENCY
[I THIS'IS A REAL EVENýT K] 'THIS IS A DRILL This is A SITE AREA EMERGENCY has been declared -at Browns Ferry affec'ting:
K-Unit I E] Unit 2
] Unit 3
-] Common Evenut Decdared:
Time "Date.
EAL-Designator:
Brief Description of the Event:
Radiological Conditions:
FD No Abnormal Releases Offsite Airborne Release Offsite F-- Iiquid Release Offsite Release Information Not Known at this time
- There is no Protective Action Recommendation at this time.
F-- Meteorological conditions are:
Wind Speed.
m~p.h" Wind Direction From-degrees
[-- Ask "Please repeat the information you have received to ensure accuracy PAGE -7 OF 10 REVISION 27
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
/
NOTES: (1) The Emergency Paging System consists of a dedicated touch screen CRT Activation of any screen feature requires the user place their fingertip within the boundary of the select button and leave it there for at least I second. The CRT Screen will normally display a large rectangle that indicates that the paging system is available but currently inactive.
(2) If the EPS fails to operate, contact the SM/SED immediately Request that the ODS be contacted to initiate the system from his location If the system fails to operate from the ODS area, then utilize the Weekly Duty List and Call-Out List to manually staff the Emergency Responders, implementing this attachment at step E
- 1. Activation of the Emergency Paging System (EPS)
A PRESS the EPS CRT Screen once to activate the paging options B
PRESS the appropriate option
"* PAGER TEST
"* DRILL
"* EMERGENCY
"* STAGING AREA
"* ABORT C
PRESS the START Button to initiate the option or ABORT to deny the option request.
D MONITOR the Paging System Terminal Display I
IF. A "NO" response is observed OR The position being paged has not responded within approximately 20 minutes THEN. Utilize the Weekly Duty List and attempt to contact the position representative with available information (No Fitness for Duty Question Required)
- 2.
IF. The individual cannot be reached utilizing the Weekly Duty List THEN.. Utilize the Call-Out List and attempt to contact an alternate position representative (Fitness for Duty Question Required)
PAGE 8 OF 10 INITIALS TIME INITIALS TIME INITIALS TIME INITIALS TIME REVISION 27
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 2 of-2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
/
E.
-Manual Call-Out (N/A step if EPS operates normally).
INITIALS TIME
- 1.
Utilize the current Weelky Duty List and contact positions as listed 2
If a position can not be reached from the current Weekly Duty list, then refer to the Call-out List as-applicable to fill all vacant positions.
F CONTINUE until all positions have been filled
- iNITIALS, TIME
- 2. Notify the Unit Supervisors on shift.
INITIALS TIME
- 3. NotifY Nuclear Security Shift Supervisor and state "AN SITE AREA EMERGENCY HAS BEEN DECLARED" and direct to INITIALS TIME activate EPIP-1 1, Security and AccessControl.
Plant Extension 3150 or 2219
- 4. Notify the Chemistry Lab Supervisor and state "AN SITE AREA EMERGENCY HAS BEEN DECLARED" and direct to implement 2/3-TI-33 1, Post Accident Sampling Procedure and CI-900 series, Analysis Procedures
/
Plant Extension 2367 or 2368
- 5. Notify the RADCON Shift Supervisor and state "AN SITE AREA EMERGENCY HAS BEEN D ECLARED" and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension 7865 or 3104
- 6. Notify the "On-Call" NRC Resident and state "AN SITE AREA EMERGENCY HAS BEEN DECLARED"'
Plant Extension 2572 [Secretary] or from weekly duty list INITIALS
-~
I-INITIALS TIME INITIALS ;
-TIME PAGE 9 OF 10 TIME REVISION 27
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page I of 1)
FOLLOW-UP INFORMATION FORM SITE AREA EMERGENCY L-THIS IS A REAL EVENT E--
THIS IS A DRILL Note This form is for conducting Follow-up Information only.
This is at Browns Ferry Name There has been a Site Area Emergency declared at Browns Ferry affecting:
L-1 Unit I
-I Unit 2
-] Unit 3 I] Common The Reactor is nI Shutdown L-At Power Plant Conditions are I-Stable FI Deteriorating "Follow-Up" Information (e g, Key Events, Status Changes)
Current Radiological Conditions are:
I] No Abnormal Releases Offsite RI Airborne Release Offsite LI Liquid Release Offsite RI Release Information Not Known Additional Rad information: (e g, release duration)
F-- There is no Protective Action Recommendation at this time Please repeat the information you have received to ensure accuracy.
The time for this follow up is Time:
Date SIGNATURE:-
LAST PAGE PAGE 10 OF 10 REVISION 27
-TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-5 GENERAL EMERGENCY REVISION 32 PREPARED BY: T W CORNELIUS RESPONSIBLE ORGANIZATION EMERGENCY PREPAREDNESS APPROVED BY:
GILBERT LITTLE EFFECTIVE DATE 10/29/2002 LEVEL OF USE: REFERENCE USE QUALITY-RELATED PHONE" 2038 DATE 10/18/2002
ý f
REVISION LOG Procedure Number:
EPIP-5 Revision Number:
32 Pages Affected:
5 Description of Change:
IC-37 This change is being conducted to incorporate a manual method of cacuating on-site, non emergency response personnel during emergency situations In addition changes to the procedure are being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713. and to human factor the notification and followN-up notification forms.
Page 2 - change to step 3.2.1 involves human factoring the Notification Form Title and revised telephone for Morgan CountN'.
Page 3/4 - changes to steps 3 4 1 - 3 4.5 involves information regarding steps for the SED to take Nl hen conducting an Accountably/Assembly and Evacuation Page 6 - changes involves removing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps Page 7 - change involves human factoring attachment title Page 8 - change involves human factoring attachnment title Page 9 - change involves adding information for Unit I Operator regarding ERO staffing support Page 10 - revised to update infomiation supporting Unit I Operator actions regarding ERO staffing support.
Page 11 - revised Protective Action Recommendation Flowchart Page 12 - change involved adding a clarifR statement concerning the appropriate use of the Follow-up Notification Form IC-38 EPIP-4. revision 25 is being issued to incorporate changes regarding assembly and accountability actions All actions to initiate the accountability and el acuation processes are now located in EPIP 8 The rex ision additionally standardizes telephone numbers, and PORC rex iew s This rex ision also adds clarification for the actions taken by the Unit 1 Unit Operator during their staffing of the ERO process Page 3 - added a statement to the caution information regarding securitN threat Clarified steps 3.4.1 and 3 4 2 to implement EPIP-8 regarding actions to be taken for assembli/accountabihtN and eN acuation Page 6 - standardize Site Area Emergency procedure closure information.
Page 8.9 - Clarify actions taken by the Unit 1 Unit Operator during the notification attachment IC-39 EPIP-5. rex ision 3 1 is being conducted to incorporate changes regarding actions to be taken w hen dangerous conditions emist on site that would require the assembly of ihe ERO at the staging area Additionally page 3 and 6 wiere rex ised to update telephone information regarding the Office of Radiation Control.
Page 2 - change instruct the SED wihen to direct the Unit I Unit Operator to asseniblN the ERO at the staging area.
Page 4 - rex ision adds clarification to the caution note regarding on-site security conditions for assembhN/accountability Page 9 - rex ision adds option for staging area IC-40 EPIP-4. revision 32 is being conduct to change the procedure reference for Dose Assessment from EPIP-14 to EPIP-13 Page 5 of this procedure is be rexised
GENERAL EMERGENCY
-EPIP-5 BROWNS FERRY NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate'individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as a GENERAL EMERGENCY (GE) 1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the GE slhduld be terminated, or continued 2.0 SCOPE This procedure applies to emergency events that are classified as General Emergency by EPIP-1, Emergency Classification Procedure.
r SPAGE,1 OF 12 REVISION 3 2
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS Date:
/
/
3.1 If all Emergency Centers ARE STAFFED, Then notify the following that a GENERAL EMERGENCY Emergency Classification has been issued and EPIP 5 is being implemented, and continue in this procedure at Step 3.4 If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure CECC TSC OSC F]
D D1 Control Rooms E]
Plant PA Announcement D-This i, N \\WE. Site Emergent,, Director. an GE has been declared at BFN. "se are currentlv iniple*nentiig EPIP-5. Standby for fuirther updates.
3.2 Notification of the Operations Duty Specialist (ODS) & Emergency Responders Note The ODS should be notified within 5 minutes after the emergency event is declared 3.2.1 Complete Attachment A (Initial Notification Form) 3.2.2 Activating Emergency Response Organization (ERO) 3.2.2.1 If ongoing/anticipated on-site security events may present a danger to the emergency responders, Then consult with Nuclear Security 3.2.2.2 If ongoing/anticipated events present a danger to emergency responders, Then direct the Unit I Unit Operator to make notifications per Attachment B and select "Staging Area" as the option for the Emergency Paging System 3.2.2.3 If there are no ongoing/anticipated danger to emergency responders, Then direct the Unit I Unit Operator to make notifications per Attachment B and select as applicable, "Drill" or "Emergency" as the option for the Emergency Paging System
- IN1ITLXL, rl%[E I aTI u1s TLmE INITLXL%
rFIIE I NITLLL*,
I IME PAGE 2 OF 12 INII L\\IS TINIE REVISION 32
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2.3 Notify the ODS and Provide the information from Attachment A Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS Telephone Nuimberis" 5-751-1700; 2495 If the ODS cannot be r'eached within 10 minutes,'Then contact the following and Provide-th6'ihformiftion from' Attachment A
- 1. Limestone County:
9-232-0111
- 2. Morgan County:
9-1-256-432-2143 INITLULS TIME I NiTaLS INITIfL TIME
- 3. Lav;rence County:
"9-1-256-974-7641
- 4. Lauderdale County:
9-1-256-760-9117
- 5. State of Alabama Rad Jlealtl Duty Officer:
a m - 5 p m (Central) 9-1-334-206-5391 9-1-800-582-1866 Holidays-Weekends-Off-Shifts Montgomery State Trooper-Post 9-1-334-242-4378 3.2.4 Fax a copy of Attachment A to the ODS for confirmation of information or the state if contacted directly.
INITIALS
,ODS Fax 5-751-8620 Offie of Radiation Control Fax" 62i )34-'206 5387--
3.2.5 Receive conifirmation call from the ODS 't6 'erify notification of the State bf Alabama), (N/A this'step if the State was contacted diiectly)
INITIALS
! PAGE 3 OF 12 Day Shift 8 Primary:
Backup:-
I INITLULS TLmE INITEALS TLnIm
- INITULS, TIME TIME TIME 1
REVISION 32
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A announcement:
THIS IS (NAAME), SHIFT MANAGER A GENERAL EMERGENCY HAS BEEN DECLARED ON UNIT I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME.
INITIALS TIME CAUTION: Do not initiate Assembly and Accountability if:
1 A severe weather condition exist or projected on-site, such as a Tornado 2 An on-site security risk condition exists that may present a danger to site personnel during the assembly/accountability process (Consult with Nuclear Security).
3.4 ACCOUNTABILITY AND EVACUATION OF NON-ENIERGENCY RESPONDERS 3.4.1 If Assembly and Accountability has not been conducted,
- Theji, implement EPIP-8, Appendix C concurrently with this procedure If Accountability has been conducted, Then continue in this procedure at step 3 4 2 3.4.2 [fan order to evacuate non-emergency responders has not be issued, Then upon completion of Assembly and Accountability, Initiate the order to evacuate non emergency responders, through the implementation of EPIP-8, Appendix F, concurrently with this procedure If the order to evacuate non-emergency responders has been conducted, Then continue in this procedure at step 3.5 1 INITIALS TIME INITIALS TIME PAGE 4 OF 12 REVISION 32
GENERAL EMERGENCY
-EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment.,
(N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is required Obtain the information from the CECC when operational 3.5.1.2 If the CECC is not operational, Contact the TSC, when staffed or the RADCON Shift Supervisor and Request the implementation of!
,EPIP 13, for dose assessment.
3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if requested by the NRC maintain an open and continuous communications channel.,,
7 Note: Utilize the Emergency Notification System (ENS) when making this notification Dial the first number listed on the sticker affixed to the ENS telephone, by dialing 9-1 "The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved: No access codes are required 3.7 PROTECTIVE ACTION RECOMMENDATION INITIALS TIME I
INITIALS TIME 3.7.1 If the CECC is not staffed, Then make a Protective
, I__
Action Recommendation (PAR) using Attachment C.,
"'INITIALS TIME (This PAR shall be made bnly'b1y the SED.)
I (N/A STEP IF NOT APPLICABLE)
REVISION 32 I
I' I
, PAGE 5 OF 12
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 PERIODIC EVALUATION OF THE EVENT 3.8.1 Continue to Evaluate the event using EPIP-1 as conditions warrant.
3.8.2 If plant conditions warrant the need for follow-up information, Complete the Follow-Up Notification Form, Attachment D.
Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred 3.8.3 If the CECC is not staffed, Then notify the ODS and provide follow up information from the completed Attachment D form. Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct.
ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at:
Day Shift 8 a m - 5 p m (Central Time)
Primary 9-1-334-206-5391 Backup:
9-1-800-582-1866 Holidays-Weekends-Off-shifts Montgomery State Trooper Post 9-1 -334-242-43 78 3.8.4 If the conditions warrant termination of the classification, Then enter EPIP-16, Termination and Recovery Procedure.
3.8.5 After the evaluation has been completed, if staffed, Notify the following of the status
"* CECC
"* NRC (ENS)
"* TSC
"* OSC
"* CONTROL RooNis
"* PLANT PA ANNOUNCEMENT 3.8.6 Re-enter this procedural section as conditions warrant at step 3 8 1 or until directed to exit this procedure by steps 3 8 4 PAGE 6 OF 12 REVISION 32
GENERAL EMERGENCY
- EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.9 CLOSURE OF THE GENERAL!EMERGENCY, 3.9.1 Upon termination of the Notification of General Emergency, the Shift Manager shall send the completed EPIP-5 and all attachments to Emergency Preparedness (EP) 3.9.2 Upon receipt of completed EPIP-5 and all attachments, Emergency Preparedness shall forward documents for the nurnose of documentation storage INITIALS TIME INITIALS
,,TIME' 4.0 ATTACHMENTS Attachment A - Initial Notification Form General Emergency Attachment B - Unit 1, Unit Operator Notifications Attachment C - Protective Action Recommendations Attachment D --Follow Up Information Form General Emergency
- II 1
A A PAGE 7 OF 12 REVISION 32
GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM GENERAL EMERGENCY F1-THIS IS A REAL EVENT F--1 THIS IS A DRILL This is N=UmIE There has been a GENERAL EMERGENCY declared at Browns Ferry affecting F-1 Unit I F-- Unit 2 n
Unit 3 El Common Event Declared Time:
Date:
EAL Designator Brief Description of the Event Radiological Conditions:
No Abnormal Releases Offsite Airborne Release Offsite Liquid Release Offsite Release Information Not Known at this time The following Protective Action Recommendation is provided Recommendation I - Evacuate 2 mile radius and 10 miles downwind and shelter remainder of 10 mide EPZ Recommendation 2 - Evacuate 2 mile radius and 5 miles downwind and shelter remainder of 10 mile EPZ Meteorological Conditions are:
Wind Speed m p.h Wind Direction From degrees i Ask, "Please repeat the information you have received to ensure accuracy PAGE 8 OF 12 REVISION 32
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
I NOTES: (1) The Emergency Paging System consists of a dedicated touch screen CRT.
Activation of any screen feature requires the user place their fingertip within the boundary of the select buitfon-ancd leave it there for ai leasi I second. The CRT Screen will normally display a large rectangle that indicates that the paging system is available but curiently inactive.
(2) If the EPS fails to operate, contact the SM/SED immediately. Request that the ODS be contacted to initiate the system from his !ocation., If the system fails to operate from the ODS area,.then utilize the WeeklyDuty.List and Call-Out List to manually staff the Emergency Responders, implementing this attachment at step E.
- 1. Activation of the Emergency Paging System (EPS)
"A.
PRESS the EPS CRT Screen once to activate the paging options B.
PRESS the appropriate option PAGER TEST 0 DRILL EMERGENCY
- STAGING AREA'
- ABORT C.
PRESS the START Button to initiate the option or ABORT to deny the option request.
D MiONITOR the Paging System,Terminal Display
- 1. IF.. A "NO" response is observed INITIALS TIME INITIALS TIME INITIALS TIME INITIALS TIME OR The position being paiged has notnresporded within approximately 20 minutes THEN... Utilize the Weekly Duty-Listland attempt to contact the position representative with,ý available information (No Fitness for Duty Question Required)
- 2.
IF.. The individual cannot be reached utilizing the Weekly Duty List 7 THEN... Utilize the Call-Out List and attempt to
-contact an alternate pbsiti6n representative. (Fitness for Duty Question, Required)
PAGE 9 OF 12 REVISION 32 1
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 2 of 2)
UNIT 1, UNIT OPERATOR NOTIFICATIONS Date:
/
/
E Manual Call-Out (N/A step if EPS operates normally)
I Utilize the current Weelky Duty List and contact positions as listed.
2 If a position can not be reached from the current Weekly Duty list, then refer to the Call-out List as applicable to fill all vacant positions F_
CONTINUE until all positions have been filled.
- 2.
Notify the Unit Supervisors on shift.
- 3.
Notify Nuclear Security Shift Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED" and direct to activate EPIP-11, Security and Access Control Plant Extension 3150 or 2219
- 4. Notify the Chemistry Lab Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED" and direct to implement 2/3-TI-33 1, Post Accident Sampling Procedure and CI-900 series, Analysis Procedures 0
Plant Extension 2367 or 2368
- 5. Notify the RADCON Shift Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED" and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension 7865 or 3 104
- 6. Notify the "On-Call" NRC Resident and state "A GENERAL EMERGENCY HAS BEEN DECLARED" Plant Extension 2572 [Secretary] or from weekly duty list INITIALS TIME INITIALS TIME INITIALS TIME PAGE 10 OF 12 INITIALS TIME INITIALS TIME INITIALS TIME INITIALS TIME REVISION 32
GENERAL EMERGENCY
- EPIP -5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the floxwchart, then answier NO (Gene"e r-a-I -E mne r g e nc y' Declared j
CONTI1]
- Modifypi on availal monitorir Locate an orMeasuhotr pDts.
S5 miles is the Projected NO (x
or Measured Dose S~Greater than PAG TablelILimits QUE-ASSESSMENT rotective actions based ble plant and field ig information.
Ld evaluate localized i.-
I I I C 4L A
PAGE 11OF12 REVISION 32 RECOMMENDATION 1 EVACUATE 2'miles radius and 10 miles downwind AND SHELTER remainder of
-10 mile EPZ I
RECOMMENDATION 2 EVACUATE 2 mile radius and 5 miles downwind
"-AND
-SHELTER remainder of 10 mile EPZ STABLE I Protective Action Guides TYPE LIMIT Measured 3.9E-6 micro Ci/cc of Iodine 131 or
,I REM/hr External Dose Projected I REM TEDE or 1 5 REM Thyroid CDE A
ALk
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D (Page 1 of 1)
FOLLOW-UP INFORMATION FORM GENERAL EMERGENCY F-1 THIS IS A REAL EVENT
[-I THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry Name There has been a General Emergency declared at Browns Ferry affecting L] Unit I
-- Unit 2
-I Unit 3 Common The Reactor is F Shutdown Plant Conditions are R Stable FI-At Power F-1 Deteriorating "Follow-Up" Information (e g, Key Events, Status Changes, Status of any Plant Evacuations)
Current Radiological Conditions are:
L-i No Abnormal Releases Offsite F--
Airborne Release Offsite n
Liquid Release Offsite LI Release Information Not Known Additional Rad information (e g, release duration)
The current meteorological conditions from the site are:
Wind Speed
, Wind Direction from The following Protective Action Recommendation is provided.
L-Recommendation 1 F] Recommendation 2 Please repeat the information you have received to ensure accuracy The time for this follow up is Time:
Date SIGNATURE:
LAST PAGE PAGE 12 OF 12 REVISION 32
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-6 ACTIVATION AND OPERATION OF THE
%TECHNICAL SUPPORT.CENTER (TSC) -.
REVISION 22 A:
I r
PREPARED BY: TIM CORNELIUS US PHONE 203 RESPONSIBLE ORGANIZATION EMERGENCY PREPAREDNESS APPROVED BY: GILBERT v.I.,ITrLE aa I
-aD-A TE:- 10-'25-2002 EFFECTIVE DATE: 10-29-2002 LEVEL OF USE: REFERENCE USE QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-6 Revision Number:
22 Pages Affected:
3, 4,16,23, 26-30 Pagination Pages:
NONE Description of Change:
IC-25 This change is being conducted to revise the listing of TSC/OSC personnel necessar, for meeting staffing requirements to declare the TSC Operational. remove information regarding the EP Call Out List. now contained in EPIP 17. revise the contingency section regarding the use of procedures, and human factors checklists to clarify responsibilities Additionally this revision N ill remove the Technical Assessor #3 position from the ERO staff Page 1 - Remove information concerning the EP Call Out List The infornation is now contained in EPIP-17 Page 1 - This change removed the contingency for the use of procedures during declared radiological emergencies Information contain use of procedures during emergencies are contained in SPP 2.2 and OPDP-l.
Page 3 - Deleted the Teclmhical Assessor #3 Checklist. Human Factored Attachment A title, and Re-lettered attachments Page 4 - Human factored title of Attaclunent A Page 5 - Revised listing of personnel required for the operational declaration of the TSC Page 8 - Revised Operations checklist to more clearlk identifx the NRC Coordinator as the spokesperson for NRC conmmnuications Nxithin the site organization Page 9 - Revised to update CECC Title Changes Page 16 - Added infornation to responsibilitN section of the TSC Communicator checklist to more clearl\\ identifx responsibilitx of board vN-riter Page 21 - Revised to clarify responsibility of the Site VP regarding interface \\\\ith ne\\\\s media Page 19 - Removed Attachment N "'Technical Assessor #3 Checklist' Pages 19 Re-Lettered Attachments IC-26 Revision 22 is being conducted as a part of standardization EPIP-20 is being canceled EPIP-6 is being rel ised to include infornation from that procedure In addition to the standardization rexision. page 4. Attachment A is being revised for human factors, per comments from operations JPM's.
___11
ACTIVATION AND OPERATION EPTIP BROWNS FERRY OF THE TECHNICAL SUPPORT
'EPIP-NUCLEARPLANT CENTER ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER (TSC) 1.0
- PURPOSE, The purpose of this procedure is to describe the activation of the Technical Support Cent&er(TSC), and provide for TSC operation once it has been staffed. *Th'e TSC is staffed during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.
2.0 SCOPE This procedurecovers the emergency response from the TSC to support the shift operations staff during a radiological emergency, and direct the onsite response to the
-emergency.,
3.0 INSTRUCTIONS 3.1 The4TSC'will be staffed by qualified iriemberg reporting to the TSC upon hearing the Site Accountability Alarm, Plant Public Address System, activation 6f the Atitomated Paging System (APS) or upon being called for duty by the Unit 1, Unit Operator.
3.2 Required Actions for activation and operation of the TSC All members of the TSC staff complete the appropriate attachment for your position.
3.3 Other Information A list of emergency organizational telephone numbers are contained in the Radiological Emergency Notification Directory (REND).
3.4 Contingencies 3.4.1 NRC order The NRC role onsite is to observe, advise,' and coh'cnur with licensee decisions and' atioiis If aý situati6 n arises where the NRC wants an action taken regarding plant operation that TVA does not agree with, the SED shall require the NRC to sign a written order directing TVA to take the action before the SED will comply.
3.4.2 Evacuation - Relocate TSC to second level of office building. (Plant Manager's Office Area)
PAGE 1 OF 30 REVISION 22
ACTIVATION AND OPERATION E
P ROWNS FERRY OF THE TECHNICAL SUPPORT Ir
-6 NUCLEAR PLANT CENTER 4.0 LONG TERM OPERATION 4.1 Long-term operation will be put into effect during an Alert, Site Area Emergency, or General Emergency which exists or is projected to exist for more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.2 The SED will notify the CECC of the decision to begin long-term operation 4.3 Meal periods will be scheduled at the request of the SED 4.4 Sleeping facilities will be established as necessary in the second floor of the Plant Administrative Building (outside the gatehouse) Nuclear Security (NS) Supervisor will provide access control (If radiological or other conditions do not permit this area to be used, provisions will be made through the CECC for near-site lodging, or for other sleeping area onsite) 4.5 The Operations Lunch Room in the control bay at Elevation 3C will serve as an assembly room for meetings, etc. The plant assembly room can also be used if additional space is needed and radiological conditions exist 4.6 Additional personnel will be called in at the request of the SED to provide coverage or to ensure 12-hour or shorter shifts in the TSC 4.7 The SED, through the OSC Director, will establish 12-hour (or shorter) shifts for their craft personnel onsite and call in additional personnel as necessary 4.8 Following the immediate actions required for mitigating the accident, the need for additional actions for long-term operation should be appraised Actions required for long-term operation shall include evaluation of the following Diesel Generator fuel oil levels and usage rates Containment Atmosphere Dilution nitrogen tank level Reactor Building basement (and other Class I structures) for water accumulation Standby Gas Treatment filter/charcoal replacement needs PAGE 2 OF 30 REVISION 22
ACTIVATION AND OPERATION
'TTip BROWNS FERRY OF THE TECHNICAL SUPPORT nrJPJIr-6 ULA LN CENTER 5.0 ATTACHMENTS Attachment A - Initial Activation of TSC Attachment B - Site Emergency Director Checklist Attachment C - Operations Manager Checklist" Attachment D - RADCON Manager Checklist'
-Attachment E -Technical Assessment Manager Checklist Attachment F - Maintenance Manager Checklist Attachment G - Chemistry Manager Checklist Attachment H - Nuclear Security Manager Ch'ecklist Attachment I - Emergency Preparedness Manager Checklist Attachment J - NRC Coordinator Checklist Attachment K - TSC Communicator Checklist Attachment L - Technical Assessor # 1 (Reactor Engineer) Checklist Attachment M - Technical Assessor #'2 (I&C Engineer) Checklist Attachment N - Operations Specialist Checklist - Assistant RADCON Manager Checklist Attachment P - Site Vice President Checklist Attachment Q - Status Board Writer Checklist Attachment R -Technical Assessment Team Leader Checklist Attachment S - Site Engineering Manager Checklist Attachment T - Control Room Communicator Checklist Attachment U - Technical Support Center Clerk Checklist Attachment V - Plant Parameter Data Sheets PAGE 3 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP-6 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL ACTIVATION OF TSC Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the EPIP-8, Appendix I "Accountability Roster" maintained in the effected Unit Control Room
/
Unlock TSC
/
Unlock all TSC Supply Cabinets (Key in SHIFT MANAGER Key Box)
/
Post and Maintain Plant conditions on a Status Board. (Obtain updates from control!
room personnel.)
Emergency Classification Initiating Conditions Current unit status.
NOTE: Remain in TSC, until initial personnel arrive to man the TSC, report to SHIFT MANAGER for assigned duties PAGE 4 OF 30 REVISION 22
ACTIVATION AND OPERATION 6BROWNS FERRY
'OF THE TECHNICAL SUPPORT EPIPNUCLEAR PLANT CENTER
' ATTACHMENT B
.(Page 1 of 3)
SITE EMERGENCYXDIRECTOR CHECKLIST.
NOTE: (1) Maintain a log of activities and communications Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet.
/
Sign in on the Staffing Board.
/
Obtain complete turnover from the SHIFT MANAGER / SED (in the Control Room).
- Obtain copy of the SHIFT MANAGER / SED Log,
/
Verify the TSC and OSC are ready-for operation (when the following positions are staffed)
- Site Emergency Director R
Radcon Manager 11!
- Operations Manager or Operations Specialist Technical Assessment Manager or-4 Technical Assessment Team Leader or All of the or following Technical Assessor # I OSC Mechanical Engineer OSC Electrical Engineer
- OSC Director
- Electrical Supervisor
- Mechanical Supervisor
"* Instrument and Control Supervisor
"* Radcon Manager (on shift)
PAGE;5 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP-6 BROWNS FERRY NUCLEAR PLANT ATTACHlMENT B (Page 2 of 3)
SITE EMERGENCY DIRECTOR CHECKLIST (Continued)
Initials/Time Initial TSC Activation
/
Assume responsibility as SED from SHIFT MANAGER/SED
/
Make the following announcement over the Emergency Center P A System.
This is NAME
, I have assumed the responsibility of the Site Emergency Director I am declaring the TSC and OSC activated at TIME This is an actual emergency (or exercise - if an exercise, we need to treat this exercise seriously as if it were a real emergency and take complete advantage of this exercise as a learning experience)
Give plant status update
/
Have a plant wide P A announcement made that you have assumed responsibility
/
Establish communications with the CECC utilizing the direct ring-down phone or by dialing the director at 5-751-1614.
NOTE: (1) Maintain a log of activities and communications PAGE 6 OF 3R)
-I REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT B
,'(Page 3 of 3)
SITE EMERGENCY DIRECTOR CHECKLIST (Continued)
Initial TSC Activation Operational Responsibilities Follow appropriate EPIP steps for current Emergency Classification:
- 1. EPIP-2, "Notification of Unusual Event" 2
EPIP-3, "Alert" 3
EPIP-4, "Site Area Emergency" 4
EPIP-5, "General Emergency" Directs onsite emergency accident mitigation activities Consult with CECC Director and Site Vice President on significant events and their related impacts Establish and maintain site priorities for accident mitigation Initiates onsite protective actions Turn over SED Log to TSC Clerk Coordinates accident mitigation actions with the NRC Initiates long term 24-hour accident mitigation operations Responsible for the declaration of emergency classifications Authorize Emergency Radiation Exposures (EPIP-1 5)
Makes final approval on entries into radiologicailly hazardous areas when Radcon recommends against entry.
Periodic Requirements
- 1. Reevaluate the event by using EPIP-1 at least every TWO HOURS or more frequently if conditions warrant
- 2. Ensure update announcements to TSC and Control Room staffs (periodically and as conditions warrant).
3,.
Ensure update announcements to plantv workers over P.A System (periodically and as conditions Warrant),.
- 4. Ensure update status to OSC Director (periodically and as conditions warrant) 5., If CECC'is not activated, make Protective Action Recommendations as needed.
When Severe Accident Management Guidelines are entered, assume decision maker duties (If Qualified)
PAGE 7 OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIr-6 NUCLEAR PLANT CENTER ATTACHMENT C (Page 1 of 1)
OPERATIONS MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications.
Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet
/
Sign in on the Staffing Board
/
Establish commumcations with the Shift Manager in the Control Room
/
Establish communications with Operations OSC Manager in the OSC.
/
Assign knowledgeable individual (NRC Coordinator) to establish and maintain communications with the NRC via the Emergency Notification System (ENS) - as required Operational Responsibilities Directs operational activities.
Performs damage assessment and recommends solutions and mitigating action for operational problems Provide current update status from the Control Room to the SED and the TSC Staff Provide direction and control interface from the TSC to the Control Room Provide assistance to the SED as needed.
Provide status updates to the OSC Operations Manager.
Ensure the Unit Status Boards and Equipment Status Board are maintained Routinely update the SHIFT MANAGER and discuss priorities and status of OSC repair teams.
When Severe Accident Management Guidelines are entered assume evaluator duties (If Qualified).
REVISION 22 PAGE 8 OF 30
ACTIVATION AND OPERATION EPIPBROWNS FERRY OF THE TECHNICAL SUPPORT NUCLEAR PLANT CENTER ATTACHMENT D (Page 1 of 1)
RADCON MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications Initials/Tinie Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability LogSheet
/
Sign in on the Staffing Board
/
Establish communications with RADCON OSC Manager.
/
Establish communications with plant monitoring van (if dispatched and CEOC or CECC is not staffed)
- /,
Provide §omeone to communicate with NRC on the Health Physics Network (HPN) phone, as required Assign a RADCON Status Board writer.
Operational Responsibilities Directs and/or performs assessment of inplant and onsite radiological conditions Directs onsite RadCon activities.
A-Coordinates additional RadCon support with the CECC Radiological Assessment Manager.
Make recommendations for protective actions for onsite personnel.
Coordinates assessment of radiological conditions offsite with CECC Radiological Assessment Manager.
Makes final recommendation to SED for entries into radiological hazardous areas Collects and Provides plant radiological data to Emergency Facilities as applicable Provide assistance to the SED, as needed Provide status update to the SED.
Provide updates to the RADCON OSC Manager.
Ensure maintenance of the RADCON Status Maps/Boards in the TSC "I
IPAGE 9 OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-.
NUCLEAR PLANT CENTER ATTACHMENT E (Page lof 1)
TECHNICAL ASSESSMENT MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications.
Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader
/
Sign TSC Accountability Log Sheet
/
Sign in on the Staffing Board
/
Establish communication with the Technical Assessment Team Leader
/
Assign a Technical Assessment Team member as a TSC Board Writer.
/
Direct the TSC communicator to begin Monitoring SPDS and support status board collection or begin completing applicable portions of EPIP-20, Plant Data if SPDS is inoperable Operation Responsibilities Provide information, evaluations, and projects to the SED Directs onsite effluent assessment Keeps assessment team informed of plant status Directs activities of the Technical Assessment Team.
Communicate with the CECC Plant Assessment Manager Coordinates assessment activities with the CECC plant assessment team Ensures that Plant Status and Trend Boards are maintained.
Projects future plant status based on present plant conditions Provide assistance to the SED, as needed When Severe Accident Management Guidelines are entered assume evaluator duties (If Qualified)
PAGE 10 OF 30 REVISION 22
ACTIVATION AND OPERATION EPI-6 BROWNS FERRY
'OF THE TECHNICAL SUPPORT nrIR-6 NUCLEAR PLANT CENTER
- ATTACHMENT F
ý'!(Page,lof 1)
MAINTENANCE MANAGER CHECKLIST NOTE (1) Maintain a log of all activities andcommunications...
Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet.
/
Sign in on the Staffing Board
/
Establish Communication with OSC Team Manager, OSC Director and Assistant Director.
/
Obtain a turnover of damage assessment and repair activities.
Operational Responsibilities Directs repairs and corrective actions Performs damage assessment Directs activities of the Operation Support Center.
Make team assignments to OSC Team Manager.
Provide update OSC status to the SED
_:Provide assistance to the SED as needed:
J Provide status to the OSC Director,
,i Ensure OSC and TSC status boards are consistent Provide TSC personnel with a debriefing summary for each returning OSC team.
Communicate with the Assistant OSC director on matters concerning equipment and/or plant assessments'
,-PAGE II OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT G (Page lof 1)
CHEMISTRY MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader
/
Sign TSC Accountability Log Sheet
/
Sign in on the Staffing Board
/
Establish communication with the Chemistry Manager in the OSC.
/
Establish communication with the CECC Rad Assessment Coordinator
/
Confirm the Emergency Data Information System is in operation Operational Responsibilities Coordinates assessment of radioactive effluents with CECC Plant Assessment Team Collect Meteorological Data.
Maintain Release Status Board (jointly with RADCON)
Provide direction of Post Accident Sampling Activities.
NOTE: Ensure that plant configurations that are prerequisite to performing sampling have been completed prior to requesting a sample. The three hour time requirement begins upon a sample request, however, a request to prepare a team for sampling does not initiate the clock. Sampling teams should not be assigned a tracking number until the team is officially requested Provide assistance to the SED as needed Provide status updates to the SED.
Directs activities of the radiochemical laboratory and provides status update to the Chemistry Manager in the OSC Determines impact of incident on environment, radwaste, various effluent treatment systems PAGE 12 OF 30 REVISION 22
ACTIVATIONAND OPERATION T
6 BROWNS FERRY OF THE TECHNICAL SUPPORT rIP-l NUCLEAR PLANT CENTER ATTACHMENT H
,(Page lof1)
'NUCLEAR SECURITY MANAGER CHECKLIST, NOTE: (1) Maintain a log of activities and communications.
Initials/Time
. Initial TSC-Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet
/
Sign in on the Staffing Board.
/
Obtain status of site accountability.
I/
Ensure accountability status is reported to the SED within 30 minutes of initiating accountability
/
Assist in organizing search teams if needed.
/
- Restrict access to the protected area except for personnel whose name appears on the Emergency Access List or as authorized by the SED
/
Close all site access control points, which control personnel entering or leaving the site. -Only personnel authorized by the Emergency Access List or the SED will be allowed to enter.
/
When SAE or GE level emergencies have been declared no personnel except those who have, (1) been authorized by the SED, (2) accounted for by Nuclear Security and, (3) monitored by RADCON will be allowed to leave the site.
Operational Responsibilities Directs activities of Nuclear Security personnel.
Controls Access to Site and Control Rooms.
Reports on site accountability / evacuation as defined in BFN-EPIP's Provide update status to Security Shift Supervisors.
Provide update status to SED.
Provide assistance to SED as needed.
PAGE 13 OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT I (Page lof 1)
EMERGENCY PREPAREDNESS MANAGER CHECKLIST NOTE: (I) Maintain a log of activities and communications.
Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader
/
Sign TSC Accountability Log Sheet.
/
Sign in on the Staffing Board.
/
Call Clerical Support personnel.
/
Confirm all TSC and OSC positions are filled and SED informed. (Notify the Unit 1, Unit Operator when TSC and OSC are staffed)
/
Correct any activation problems
/
Confirm all "Initial TSC Activation" items are completed for all TSC positions.
Operational Responsibilities Advises SED regarding overall radiological emergency plan, use of implementing procedures, emergency equipment availability, and coordination with CECC Confirms site emergency centers are operating properly Provide assistance to the SED as needed Deactivation of the TSC
"* Collect all logs and information forms from all staff members in the TSC.
"* Place the TSC in a ready state PAGE 14 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER
.EPIP-6 BROWNS FERRY NUCLEAR PLANT ATTACHMENT J "I (Page lof 1)
NRC COORDINATOR CHECKLIST NOTE: (1) Maintain a log of activities and communications Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet.
/
Sign in on the Staffing Board. i Operational Responsibilities Acts as primary liaison with onsite NRC personnel.
Update NRC Personnel on plant status Provide information requests from NRC to TSC personnel.
I#
1#
PAGE.15 OF 30 REVISION 22
ACTIVATION AND OPERATIONlDID BROWNS FERRY OF THE TECHNICAL SUPPORT 12rIr-6 NUCLEAR PLANT CENTER ATTACHMENT K (Page lof 1)
TSC COMMUNICATOR CHECKLIST
[nitials/Tinie Initial TSC Activation
/
Swipe into Accountability Card Reader
/
Sign TSC Accountability Log Sheet
/
Sign in on Staffing Board.
/
Ensure operability of SPDS in the TSC Operational Responsibilities Maintain the Main SPDS terminal in the TSC in support of staff needs Support the status board writers in maintaining parameter and parameter trend board information Provides information from the control room to the Technical Assessment team as needed If SPDS or all electronic means for displaying plant parameter data becomes unavailable then, complete plant parameter data sheets, Attachment V of EPIP-6 every one-half hour or more frequently if required. Record data pertinent to the emergency or as prescribed by the TSC As data sheets are completed carry them to the TSC Clerical Staff for distribution If assigned as a TSC Status Board Writer follow these instructions
"* Monitor communications via the operations party line
"* Maintain the following status boards Affected Unit Trend Boards Technical Assessment Parameter PAGE 16 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER
'EPIP-6 BROWNS FERRY NUCLEAR PLANT ATTACHMENT L S(Page lof 1)
TECHNICAL ASSESSOR # 1 CHECKLIST
"(REACTOR ENGINEER)
NOTE: (1) Maintain a log of activities and communications Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet.
i,
Sign in on Staffing Board
/
Obtain needed documents and setup in the Technical Assessment Team Area Operational Responsibilities Completes trend graphs as needed Provides the TSC staff and CECC Plant Assessment Team with current assessments on plant conditions Project future plant status based on current conditions
'. I Provide Technical Support as needed.
When Severe Accident Management Guidelines are entered report to the TSC and assume evaluator duties (If Qualified).
, PAGE 17 OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT 12Y12-6 NUCLEAR PLANT CENTER ATTACHMENT M (Page lof 1)
TECHNICAL ASSESSOR # 2 CHECKLIST (INSTRUMENTATION AND CONTROL ENGINEER)
NOTE: (1) Maintain a log of activities and communications Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet
/
Sign in on Staffing Board
/
Obtain needed documents and set up in the Technical Assessment Team Area Operational Responsibilities Completes trend graphs as needed.
Provides the TSC staff and CECC Plant Assessment Team with current assessments on plant conditions.
Project future plant status based on current conditions Provide Technical Support as needed When Severe Accident Management Guidelines are entered report to the TSC and assume evaluator duties (If Qualified).
PAGE 18 OF 30 REVISION 22
ACTIVATION AND OPERATION 6
BROWNS FERRY OF THE TECHNICAL SUPPORT rEPIP-NUCLEARPLANT CENTER ATTACHMENT N
"'(Page Iof 1)
,OPERATIONS SPECIALIST CHECKLIST "
NOTE: (I) Maintain a log of activities and communications.,
Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log 'Sheet.
/
Sign in on Staffing Board.
/
- Establish communications with Control Room Communicator in the Control Room and OSC Operations Manager via party line.
Operational Responsibilities Provides operational knowledge for status evaluation of plant systems, Provides advice regarding technical specifications, system response, safety limits, etc..
Assists in development of recommended solutions to developing problems Provide plant data to the TSC Staff and to the Shift Manager. (Use party line)
Provide Assistance to the SED as needed When Severe Accident Management Guidelines are entered assume evaluator duties (If Qualified)
PAGE 19 OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT Ir-6 NUCLEAR PLANT CENTER ATTACHMENT 0 (Page lof 1)
ASSISTANT RADCON MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications.
Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet.
/
Sign in on Staffing Board
/
Begin providing information for the TSC RADCON Status Board writer Operational Responsibilities Provide Radiological Data to the RADCON Manager Assist the Chemistry Manager in maintaining the Release Status Board.
PAGE 20 OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT
-IP-NUCLEAR PLANT CENTER ATTACHMENT P
.(Page lof 1)
SITE VICE PRESIDENT CHECKLIST NOTE: (1) Maintain a log of activities and communications Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign TSC Accountability Log Sheet
/
Sign in on Staffing Board Operational Responsibilities Provides TVA policy direction to the Site Emergency Director (SED).
Directs the site resources to support the SED in the accident mitigation activities.
Interface with News Media through the Information Officer.
Assist the SED as needed.
At his discretion, may provide interface at the appropriate offsite location on the overall site response activities with, State and local agencies, NRC region/corporate, and Joint Information Center.
Provide direct interface on overall site response activities with NRC, FEMA, or other Federal organizations responding to the site.
Provides direct interface on overall site response activities with the CECC Director and onsite media.
Provides support to the other emergency operation centers as necessary.
PAGE 21,OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TEC14NICAL SUPPORT CENTER EPIP-6 BROWNS FERRY NUCLEAR PLANT In itials/Timne
/
/
/
/
ATTACHMENT Q (Page lof 1)
STATUS BOARD WRITER CHECKLIST (Unit/Equipment Boards)
Initial TSC Activation Swipe into Accountability Card Reader Sign TSC Accountability Log Sheet Sign in on Staffing Board Establish communications with OSC status Board writers Operational Responsibilities Maintain the following Status Boards
"* Equipment Problems
"* Unaffected Unit
"* Team Tracking REVISION 22 PACE 22 OF 30
ACTIVATION AND OPERATION EPIP :6 r
BROWNS FERRY OF THE TECHNICAL SUPPORT "EPIP26 NUCLEAR PLANT CENTER ATTACHMENT R
ý J(Page lof 1)
TECHNICAL ASSESSMENT.TEAM LEADER'CHECKLIST NOTE: (1) Maintain a log of activities and communications -.
Initials/Time Initial TSC-Activation
/
Swipe into Accountability Card Reader
/
Sign the TSC Accountability Log Sheet.'
/
Sign in on the Staffing Board
/
Report to Technical Assessment Team Area.,
/
Establish communications with the Plant Assessment Team in the CECC
/
Assign a technical assessor position to monitor the operation communication bridge.
Operational Responsibilities Performs systems assessment as directed by Technical Assessment Manager.
Determines condition of Reactor and Nuclear Fuel Acts as Plant Assessment Team Leader Provide updated information to the Plant Assessment Team.
Provide detailed technical assessments and recommendations to the TSC When Severe Accident Management Guidelines are entered remain in technical assessment team area and assume evaluator duties (If Qualified).
If plant parameter data cannot be displayed electronically, then assign the TSC Communicator to obtain plant parameter data utilizing Attachment V, of this procedure I -.PAGE 23 OF,30 REVISION 22
ACTIVATION AND OPERATION E PI BROWNS FERRY OF THE TECHNICAL SUPPORT I P-Y NUCLEAR PLANT CENTER ATTACHMENT S (Page lof 1)
SITE ENGINEERING MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the TSC Accountability Log Sheet
/
Sign in on the Staffing Board
/
Report to the Technical Assessment Team Area.
Operational Responsibilities Serves as the primary interface with Engineering.
Serve as a member of the Technical Assessment Team.
Provide Engineering Support to TSC PAGE 24 OF 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT nrIr-u NUCLEAR PLANT CENTER ATTACHMENT T
" (Page lofl1)
I CONTROLVROOM COMMUNICATOR CHECKLIST Initials/Time Initial TSCActivation
/
Swipe into Accountability Card Reader.,
/
Sign the TSC Accountability Log Sheet,
/
Sign in on the Staffing Board.','
/
Report to the affected Unit Control Room.
/
Establish Communications with the Operations Specialist (use party line).
Operational Responsibilities Provide updated plant parameters and status over the telephone to the Operations Specialist, Technical Assessment team areas and OSC operations personnel When Severe Accident Management Guidelines are entered remain in the control room and assume evaluator duties (If Qualified).
PAGE 25 OE 30 REVISION 22
ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT U (Page 1 of 1)
TECHNICAL SUPPORT CENTER CLERK CHECKLIST NOTE Maintain a log of activities and communications.
Initials/Time Initial TSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the TSC Accountability Log Sheet.
/
Sign in on the Staffing Board
/
Check the operability of the copy machine.
Operational Responsibilities Maintain log of events Answer telephones Operate facsimile machine Other duties as assigned by the Site Emergency Director Provide clerical support to the TSC Staff.
Maintain official SED Log As requested copy and distribute Plant Parameter Data Sheets to members of the TSC, fax a copy of the information to the OSC and CECC PAGE 26 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIPi6 BROWNS FERRY NUCLEAR PLANT ATTACHMENT V
'(Page 1 of 4)
PLANT PARAMETERS DATA SHEETS FOR UNIT-2/3 UNIT Time______
Date Parameter Reading Instrument, Panel Reactor Power 9-5 Operator 9-5 Reactor Water Level LI-3-58A/B 9-5A Eme-rgeficy Systeni Range
- (:155 to 60 inches)
- Reactor Water Level-
- LI-3-62A/52 9-3E (Accldent Range)
(-268 to +3,2 inches)
Rea'ctor Pressure Wide Range' PI-3-54/61/207 (0'1500 psig) 9-5A:
Drywell Pressure (Wide Range)
XR-64-159 Green Pen/160A 9-3E/3B1 S.
(0-300 psig)--
Drywell Temperature XR-64-50 (TE-64-52C) 9-3B31 Red Pen (00 to 4000t)'
e SUPPR CHBR PRESS PT-64-5 1(XR-64-52 green pen) 9-3B13 SUPPR Pool Water Level XR-64-159 Red Pen/i 59A 9-3E/3C, (Wide Range)
(0-20 fl)
SUPPR Pool Water TR-64-161/162"(30-230 0 F) 9-3D/3E Temperature
-Green Pen SUPPR CHBR XR-64-52 (TE-64-52B) 9-3B Air Temperature (0-400- F) (Red Pen)'
MSIV status OPEN/CLOSED (Circle Position),-
9-3A ReactrRecirc
-umpsIn
-- A / B / NONE--
(Circle Pumps Running) 9-4 Service
" Mark N/A if instrument pegged high PAGE 27 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP-6 BROWNS FERRY NUCLEAR PLANT ATTACHMENT V (Page 2 of 4)
PLANT PARAMETERS DATA SHEETS FOR UNIT 2/3 UNIT Time Date NON Affected Unit Status UNIT 1 / 2 / 3 )(Circle Un it)
MODE I MODE 3 / SHUTTING DOWN (Circle Condition)
UNIT I / 2 / 3 )(Circle Unit)
MODE I /MODE 3 / SHUTTING DOWN (Circle Condition)
Parameter Reading Instrument Panel FEEDWATER FI-3-78A + FI-3-78B (LBS/HR) 9-5
- HPCI System Flow Mode FIC 73-33 (0-6000 gpm) 9-3F L-I Injection F-Pressure Control
- RCIC System Flow Mode FIC 71-36A (0-700 gpm) 9-3C
-- Injection F-Pressure Control
- RHR Sys I Flow Mode FI 74-50 (0-25,000 gpm) 9-3D
[-LPCI
[- Torus Cooling
-l Torus Spray F-- Drywell Spray n-Shutdown Cooling
- RHR Sys II Flow Mode Fl 74-64 (0-25,000 gpm) 9-3E
-l LPCI F1-Torus Cooling
[- Torus Spray E-Drywell Spray F1-Shutdown Cooling Core Spray Sys I Flow Fl 75-21 (0-10,000 gpm) 9-3C Core Spray System II Flow FI 75-49 (0-10,000 gpm) 9-3F
- Check MODE or STATUS for injection systems PAGE 28 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER
"-EP.IP -6 BROWNS FERRY
-NUCLEAR PLANT "ATTACHMENT V
!.ý(Page 3 of 4)
PLANT PARAMETERS DATA SHEETS FOR 'UNIT 2/3 UNIT-i Time _
Date _
Parameter Reading Instruirient Panel (1)(2) Suppression Chamber H2 R 76-37 or 39 9-54, 55 H2
)onc.
(%) Green pen "
- 1)(2) Suppression Chamber 02 R 76-41 or 43 9-54, 55
'02 conc.
(%) Green pen (1 2)Drywell H2 conc H2 R 76-37 or 39 9-54, 55
(%)Red pen (I)(*)Drywell 02 con.,
02 R 76-41-or 433 54, 55;
(%)Red pen NOTE (1) - HS-76-49 and HS-76-59 must be checked to determine wi hat recorder pens are active-NOTE (2)
HS-76-72(82) and HS-76-73(8.3). Anal-zer A(B). 'Rdngc and Analyzer A(B) H2 Rafige. must be checked to detennine appropriate scale to read.
Paraihete
-Reading-Instrum-ent Panel Drywell Radiation RM-90-272A/RR-90-272 9-54 (red pen)(0-10 6 R/hr)
Drywell Radiation RM-90-273A/RR-90-273 9-55 (red pen)(0-10 6 R/hr)
SUPPR CHBR Radiation RM-90-272B (0-106 R/hr) 9-54 SUPPR CHBR Radiation RM-90-273B (0-106 Rhr) 9-55 Stack Gas Radiation O-RR-90-147 Red pen (Cps) 1-9-2 (From Unit 1 only) 4 Stack Gas Radiation 0.,'
,-RR-90-148 Black pen (Cps) 1-9-2, (From Unit I only)
I I PAGE 29 OF 30 REVISION 22
ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER EPIP-6 BROWNS FERRY NUCLEAR PLANT ATTACHMENT V (Page 4 of 4)
PLANT PARAMETERS DATA SHEETS FOR UNIT 2/3 UNIT __
Time Date Parameter Reading Instrument Panel OFFGAS STACK 0-RM-90-306 2-9-10 RADIATION MONITOR (WRGERMS) Noble Gas BLDG Release Fraction (Gas Log/Log AUO)
Unit I Stack Gas Flow 0-FI-90-271 1-9-53 (0-56,000 scfm)
(From Unit I only)
SGTS-I + 2 Flow to Stack (0-FI-65-50-2)+(0-FI-65-71-2) 2-9-25 (0-15,000 scfm)
Other Parameters As Reading Instrument Panel Specified Remarks After completion, carry to secretary in the TSC for distribution.
LAST PAGE PAGE 30 OF 30 REVISION 22
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-7
-.ACTIVATION AND OPERATIONOF THE" OPERATIONS SUPPORT CENTER (OSC)
REVISION 20 PREPARED BY: TIM CORNELIUS RESPONSIBLE ORGANIZATION. EMERGENCY PREPAREDNESS APPROVED BY GILBERT LITTLE EFFECTIVE DATE: 10/29/2002 LEVEL OF USE: REFERENCE USE PHONE 2038 DATE:
10/18/2002 QUALITY-RELATED
REVISION LOG Procedure Number EPIP-7 ReN ision Number 20 Pages Affected: 12.19 Pagination Pages All Description of Change IC-22 This re% ision is being conducted to correct minor changes to the procedure Page 5 - is being revised to correct page of attachment Page 6 - is being conducted remnowe a note referring to operations support, establishing the OSC initially Page 29 - is being re ised to update the OSC Iax out.
IC-23 This revision is being conducted to revise the chelmstrN lab supervisor checklist and OSC Chemistr. Manager checklist to include the items being removed from the revision of EPIP-13.
ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EP P' NUCLEAR PLANT CENTER (OSC) 1.0 PURPOSE 1.1 The purpose of this procedure is to describe the activities of the Operations Support Center (OSC) and the assessment and repair activities during a radiological emergency.
-2.0 Scope 2.1 The procedure covers the emergency response from the OSC during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.
3.0 INSTRUCTIONS 3.1 The OSC will be staffed by qualified members reporting to the OSC and staging area upon hearing the Site Accountability Alarm, Plant Public Address System, upon activation of the Automated Paging System (APS), or upon being called for duty by the Unit 1, Unit Operator.
-,NOTE: Refer to EPIP-8, Personnel Accountability and Evacuation 3.2 The OSC is located in two locations. '
"* The OSC is located on elevation 580' Service Building.
The OSC staging area located on elevation 565' of the Service Building Maintenance Lunch Room area.
NOTE: If necessary to evacuate the OSC, relocate to the second level of the Plant Office Building (Plant Manager's Office area)
,, PAGEI OF 29 REVISION 20
ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPI[r-i NUCLEAR PLANT CENTER (OSC) 3.0 INSTRUCTIONS (CONTINUED) 3.3 Operation of The OSC 3.3.1 Normal plant maintenance procedures will be followed whenever possible.
Should a situation arise where normal procedures would be inappropriate, maintenance will be performed as determined by the SED. If a situation is encountered in the field that threatens the safety of any team member, the Team Leader shall take appropriate action to prevent injury 3.4 Required Actions for Activation and Operation of the OSC 3.4.1 All members of the OSC staff complete the appropriate attachment for your position 4.0 LONG -TERM OPERATION 4.1 Upon receiving information from the TSC that emergency operation is expected to extend past 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the OSC Director will arrange to set up shift rotations NOTE: Calling in additional personnel may be necessary.
PAGE 2 OF 29 REVISION 20)
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
TEPIP-7 BROWNS FERRY NUCLEAR PLANT 5.0 Attachments Attachment A Attachment B Attachme'nt'C Attachment D Attachiment E Attachment F
. Attachment G Attachment H"-""
Attadhient I Attachment J
-- Attachment K. -.
Attachment L Attachmeni M Attachment N N Attachment P Attachment Q Attachment R Attachment S
- Attachment T -_
Attachinent U -
Attachhient'V -
Tearii'Tracking Form OSC Director Checklist RADCON OSC Manager Checklist "Fire Protection OSC Manager Checklist-,
Chemistry OSC Manager Checklist
- Operations OSC Manager Checklist Instrumentation and Controls OSC'Super'isoi Checklist-_
Mechanical OSC Supervisor Checklist Electrical OSC Supervisor Checklist
--RADCON Lab Supervisor Checklist
-- Fire Protection Shift Captain Checklist Chemistry Lab,Supervisor'Checklist OSC Enginees Check Listk, OSC Staging Area Manager.
Assistant OSCDirector
,: OSC Clerk Checklist, Status Board Writer OSC Team Manager Materials Coordinator OSC Planners Checklist.
OSC Document Control Checklist OSC-Configuration
- Ii.
'4'
2 t
I I'
I' 4
-I I.',
4 1
4 Er'
'4At 3.:',.
,PAGE3 OF 29 J
REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page I of 2)
TEAM TRACKING FORM TEAM DESIGNATOR (A, B, C, etc.)
TEAM PRIORITY (NA, 1, 2, 3, etc.)
Team Team Task:
M1anager I
Associated TSC Priorith:
Ini,,alt Time Task Location: UNIT L-1 E1-2
[:]3
-]Common 0 Rea tor Bldg.. Elc%. _
Conti ol lBax, Ele%.
[I Diesel Bld., Elei.
EU Furbine B1dg, Eltc.
0_
OHIIER (Be Specific)
Ele*.
Assist.
Responsible El Electilcal U I&C U R.D ON Director Section:
U EMechanlical
[I Operations U] Fire/Medic.d El 01 HER (Be Specific)
/
[E OSC Center Announcement:
lnitials Time Let me hai e. our attention, Team (Use Designator) has been requested from the TSC to (Describe Task). (Section Rep) has been assigned to plan this task.
Section Rep Team Members Team Leader Section:
/
_Section:
inutials Time Section:
Section:
Section:
Briefing Checklist D Description of Problem E] Kce (s) Needed for Task El Effecicd SNstem Status El Hazards to/from Work Site El Procedures to be Used D SafeWO E~aluation Di Dram ings to be Used El Operations Support D Tools/Equipmcni Needed ED RADCON Support El Clearances Needed El RWP Rcquircd/Bricf 0
Route to/from Work Site El Return as a team for De-Briefing Communications:
E] Hand-Held Radio, Channel El Telephone, proi ide OSC Number El Other RADCON RWP Utilized E]Yes L]No If.*es, RWP#
I Emergency Exposures Utilized L]Yes L]No (If Yes Approval Required, EPIP 15)
Initials Tume Potassium Iodine Utilized D]Yes L]No (If Yes Approval Required, EPIP 14)
OSC Director Final Approial By OSC Director
/
Initials Time "Is there any reason that Team (Uve Designator) should not be released at this time".
PAGE 4 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 2 of 2)
-, TEAM TRACKING FORM TEAM DESIGNATOR (A, B, C, etc.)
TEAM PRIORITY (NA, 1, 2, 3, etc.)
Section Rep Inittals Timne De-Briefing Summary Information E-Assignment Completed [- YES
-- NO Eli CANCELLED E] Equipment Status "As Left":
El 'Hazards Encountered (Actual or Potential)
El Equipment Clearance Status F-1 !Unusual Sounds, Additional Radiological Information, Other Task Applicable Information DE-BRIEFING cLO -SURE' I,
El Inform OSC Director of Team De-Briefing Summary D1 Direct Personnel to OSC STAGING AREA or Other
[E Update OSC Team Tracking Board I f-PAGE 5 OF 29 OSC Director 1--]TSC Notified. Team results provided to the TSC Maintenance Manager i
lnuzaI*
Time REVISION 20
ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC)
ATTACHMENT B (Page 1 of 3)
OSC DIRECTOR CHECKLIST NOTE: Maintain a log of activities and communications Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader
/
Sign the OSC Accountability Log Sheet
/
Sign in on the staffing board
/
Set up the OSC (assign any available personnel to assist)
"O Configure OSC area an arrangement similar to EPIP-7, Attachment V "O Clear tables "o Ensure telephones are in proper location and operating.
"O Open OSC supply cabinet "O Place notebooks in the proper position in the OSC "O Obtain needed documents Inform the SHIFT MANAGER/SED of your location and status Unit 1 2191/2192 Unit 2 2291/2292 Unit 3 2391/2392 Establish communication with the Maintenance Manager (TSC) (phone #
3.766)
Establish communication with the OSC Staging Area Manager (phone #
2244)
Confirm the OSC is staffed (Notify the Maintenance Manager) (phone #
3766).
PAGE 6 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPtP-7 BROWNS FERRY NUCLEAR PLANT Initials/Time
/
ATTACHMENT B (Page 2 of 3)
OSC DIRECTOR CHECKLIST (Continued)
Initial OSC Activaition (Continued)
Make the following remarks prior to activating-the OSC.
This is an actual emergency (or exercise - if an exercise, we need to treat this exercise seriously as if it were a real emergency and take complete-i i_, ý advantage of this exercise as a learning experience).
Be Professional
- Keep legible logs of all your activities.
- Be clear and precise in transfer of information.
- Make sure you are accurate with units as data are transferred.
.d l
a 11
- Keep noise level dowiin as low as possible.
Ensure that the Team Manager" 1---
Tracks any team(s) dispatched prior to OSC activation E-Form initial response teams (see note below)
Operational Responsibilities Provide Maintenance Manager with a debriefing summary for each returning repair/damage team Direct OSC activities through the Assistant OSC Director Communication with the SED as needed to ensure effective performance of the OSC.
Approve the dispatching of all teams.
Provide updates to the OSC personnel.
( PAGE 7 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT K>
ATTACHMENT B (Page 3 of 3)
OSC DIRECTOR CHECKLIST (Continued)
Operational Responsibilities! (Continued),
Provide updates to the OSC staging area personnel (approximately every one-half hour or as conditions warrant)
Ensure that all teams returning from assigned tasks are debriefed utilizing Attachment A of this procedure NOTE: Initial response teams are as a minimum.
- 1. One Medical Emergency/Fire Response Team.
- 2. Two RADCON Survey Teams
- 3. One Post Accident Sampling Team.
- 4. Two repair teams (each consists of at least one Mechanical, one Electrical, one Operations, and one RADCON)
- 5. Turbine Building el 565' Tool Room.
NOTE: If AREA is determined to be not habitable by Radcon discontinue this team #5.
K';
REVISION 20 I
PAGE 8 OF 29
ACTIVATION AND OPERATION TT T'7BROWNS FERRY OF THE OPERATIONS SUPPORT Erl-r-I-NUCLEAR PLANT CENTER (OSC)
ATTACHMENT C (Page 1 of 2)
RADCON OSC MANAGER CIHECKLIST NOTE: Maintain a log of activities and communications Initials/Time Initial Activation of the OSC,,
/
Swipe into Accountability Card Reader.
/
Sign the OSC Accountability Log Sheet.-
/
'Sign in on the staffing board :
/
Establish communication with the RADCON Manager in the TSC.
/
Establish communication with the RADCON Lab Supervisor.
/
Ensure adequate RADCON staff available for OSC support.
/
Assign a RADCON Technician to the MERT.
/
Assign a RADCON status board writer.
/
Complete "Team Tracking Forms" (Attachment A) for all RADCON personnel dispatched prior to the OSC activation and give to the Assistant OSC Director.
Operational Responsibilities Direct RADCON personnel in the RADCON lab.
Ensure all RADCON teams are dispatched through the OSC.
Provide assistance to the OSC Director, as needed.
Ensure as applicable that teams have RADCON coverage.
Brief the OSC Director of RADCON status Brief the RADCON Superintendent in the TSC on status SPAGE 9 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT K>
ATTACHMENT C (Page 2 of 2)
RADCON OSC MANAGER CHECKLIST (Continued)
Operational Responsibilities (Continued)
Complete and update "Team Tracking Forms" (Attachment A) for RADCON teams you are assigned.
Ensure that all predressed OSC staging area teams are issued proper dosimetry and have been evaluated for radiological access (i.e. watch list)
Ensure technical briefing to OSC teams of radiological conditions prior to dispatch K-I PAGE 10 OF 29 REVISION 20
ACTIVATION AND OPERATION I
BROWNS FERRY OF THE OPERATIONS SUPPORT "EPIr-i NUCLEAR PLANT CENTER (OSC) 2 ATTACHMENT D* (Page 1 of 1)
FIRE PROTECTION OSC MANAGER CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation'
/
Swipe into Accountability Card Reader.
/
Sign the.OSC Accountability Log Sheet.
/
Sign in on the staffing board
/
Establish communications with the Site Fire Protection Shift Captain and staff.
/
Complete "Team Tracking Forms" (Attachment A) for all Fire Protection
_,Personnel dispatched prior to OSC activation and give to the Assistant OSC Director.
Operational Respon~ibilities When possible allow Staging Area Fire Protection personnel to assist team in donning SCBAs Provide and coordinate site Fire'Protection resources as necessary'to support the OSC Director Assist in technic'al briefings of OSC teams as necessary.
Provide evaluations and projections on emergency air supplies.
¢*
l r" rg e, ne
,a,2, su*
Co m"lplete and update "Team Tracking Forms" (Aitachment A) for MERT and fire fighting teams you are assigned.
Provide industrial safety support to the OSC Director as needed Brief teams on industrial hazards as needed.'
-i tp i,
+
I,"
I
" PAGE 11 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT ATTACHMENT E (Page 1 of 1)
ATTACHMENT E (Page I of 1)
CHEMISTRY OSC MANAGER CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time
/
/
/
/
I
/
/
Initial Activation of the OSC !,
Swipe into Accountability Card Reader.
Sign the OSC Accountability Log Sheet.
Sign in on the staffing board.
Establish communication with the Chemistry Lab Personnel If no Chemistry Shift Supervisor is available in the lab, appoint a lead technician and call in the next shift Chemistry Supervisor.
Ensure adequate Chemistry staff is available to support the OSC Complete "Team Tracking Forms" (Attachment A) for all Chemistry Personnel dispatched prior to OSC activation, and give to the Assistant OSC Director.
Inform Lab Supervisor or Lead Radiochemical Lab Analysis (LRLA) to have technicians swipe into the Accountability Card Reader in the RADCON Lab, Sign the Chemistry Lab Accountability Log Sheets review emergency sampling/analysis procedures and prepare for implementation.
Inform Lab Supervisor or Lead Radiochemicai Lab Analysis (LRLA) to make preparations to implement 2/3 T1-33 1, Post Accident Sampling Procedure and CI-900 Series, Analysis Procedures Operational Responsibilities
"* Direct Chemistry assignments in the Chemistry lab.
"* Ensure all Chemistry teams are dispatched through the OSC.
"* Provide assistance to the OSC Director as needed
"* Brief the OSC Director of Chemistry status.
"* Complete and update "Team Tracking Forms" (Attachment A) for Chemistry teams you are assigned
"* Obtain necessary post accident samples (as directed by the OSC Director). The three hour time requirement begins upon a sample requested by the SED, however, a request to prepare a team for sampling does not start the time period Sampling teams should not be assigned a tracking number until the sample is officially requested.
K>J PAGE 12 OF 29 REVISION 20
ACTIVATION AND OPERATION EPIO-7 BOWNS FERRY OF THE OPERATIONS SUPPORT NUCLEAR PLANT CENTER (OSC)
ATTACHMENT F (Page 1 of 1)
OPERATIONS OSC MANAGER CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign in on the staffing board.
/
Notify the OSC Director and Shift Manager (affected unit Control Room) upon arrival to the OSC.
/
Establish communications with the Operations Communicator utilizing the "operations communications bridge.
/
Establish communications with supporting OSC Operations personnel
"(staging area).
/
Complete "Team Tracking Forms" (Attachment A) for all Operations Personnel dispatched prior to OSC activation, and give to the Assistant OSC Director. (EOI Activities)
Operational Responsibilities Provide and coordinate operations personnel to support the OSC Director.
Provide operations support to OSC teams that are dispatched into the field -,
Perform any operations actions that may be required while in the field-,
Keeps the SHIFT MANAGER apprised of OSC team activities while in the field.
Complete and update "Team Tracking Forms" (Attachment A) for Operations teams you are assigned Ensure the responsiveness of EOI field teams PAGE 13 OF 29 REVISION 20
ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEARPLANT CENTER (OSC)
ATTACHMENT G (Page 1 of 1)
INSTRUMENT AND CONTROL (I&C) SUPERVISOR CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the OSC Accountability Log Sheet
/
Sign in on the staffing board.
/
Notify the OSC Director upon arrival.
/
Establish communications with the supporting OSC I&C staff (staging area)
/
Complete "Team Tracking Forms" (Attachment A) for all I&C Personnel dispatched prior to OSC activation and give to the Assistant OSC "Director.
Operational Responsibilities Provide and coordinate I&C resources necessary to support the OSC Director and teams.
Provide technical assistance with I&C problems Perform damage and repair assessments.
Assist in technical briefings of OSC teams as necessary.
Complete and update "Team Tracking Forms" (Attachment A) for I&C teams you are assigned.
K>,_
PAGE 14 OF 29 REVISION 20
ACTIVATION AND OPERATION ThPIP7 BROWNS FERRY OF THE OPERATIONS SUPPORT E
NUCLEAR PLANT CENTER (OSC)
ATTACHMENT H (Page 1 of 1)
'MECHANICAL OSC SUPERVI1SOR CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the OSC Accountability Log Sheet.-
/
Sign in on the staffing board.,'
/
Notify OSC Director upon arrival.
/ "Establish communications with appropriate supporting OSC Mechanical staff (Staging Area)
',Complete.Team Tracking Forms",(Attachment A) for all Mechanical Personnel dispatched prior to OSC activation and give to the Assistant OSC Director.
Operational Responsibilities a
+
~
l l
Provide and coordinate Mechanical Maintenance resources necessary to support OSC Director and teams Provide technical assistance with mechanical system problems.
Perform damage and repair assessments.
Assist in technical briefings of OSC teams as necessary.
Complete and update "Team Tracking Forms" (Attachment A) for mechanical maintenance teams you are assigned.
PAGE 15 OF 29 REVISION 20
ACTIVATION AND OPERATION
-i'--TT-'-7 BROWNS FERRY OF THE OPERATIONS SUPPORT PIrr--
NUCLEAR PLANT CENTER (OSC)
ATTACHMENT IF (Page 1 of 1)
ELECTRICAL OSC SUPERVISOR CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader
/
Sign the OSC Accountability Log Sheet.
/
Sign in on the staffing board.,
/
Notify OSC Director upon arrival.
/
Establish communications with appropriate supporting OSC Electrical staff (staging area)
/
Complete "Team Tracking Forms" (Attachment A) for all Electrical Personnel dispatched prior to OSC activation.
Operational Responsibilities Provide and coordinate Electrical Maintenance resources necessary to support OSC Director and teams.
Provide technical assistance with electrical system problems Perform damage and repair assessments.
Assist in technical briefings of OSC teams as necessary.
Complete and update "Team Tracking Forms" (Attachment A) for Electrical Maintenance teams you are assigned.
PAGE 16 OF 29 REVISION 20
ACTIVATION AND OPERATION PIP 7 BROWNS FERRY OF THE OPERATIONS SUPPORT
'ErIr-NUCLEAR PLANT CENTER (OSC)
ATTACHMENT J (Page 1 of 1)
RADCON LAB SUPERVISOR (RADCON LAB) CHECKLIST NOTE: Maintain a log of activities and communications Initials/Time Initial OSC Activation
/
Swipe into'Accountability Card Reader..,,
/
'Sign RADCON lab Accountability Log Sheet
/
Establish communications with appropriate supporting RADCON Lab staff.
Operational Responsibilities Provide and coordinate RADCON personnel necessary to support the OSC teams Maintains an interface with the OSC RADCON Manager related to the radiological conditions in the plant.'
Ensure that adequate dosimetry is maintained for OSC teams PAGE 17 OF 29 REVISION 20
ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC)
ATTACHMENT K (Page 1 of 1)
FIRE PROTECTION SHIFT CAPTAIN (STAGING AREA) CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the OSC staging area Accountability Log Sheet
/
Ensure all ESTS sign the OSC Staging area Accountability Log Sheet.
/
Notify Fire Protection Manager (OSC) upon arrival.
/
Establish communications with the site Fire Protection staff.
Operational Responsibilities Monitor status of site Fire Protection/Life Safety systems and keep OSC Fire Protection Manager apprised.
Acts as Medical Emergency Response Team (MERT) Leader if EPIP-I 0 is implemented.
Keeps Fire Protection OSC Manager apprised as to status of emergency air supplies.
Directs the Fire Protection staffs activities when required to dispatch into the field for fire, medical, or other necessary support.
PAGE 18 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
\\EPIP-7 BROWNS FERRY NUCLEAR PLANT ATTACHMENT L (Page 1 of 1)
CHEMISTRY LAB SUPERVISOR (CHEMISTRY LAB) CHECKLIST NOTE: Maintain a log of activities and communications Initials/Time
/
/
/
/
/
/
Initial OSCActivation --
Swipe into Accountability Card Reader in the RADCON Lab.
Sign the Chemistry Lab Accountability Log Sheets Ensure the condensate oxygen injection system has been isolated if installed on the affected unit Establish communications with appropriate supporting Chemistry staff.
Ensure dose-rate monitoring instruments are functioning properly.
Have technicians swipe into the Accountability Card Reader in the RADCON Lab, Sign the Chemistry Lab Accountability Log Sheets review emergency sampling/analysis procedures and prepare for implementation.
Make preparations to implement 2/3 TI-33 1, Post Accident Sampling Procedure and CI-900 Series, Analysis Procedures.
Operational Responsibilities Provide and coordinate Chemistry Lab necessary to support the OSC teams.
Assist in technical briefings of OSC teams as necessary Obtain necessary post accident samples and performs analysis of samples (as directed by the OSC Director). The three hour time requirement begins upon a sample request by the SED, however, a request to prepare a team for sampling does not start the time period Sampling teams should not be assigned a tracking number until the sample is officially requested Maintains an interface with the Chemistry OSC Manager and provides results of sample analysis in a timely manner.
If Radiochemical Lab becomes inhabitable, report to a location determined by RADCON and inform the OSC Chemistry Manager.
PAGE 19 OF 29 I
REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT K>-
ATTACHMENT M (Page 1 of 1)
OSC ENGINEER'S CHECKLIST (ELECTRICAL - MECHANICAL - INSTRUMENTATION AND CONTROLS)
NOTE: Maintain a log of activities and communications.
Initials/Time
/
/
/
Initial OSC Activation Swipe into Accountability Card Reader.
Sign the OSC Accountability Log Sheet.
Sign in on the staffing board.
Ooerational Responsibilities Provide engineering support to the OSC staff.
K-'
PAGE 20 OF 29 REVISION 20
ACTIVATION AND OPERATION PBROWNS FERRY OF THE OPERATIONS SUPPORT EIP,-
NUCLEAR PLANT CENTER (OSC)
ATTACHMENT N (Page ' of 1)
,;OSC STAGING ýAREAMANAGER, Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.,
/
Sign the OSC Staging AreaAccountability Log Sheet.
/
Assign a foreman to'set up th.OSC staging area, include the following.
[-D Ensure all personnel in the OSC staging area card into the Accountability Card Reader.
E-- Ensure all personnel in' the OSC-staging area sign the Accountability Log Sheet ED Unlock Supply Cabinet Fl1 Install the OSC Staging Area Telephones Operational Responsibilities Maintain control in the OSC'stagifig area,
Assemble personnel and direct them to the OSC when requested Ensure adequate man-power exist in the OSC staging area (i e. Radcon, AUO's, Electrical, etc personnel)
Inform OSC manager of all time delays in team assembly.
I -PAGE 21 OF 29 REVISION 20 1 1,
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT K-,
ATTACHMENT 0 (Page 1 of 1)
ATTACHMENT, 0O1 (Page I of 1)
ASSISTANT OSC DIRECTOR CHECKLIST Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the OSC Accountability Log Sheet.
/
Sign in on the staffing board
/
Call Maintenance Planner.
/
Collect any completed Team Tracking Forms from OSC managers and route to OSC Team Manager.
Operational Responsibilities Ensure status boards are kept current.
Assign tasks to appropriate OSC managers when directed by OSC Team Manager Keep the OSC Director informed of task status.
Ensure the responsiveness of all personnel assigned to assemble and dispatch field teams.
Ku PAGE 22 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 SBROWNS FERRY NUCLEAR PLANT ATTACHMENT P (Page 1 of 1)
OSC CLERK CHECKLIST NOTE: Maintain a log of activities and communications Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader:.
/
Sign the Accountability Log Sheet. -' f I
Sign in on the staffing board.
Operational Responsibilities Maintain a log for the OSC Director.
Provide clerical support for the OSC and OSC Staging Area PAGE 23 OF 29 REVISION 20
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT Initials/Time
/
/
/
ATTACHMENT Q (Page 1 of 1)
ATTACHMENT Q (Page I of 1)
STATUS BOARD WRITER CHECKLIST Initial OSC Activation Swipe into Accountability Card Reader.
Sign OSC Accountability Log Sheet Sign in on Staffing Board.
Operational Responsibilities Maintain the following Status Boards (As assigned)
"* Affected Unit
"* Equipment Problems
"* Team Tracking Obtain up-to-date plant data from the OSC Operations Communicator.
K>
PAGE 24 OF 29 REVISION 20 1
ACTIVATION AND OPERATION
' EPIP BROWNS FERRY OF THE OPERATIONS SUPPORT
-rIr-,
NUCLEAR PLANT CENTER (OSC)
ATTACHMENT R (Page 1 of 1)
OSC TEAM MANAGER NOTE: Maintain a log of activities and communications Initials/Time Initial OSC Activation
/
Swipe into Accountabi!ity Card Reader.
/
Sign the Accountability Log Sheet.
/
Sign in on Staffing Board.
/
,Track any team(s) dispatched prior to the OSC activation.
/
Establish communications with the TSC maintenance manager (#3766)
Operational Responsibilities Initiate team Tracking Forms as requested by TSC Maintenance manager and forward to Assistant OSC Director upon acknowledgment by the OSC director.
Ensure that the team tracking board is consistent and accurate and that the information is being transferred in a timely manner to the TSC team tracking board writer PAGE 25 OF 29 REVISION 20
ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT
/NUCLEARPLANT CENTER (OSC)
ATTACHMENT S (Page 1 of 1)
MATERIALS COORDINATOR NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the Accountability Log Sheet.
/
Sign in on Staffing Board.
/
Track activities conducted prior to the OSC activation and report to director
/
Establish communications with Power Stores representative at Extension
- 2608.
Operational Responsibilities Provide and coordinate material support resources necessary to support the Operation Support Center.
Provide technical assistance as applicable in regards to material acquisition, substitution, and availability PAGE 26 OF 29 REVISION 20
ACTIVATION AND OPERATION
,BROWNS FERRY OF THE OPERATIONS SUPPORT rr-i f,
',NUCLEAR PLANT CENTER (OSC)
ATTACHMENT T (Page" I of 1)
OSC PLANNERS CHECKLIST NOTE: Maintain a log of activities and communications.
Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the Accountability LogSheet. -
/
Sign in on the staffing board.
Operational Responsibilities Provide support to the OSC Staff as applicable.
Support in the Planning and briefing preparation for OSC Team Complete and update "Team Tracking Forms" for teams you are assigned S PAGE 27 OF,29 REVISION 20
ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT ENPCIP-7 LEAR PLANT CENTER (OSC)
ATTACHMENT U (Page 1 of 1)
OSC DOCUMENT CONTROL NOTE: Maintain a log of activities and communications Initials/Time Initial OSC Activation
/
Swipe into Accountability Card Reader.
/
Sign the Accountability Log Sheet.
/
Sign in on the staffing board Operational Responsibilities Provide document control support for the OSC and OSC Staging Area Ensure that documents/drawings are maintained as utilized by OSC members Ensure timely availability of procedures and drawings as requested by OSC members PAGE 28 OF 29 REVISION 20 1
ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC)
EPIP-7 BROWNS FERRY NUCLEAR PLANT ATTACHMEfNT V (Page I of 1)
OSC CONFIGURATION Sign IR Board a a cn Radcon 88 LD m
E 00 r
C lerk
, r-u S -Stats Boards REVISION 20 I
(D (T-)
T)
C heristrv I
F 22 Assislant OSC OSC Dir.
Diec PAGE 29 OF 29 ATTACHMENT V (Page 1 of l)
OSC CONFIGURATION H H
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT
",EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-12 Emergency Equipment and Supplies (Inventory and Operability Procedure)
REVISION 0 PREPARED BY: T. W CORNELIUS RESPONSIBLE ORGANIZATION. EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE: 10/29/2002 PHONE: 2038 DATE. 10/18/2002 LEVEL OF USE: REFERENCE USE QUALITY-RELATED l
f
REVISION LOG PROCEDURE NUMBER PAGES AFFECTED EPIP-12 REVISION NUMBER- 0 All DESCRIPTION OF CHANGES-IC-01 Tlus revision is being conducted to renumber procedure N hich w as EPIP-1 7 to EPIP-12 for standardization issues. ReN ised records section for standardization and reinoN ed FRED Manuals from the TSC inventories
EMERGENCY EQUIPMENT AND BROWNS FERRY "SUPPLIES (In% entory and EIP-12
, NUCLEAR PLANT Operability Procedure) 3
- ___Z 1.0 PURPOSE The purpose of this procedure is to provide a listing of equipment and supplies, along with storage l6cations; available for emergency response during the activation of the Radiological Emergency Plan and Emergency Plan Implementing Procedures -This procedure will ensure the availability and readiness of emergency equipment at BFN through the performance of periodic inventories and operability checks.
2.0 SCOPE This procedure provides information pertaining to equipment and supplies available for use during emergencies at the Browns Ferry Nuclear Plant This procedure additionally provides instructions to personnel performing checks of equipment and supplies in regards to frequencies, responsibilities,-acceptance and record management.
3.0 INSTRUCTIONS
'Responsibilities and Frequency-,
3.1.1 Inventories and operability checks shall be conducted in accordance with frequencies provided in Allachmnenti
- 1. In addition with this frequency schedule, special inventories shall be required whenitems or equipment maintained by, this procedure have been affected by a drill, exercise or training,This special inventory shall be performed at a reasonable time following the activity. This special inventory may also ýbe used as the routine inventory.
3.1.2 Conduct of inventories and operability checks shall be the responsibility of the organization providedin Atachmemt 1.
3.1.3 The Manager, Emergency Preparedness (EP), is responsible for ensuring the overall state of readiness ofsupplies and equipment identified in the procedure.,
-_PAGE IOF36 REVISION 0
EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Im entor.' and EPIP-12 NUCLEAR PLANT Operability Procedure) 3.1 Responsibilities and Frequency (Continued) 3.1.4 Individuals performing work within this procedure shall be familiar with all procedural guidance and testing requirements applicable to their assigned task. By initialing the item listing on the task form, the individual performing tasks within this procedure is responsible for ensuring the item is present, in the specified quantity and functional for its intended purpose 1
3.1.5 Equipment inventories and operability of the site environmental monitoring vans shall be conducted in accordance with CECC-EPIP-9 Routine and special inventory/operability checks involving the site environmental monitoring vans are the responsibility of RADCON. Training personnel will be responsible for inventory and operability checks following training activities.
3.1.6 Personnel performing inventories and operability checks shall ensure that upon completion of task, seals or locking devices are in place to ensure the integrity of the equipment or supplies. Areas requiring these measures are listed on Attachment 2.
3.1.7 Personnel conducting inventories and operability checks in accordance with this instruction will ensure that the latest revision of this procedure is utilized.
3.1.8 Definition for annual and quarterly shall be as noted in the Radiological Emergency Plan Terms such as once every calendar quarter or month invokes that the task should be conducted within the timeframe of a physical quarter or month 3.2 Records Management 3.2.1 Personnel conducting tasks within this procedure will provide legible documentation of results on applicable forms 3.2.2 Upon completion of applicable task(s), originals with signatures, shall be forwarded to the Manager, EP for review and concurrence Originals should be forwarded as soon as possible, but no later than the end of the current quarter.
PAGE 2 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (In entory and OpcrabilitN Procedurc)
"TEPIP-12 BROWNS FERRY
-NUCLEAR PLANT 3.1 Records Management(Continued) 3.2.3 The Manager, EP shall review all task forms and concur with results by signature
.3.2.4 EP shall maintain all procedure records for a minimum retention period of 3 I
- years. These records are considered -NON-QA 3.3 Task Deficiencies Deficient items as discussed within this procedure do not relate to those described in SPP 3. 1, "Corrective Action Program"'. 'Anydeficient item identified within this procedure which does meet the requirements of SPP 3.1 shall be'documented in accordance with SPP 3 1..
"*3.3.1 All task deficiencies shall be noted on the applicable task form.
3.3.2 All task deficiencies shall be corrected as soon as possible. If circumstances do not allow prompt correction the Manager, EP, shall be
, notified.When deficiencies have been corrected, the applicable task form
- shall be signed.
"3.3.3 For failures of the, Emergency Telecommunications System (ETS)
"deficiencies will be reported immediately in accordance with the instructions provided on the applicable task form 4,J,
- 4.
44' 4
j.Z,
- 1
-"--4, 44 I
4 I 4 4
I 4,t 4
'44
-4
-4
'1 i,-: : PAGE 3 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-12 NUCLEAR PLANT Operablily Procedure) 3.4 Specific Instructions for Inventories. Operability Checks, Administrative Checks and Reviews 3.4.1 SCBA's Self Contained Breathing Apparatus (SCBA) units are inventoried per this procedure for inventory purposes only Inspections/equipment maintenance and operability checks are conducted in accordance with applicable Fire Protection Instructions.
3.4.2 Radiological Control Instrumentation 3.4.2.1 On-Site - Survey instrumentation, counting equipment, air samplers, dosimeters and other radiological control equipment listed on applicable forms are for inventory purposes only Instrument readiness is a process of the on-site radiological control organization As a function of this inventory calibration due dates and instrumentation physical appearance will be observed to help ensure operability 3.4.2.2 Off-Site - Survey instrumentation and dosimeters referenced as offsite by this procedure are considered those maintained by EP at the BFN - Agreement Hospitals. Survey instrumentation operability shall be maintained by the Western Area Radiological Laboratory, Instrumentation Section. Electronic dosimeters shall be exchanged according to response dates not to exceed calibration due dates. Electronic dosimetry should be observed for physical damage to help ensure operability.
3.4.3 Telecommunications 3.4.3.1 Nuclear Regulatory Commission - Emergency Notification System telephones Lift the receiver and listen for a dial tone; after receiving a dial tone, dial 9-1 then first number listed on the sticker located on the telephone instrument, using all 10 digits. If the first number is busy, proceed on with the second, etc Confirm acceptable voice quality between parties conducting the test with all extensions off hook. Request a call-back be made to single phone and confirm acceptable voice quality PAGE 4 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND, SUPPLIES (Imentorvand Opcrabilhty Procedure)
EPIP-12 BROWNS FERRY "NUCLEAR PLANT 3.4 Specific Instfuctions for Invenitories. Operability Checks.,Administrative Checks and Reviews (Continued).-:
3.4.3 Telecommunications (Continued) 3.4.3.2 -All'other telecommunications tested by this procedure. Conduct the test by lifting'receiver and listen for a dial tone; after receiving a dial tone, place a local call and request a call-back be made Confirm acceptable voice quality between telephones being tested.
3.4.4 TSC & OSC Intercom System Activate the intercom system in the TSCor OSC. Assign someone to monitor the test in the applicable locations The TSC PA services the TSC, OSC and the Technical Assessment Team Area while the OSC PA services the OSC and OSC Staging Area t 3.4.5 EP Clocks Verify the correct operation of the TSC and the OSC clock by logging onto the clock program and making classification changes using the program. Return the system to the "No Classification" display 3.4.6 Telecopiers (TSC & OSC)
Verify operability by'faxing a test message to another telecopier. Fax a test message back to the telecopier being tested. Check telecopier paper and physical condition -Ensure legibility of test messages:
3.4.7 -Telephone Headsets Configure headset as applicable Make call and confirm acceptable voice quality using the microphone and ear piece.
.3.4.8 Ring down Phones (CECC/TSC, TAT/Plt Assessment; ODS/Control Rooms 1/2 & 3)
Contact Corporate EP,-,have someone man the telephone in the:
CECC/ODS areas. Place a call to the CECC/ODS by lifting the receiver and receive a call form the CECC/ODS.
,,PAGE 5 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (In% entorv and EPIP-12 NUCLEARPLANT Opcrabilitv Proccdure) 3.4 Specific Instructions for Inventories, Operability Checks, Administrative Checks and Reviews (Continned) 3.4.9 Meteorological (MET) Data Terminal and Printer Log onto the MET terminal. Request information in printed format Verify that the printer has a supply of paper and that the print is legible Log off system.
3.4.10 OSC Computer & Printer (OSC)
Ensure the operability of the OSC computer by performing a task such as the activation of the word processing program. Check the response of the printer by requesting a print task via the computer, observe the action of the printer and print quality 3.4.11 Copiers (TSC/OSC)
Verify operability by copying a test message through the copier. Make copies using the sorter and verify legibility of copies, check copy paper supply and physical condition of copier.
3.4.12 Batteries All batteries shall be observed for physical damage such as indentations, leaking or rust Batteries shall be tested to determine effectiveness by battery tester Batteries sealed by the manufacture with an affixed label indicating a "shelf life" can be exempted from the individual battery test and accepted as is, as long as the current date does not exceed the "shelf life" date. Sealed batteries which have a "shelf life" date that is exceeded by the current date can be utilized, but must pass a battery test utilizing the battery testor.
3.4.13 Zetron Radio Control Units (RCU)
Observe the unit to ensure that the time is displayed on the face plate.
Verify that a green indicator light appears by one of the radio frequency selector buttons The RCU should be tested by contacting a normally manned station PAGE 6 OF 36 I
REVISION 0
EMERGENCY EQUIPMENT AND T-BROWNS FERRY SUPPLIES (Inventory and EI iir_-,
- L.NUCLEAR PLANT Operability Procedure) 3.4 -Specific Instructions for Inventories. Operabilitv Checks. Administrative Checks and Reviews (Continued) 3.4.14 Hand Held 2-Way Radios ;-
Observe the unit fcr physical damage, then assemble one of the battery packs to the radio.Make radio contact with another hand held unit and "verify acceptable voice qtfalit,.
3.4.15 Control Room Conference Bridge (101/102)
Activate the "2-Way", bridge by dialing 101 on two plant telephones.
Verify acceptable voice quality. Then test the "Listen Only" bridge by having someone activate the "2-Way" bridge by dialing 101 and someone activate the"Listen Only" bridge by dialing 102. Verify that the 102 is a "listen Only" system
-3.4.16-ERO Logbooks Utilize EPIP-6 or 7,,positi6n attachments to identify what ERO logbooks are intended for use in the applicable centers Review the logbooks to unsure that each contains:
(1)The latest revision ofthe applicable EPIP Attachment (2)An adequate supply of log sheets 3.4.17 Calculators, Flashlights, etc.
Verify functional by observing anticipated response.
- 3.4.18 Emergency Procedure Telephone Number-Review and Update "Certain EP1P'sand site procedures contain tel ephone numbers utilized by response personnel. i Once per calendar quarter these numbers will be reviewed to ensure accuracy and updates are made as applicable.
Changes will be conducted in accordance with site instructions I,
-IPAGE 7 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND--
IP-"
1 BROWNS FERRY SUPPLIES (Invcnlory and nrIr-I L NUCLEAR PLANT Opcrabilhty Procedure) 3.4 Specific Instructions for Inventories, Operability Checks. Administrative Checks and Reviews (Continued) 3.4.19 Review of Emergency Procedures In accordance with the Radiological Emergency Plan (REP) the REP, REP Appendices and the EPIPs shall be reviewed annually. Changes concerning the REP will be forwarded to the corporate EP staff for consideration and implementation as applicable Changes noted concerning the EPIPs shall be considered and if applicable revisions conducted in accordance with site instructions.
3.4.20 Emergency Response List The Emergency Response List contains individuals which are allowed access to the protected area during an emergency at BFNP for the purposes of serving within the emergency response organization. This listing is updated quarterly and copies distributed to Nuclear Security.
The list will be issued on white paper and will not require PORC review 3.4.21 Call-Out List This list contains active Emergency Responders by emergency positions This list is utilized as a tool for the call-out of emergency responders The list is updated quarterly and will be issued on white paper The call out list will not be PORC reviewed.
3.4.22 Procedures and/or Drawings Controlled Procedures and/or drawings listed on applicable forms are for inventory purpose only. Procedure and Drawing inspection/maintenance process is conducted through applicable site instructions PAGE 8 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (Inventory and Operability Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT 4.0 ATTACHMENTS 4.1 4:2 4.3J 4.4 4:5 4:6 4.7 4.8 4.9.
4.10 4.11 A4.12 4.13
":4.14 4.15 Attachment I kttachment -3 Attachment. 4 kttachment 8 Akttachment 9 0 1 2 3 4 5
.4.16 Attachment 16 4:17 Attachment 17
'4.1 Attachment 18 Inventory Matrix Table Locked/Sealed Cýabinet Listing Radcon Emergency Equipment - Service Building 565' Radcon Emergency Equipment - Control Building 617" Staging Area C-Zone Dress-Out Clothing - Service Building
.565' Emergency Use SCBA Inventory Maintenance Emergency Tool Box Inventory, Clean Tool
-Room - Service*Building 565' Technical Support Center Inventory/Operability Check Operations Support Center Inventory/Operability Check OSC Staging Area Inventory/Operability Check Huntsville/Decatur General Hospital Inventory/Operability Checks ETS Communications Operability Checks Local Recovery Center Inventory/Operability Checks EP Quarterly Administrative Checks and Reviews EP Once per Calendar Quarter Administrative Checks and Reviews EP Annual Administrative Checks and Reviews Alternate Decontamination Facility Personnel Decontamination Treatment Area
\\
.9 PAGE 9 OF 36 t
REVISION 0
ErvMRGENCY EQUIPMENT AND SUPPLIES (InA entory and OperabilitN Procedurc)
)
EPIP-12 BROWNS Fity{Y NUCLEAR PLANT Attachment I Inventory Matrix Table Description EPIP Ittachment Number 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 Reylponivle Section Radcon Radcon Radcon Operations Maintenianlce I'P Ell FPP ET~
1,;I)
EPl EP Radcon
- lreqnenc, Once ever-calendar quarter Once c% en calendar quarter Once even Lalendar quarter Once ever, calendar quarter Once evern calendar quarter Once even, calendar quarter Once even, calendar quarter Once evel' calendar quarter Once everv calendar quarter Once monthlv Once evern calendar quarter Once quarterly Once even calendar quarter Once anmially Once even, calendar quarter Once even' calendar quarter
- 1. ____________________________________________
J ___________
I. _________________________
L ___________
PAGE 10 OF 36 REVISION 0 Radcon imEnteren, Equipment - Semvice Bn Ihdng 565' Radon Eniergenciy Equipment - Control BIthldig 617' Staging. Irea C-Zone Diev'-Out Clothiig Service Building 565' Etmeigentci, Me SCBA I nventoit, A lamtinenance En'ergenicy Tool Boy Inventory, Clean Tool Rooni Service Buildng Tecltiical Suppott Center hnventory Operabilitty Check Operatiot Support Center Inventony Operabiliti' Check OSC Staging. Irea hIventoy Operabilitt Check Iltuitsville Decatur General IIovpttal inveittory Operabilit, ChecAe ENS.
lonthh, Commititicattoni Opetablith, ChecA Local Recovery, Center InventoryrOpet-abilit, Check EP Qutai terlv,. Idmnint atitve Clieckv amid Revteir El oitce per Calendar Ottarter. Idninnstrative C(heck V anld lewteii, EP. Inmnal. 1mdiniwtrative Checl ¶ andl Revtu'u'
. Ilteniate Decontanunatton Facilt, PerIoinel Decontanination 7 ratmeit. Irea Stiecific Iii trngctuion Provided Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes PAGE 10 OF 36 REVISION 0
EMERGENCY EQUIPMENT AN 1'
BROWNS FERRY SUPPLIES (Inventory and EPIP-12 NUCLEAR PLANT Operability Procedure)
I Locked/Sealed Cabinet Listing "Cabinet Location Equipment and Supplies Cabinet Technical Support Center, Equipment and Supplies Cabinet Operations Support Center,,
Equipment and Supplies Cabinet OSC Staging Area Equipment and Supplies Cabinet Local Recovery Center Equipment and Supplies Cabinet Service Building 565',
(Radcon)
Equipment and Supplies Cabinet Control Building 617' (Radcon)
Equipment and Supplies Cabinet Decatur General "Emergency Room" (Hospital)
Equipment and Supplies Cabinet Huntsville Hospital "Emergency Room" (Hospital)
Equipment and Supplies Cabinet PowerService Shop # 4 (Alternate Decontamination Facility)
TVA Muscle Shoals Reservation
-PAGE11OF36 REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (Inventory and Operability Proccdure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT Radconi Einergency Equipment - Service Building 565' Location: Service Building 565' Behind Radiological Control Lab Equip ni en t QTY INV OPER INIT Equipment Radiolo~ical Survey Instrumentation QTY 2
4 2
1 10 8
1 2
1 I
16 8
1 2
1 2000
.1. ______
L High Range Survey Meters Ion Chambers GM Survey Meters (Friskers)
Neutron Survey Meter Silver Zeolite Cartridges' Alpha Survey Meter Mini-Scaler Hi-Volume Air Sampler Low-Volume :Air Sampler Shielded Detector "Pig" (Located m Radcon Area, Service Building, 565)'
Miscellaneous Calculator (Hand Held)
Batteries (D-Cell)
Log Book Flashlights Box of Pens Particulate Air Filters (Box)
Disc Smears (Box)
KI Tablets Expiration Date (Radcon Sup)ply Cage)( Tableis)
Si21 natures:
Supervisor, Radcon:
Manager, EP:
Rctcntion Period is 36 months - - Non-QA Record Date:
Date:
PAGE 12 OF 36 Y
Y N
N Y
N INIT 1_ý INV OPER INIT REVISION 0
EMERGENCY EQUIPMENT AND SSUPPLIES (Inaentory and Operability Procedure)
-BROWNS FERRY
-~
EPI-12'-NUJCLEAR PLANT S- 'Attachment 4
,, Radcon Emergency Equipment - Control Building 617' Location: Control Btildig, 617'Mechanical Equipmeltl Roomi
...,Eq uip ment Radiological Survey Instrumentation High Range Survey Meters Ion Chambers GM Survey Meters (Friskers)
Neutron Survey Meter Silver Zeolite Cartridges Alpha Survey Meter Mini-Scaler Hi-Volume Air Sampler Low-Volume Air Sampler Shielded Detector 'Pig' Miscellaneous Calculator (Hand Held)
Batteries (D-Cell)
Log Book Flashlights Box of Pens Particulate Air Filters (Box)
Disc Smears (Box),
'S 4.
Y r
INIT OPER
-,QTY 2
4 2
'2:1 1
2 1
1 1
16 1
8 1
2 I
5-"
S -
,Y N
Y N
':'
'i S
1'
INV Signatures:.
Supervisor, Radcon:
Manager, EP:.....
Retention Period is 36 -nontls - - Non-QA R, Date:
'4
-Date-
ecordI
-PAGE 13 OF 36 REVISION 0 I
ecord L
EMERGENCY EQUIPMENT AND SUPPLIES (In entory and OperabilWv Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT Staging Area C-Zone Dress-Out Clothing - Service Building 565' Location: Service Building Cohlmuu 6, G-hne Hal/way behind Mecthanical Mainteniance Offices Si2natures:
Supervisor, Radcon:
Manager, EP:
Retention Period is 36 months - - Non-QA Record Date:
Date:
PAGE 14 OF 36 Equipment QTY INV INIT Coveralls (Pairs) 40 Based upon size availability an alternate distribution may be acceptable at the discretion of the Radcon Supervisor and the EP Manager, noted by signature of completed form Size 46 Size 48 10 Size 50 10 Size 52 5
Size 54 5
Size 58 5
5 Hood covers 25 Shoe Covers (Pairs) 25 Surgeon Caps 25 Rubber Gloves (Pairs) 25 Booties (Pairs) 25 Cotton Glove Inserts (Pairs) 25 Masking Tape (Rolls) 8
.1.
J REVISION 0
EMERGENCY EQUIPMENT AND, T
1 SUPPLIES (Inventory and
_ EPIP-12 Operabihit% Procedure)
BROWNS FERRY NUCLEAR PLANT Emergency Use SCBA-Inventory Description Self Contained Breathing Apparatus Self Contained Breathing Apparatus Self Contained Breathing Apparatus 45 cu ft. Air Cylinder Self Contained Breathing Apparatus and 10 additional cylinders Self Contained Breathing Apparatus Self Contained Breathing Apparatus SelfConBtained-Breathing Apparatus Self Contained Breathing Apparatus Self Contained Breathing Apparatus Self Contained Breathing Apparatus
(*) Required for by 10 CFR 50 Appendix R Support Signatures:
Supervisor, FIRIEPROTECTION:
Date:
Manager, EP:
Date:
Retention Period is 36 months - - Non-QA Record
--,,
- PAGE 15 OF 36 INV INIT
- ,- -* :
- Attachment 6 SEmergency Use SCBA-Inventory REVISION 0 i
Location Unit I Control Room Unit 2 Control Room Unit 3 Control Room Service Building
- Elevation 565, Service Shop Hallway Fire Equipment Cabinet-,
Turbine Building - 557
4kV Shutdown Bd Rm 'C" 3A Electrical Board Room Fire Eiquipmieint Cabinet.
Stairwell - RB 1&2 El 565' Fire Equipment Cabinet Stairwell - RB 2&3 El. 565' Radcon Emergency Cart Fire Truck QTY 5
5
,15
'10" 25 4
2 4
EMERGENCY EQUIPMENT AND SUPPLIES (InN entory and Operability Proccdure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT (Page 1 of 4)
Maintenance Emergency Tool Box Inventory Electrical Tool Box Number of Boxes 2 -- Number of Boxes Inventoried Tool Description QTY INV INIT Pliers, Needle Nose, 6" 21 Pliers Diagonal, 6" 2
Tester, Circuit, 24.0" 21 Rule, Folding, Carpenters, Outside Reading, 6' 2
Pliers, Tongue & Groove, 10", #430 Channel Locks 21 Screwdriver, STD Tip,.25" Tip, X 8.0" Long 21 Screwdriver, STD Tip,.3 13" Tip, X 4 0" Long 2
Screwdriver, STD Tip,.125" Tip, X 6 0" Long 2
Pliers, Lineman's, 9.0" 2
Screwdriver, STD Tip, 25" Tip, X 6.0" Long 21 Screwdriver, Phillips Tip, #2 Tip, 4" Blade 2
Screwdriver, Holding, 25" X 6" (Klein) 21 Wrench, Adjustable, 10.0" 2
PAGE 16 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND V
SUPPLIES (Inventor" and Operability Procedure)
"" ;EPIP-12 SBROWNS FERRY
- -NUCLEAR PLANT (Page 2 of 4)
Maintenahice Emergency Tool Box Inventory I&C Tool Box Number of Boxes 2 -- Number of Boxes Inventoried 7
- 7.
Tool Description Pliers, Tongue & Groove, 9, #42 Channel Locks Screwdriver, STD Tip,.25" Tip, X 6.0" Long ScreN*driver. Je* elers. Set of Six,.25"-.100" Mfg Starrett Screwdriver, Holding,.25" X 6" (Klein)
Cord, Extension, 110 V 100' Wrench Set, Hex Key (Allen), Folding, 0.050"-0. 187" Wrench, Ignition, Set Wrench, Valve Wheel, Number 0, 8.0"X.50"X.656" Socket, Set, 1/4" DR., SL/DW, 3/16" to 9/16" Driver, Nut, Set, Fractional 1/4" to 1/2" Wrench, Set, Hexkey, 028" to 5/8" Cutter, Tube,'.125", to.625" Cutter, Tube,.125" to 1.125" Pliers, Diagonals, 6" Pliers, Lineman, 7" Pliers, Needle Nose, 7" Pliers, Tounge & Groove, #430 CL.
File, Half Round, 4" Smooth File, Round, 6" Smooth Puller, Fuse, Midget Puller, F-use, 100A-250V.
Screwdriver, Philips, #1x3" Screwdriver, Phillips, #2x4" Screwdriver, Flat, _1/8x2.25" Screwdriver, Flat,, 1/4x6" Screwdriver, Flat, 1/4x4'!
Screwdriver, Flat, 5/16x6" Screwvdriver, hodldinig, SM/p6etCli-.
Screwdriver, Holding, 3/16x6" Screwdriver, holding, 1/4x8" Wrench, Adjustable, 4" Wrench, Adjustable, 6" Wrench, Adjustable, 8" l J-QTY A.
A 2,PAGE 17OF36 INV 1
I 1
I I
- 1 1
1
.- ";
- 1
-1 2
1 I
I I
1:
--
Ii 17*
1 1
1
- 1 I
.
1 7
- I I
I I
I I
1 A
I
,INIT REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (InN entorv and Operability Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT (Page 3 of 4) (Page 3 of 4)
Maintenance Emergency Tool Box Inventory I&C Tool Box (CONTINUED)
PAGE 18 OF 36 Tool Description QTY INV INIT Wrench, Combo, 3/8" 1
Wrench, Combo, 7/16" 1
Wrench, Combo 1/2" 1
Wrench, Combo, 9/16" 1
Wrench, Combo,5/8" 1
Wrench, Combo, 11/16" 1
Wrench, Combo, 3/4" 1
Wrench, Flare Nut, 1/2"-9/16" 1
Wrench, Flare Nut, 5/8"-11/16" 1
Wrench, Flare Nut, 3/4"-1" 1
Wrench, Flare Nut, 7/8"-1 1/8" 1
Snoop, Bottle, 8 oz I
Note. The following items are supplied by the I&C Shop Tube Fitting, 1/4"M NPT to 3/8" tube comp 2
Tube Fitting, 1/4"F NPT to 1/4" tube comp 2
Tube Fitting, 3/8" comp to 3/8" comp 2
Tube Fitting, 1/4" comp to 1/4" comp 2
Tube Fitting, Tee, 1/4" comp 2
Tape, Electrical, Scotch 33 Black I
Leads, Test, 4' 1
Jumpers, Banana, 2' orange w/clips 2
Tywraps, 3/1 6"x8" 1PK Tywraps, 1/8"x4" IPK Valve Wrench, Custom Made, I&C Specs.
1 REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (InNentory and Operability Procedure)
--EPIP-12
,'BROWNS FERRY
,NUCLEAR PLANT (Page 4 of 4)
=.Maintenance Emergency Tool Box1nventory Mechanical Tool Box Number of Boxes 2 -- Number of Boxes inventoried ___
Tool Description Flux, Soldering Chisel, Cold,.4375"-Cut Wrench Set, Com b o, 0.250"-1.250" Wrench Set, Hex Key (Allen), 0 187"-0 375" Wrench Set, Hex Key (Allen), Folding, 0.050"-0:187" Socket Set,.375" Hammer, Ball Pein, 12 oz Punch, Pin,.188" Punch, Pin,.125" Pliers, Tongue & Groove, 9".#420 'Channel Locks Screwdriver, Phillips Tip, Round Shank, #2 Tip X 4 0" Blade Screwdriver, Phillips Tip, Round Shank, #2 Tip X 1.50" Blade 44 Screwdriver, STD Tip,.25" Tip X 6.0" Long Screwdriver, STD Tip,.25" -Tip X 12 0" Long Wrench,,Pile, 12" Wrench, Adjustable, 12.0" Pliers, Slip Joint, 10" Pliers, Needle Nose, W/Side Cutter, 8" INV4
-4
44 44 I
I INIT QTY 41 1,
1 1
.41 1~
41
. Signatures:-'-
"Supervisor, Tool Room:
'Date:______,______
Manager, EP:
Date:
Retention Period is 36 months - - Non-QA Record Date:_
PAGE 19 OF 36 I I REVISION 0
EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (InA entorv and EPIP-12 NUCLEAR PLANT Operability Procedure) (Page 1 of 4)
Technical Support Center Inventory/Operability Check Equipment QTY INV OPER INIT In the Technical Support Center Telecopier 2
Y N
Telecopier (TAT Area) 1 Y
N TSC Intercom System 1
Y N
TSC Zetron Radio System I
Y N
Copier I
Y N
EP Clock I
Y N
Control Room Conference Bridge Headset 2
Y N
Met Data Terminal & Printer I
Y N
ERO Logbooks Accountability Roster I
N ICS Terminal (TAT Area) 1 Y
N In TSC Equipment & Supply Cabinet Calculators, (,Scientific) 6 Y
N Flashlights 12 Y
N Batteries (D-Cells) 24 Y
N Batteries (AA) 24 Y
N Telephone Headsets (Spares) 3 Y
N Staplers I
Pens (Black Ink) 24 Pencils 12 Tape Dispensers w/tape 1
"Post-it-notes" Pads 12 Message Pads 12 Note Pads (8.5"x 11")
12 Board Cleaner (Bottles) 1 Paper Towels (Rolls) 1 Grease Pencils 12 Dry Erase Markers 12 Copier Paper (Packs) 4 Spare Phones for NRC ETS 6
PAGE 20 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND T
TBROWNS FERRY SUPPLIES (Inventon and
-ri z:NUCLEAR PLANT Operability Procedure) (Page 2 of 4)
Technical Support Center Inventory/Operability Check I
Procedures/Drawings QTY J,,NV2' OPER 1INIT In the Technical Support Center,
- REP 4
- BFN EPIP's 11
- CECC EPIP's 2
- Severe Accident Management Guidelines Flowcharts 1 1 Set
- Technical Support Guidelines 1 Set
- Emergency Operating Instruction (EOI)
Flowcharts It 1 Set____
- EOI Program Manual 1 Set
- Radiological Control Instructions 1 Set
- Abnormal Operating Instructions 1 Set
- REND 2
- AI Radiological Emergency Response Plan 1
- Multi-Jurisdictional Radiological Emergency, Response Plan TEMA, 1
-I i
- Alarm Response Procedures I Set
- Operating Instructions 1 Set
- Technical Specifications 1 Set
- Technical Requirements 1 Set
- Safe Shutdown Instructions 1 Set
- Fire Protection Report 1 Set
- Final Safety Analysis Report I Set
- User Manual Meteorological Data Display Program CECC I
- User Manual Nuclear Power (NP) Sites Emergency Paging System (EPC) CECC 1
- User Manual Meteorological Data Print Program 1
- Plant Drawings 1 Set Radcon Survey Maps 1 Set EP 10-Mile Sample Point Map 2
EP 2-Mile Sample Point Map I
EP 50 Mile Sample Point Map I 1 EP 10 Mile Evacuation Sector Map I
Operators Manual Zetron Radio Console 1
- Controlled Documents or Drawings
-,,.c.PAGE 21 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (Inentory and Operability Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT (Page 3 of 4)
Technical Support Center Inventory/Operability Check PAGE 22 OF 36 Procedures/Drfiwings QTY INV OPER INIT In the Technical Assessment Team Area
- REP 1
- BFN EPIP's 2
- REND I
- Operating Instructions 1 Set
- Technical Specifications 1 Set
- Technical Requirements I Set
- UNMMI I Set
- UEM I I Set
- EI~lI 1 Set
- Unit 2 EOI Appendices 1
- Unit 3 EOI Appendices
- SAMG EOI Appendices I
- SPCC Plan l
- Plant Drawings 1 Set L
I I.
REVISION 0
"EMERGENCY EQUIPMENT AND:
"-PI 12 SUPPLIES (Inventory and
-LPIJ-1 2
Operability Procedure)
BROWNS FERRY NUCLEAR PLANT Attachment'8 (Page 4 of 4)
'Technical Support'CenterInventoiy/Operability Check Technical Support Center Telephones Telephone Number 3777 3730
.'3771
-'3770
ý "3732
-3764
- -3761
- *3765 3767 3766 "3768
.3763 3779 3782 (Node2) 3784 (Node2)
TSC FixeId Satellite Operable Y
V Y
Y Y
Y y
Y Y
Y Y%
Y Y
N N
N N
N N
N N
N N
N N
N N
N N
TT Initials TelephoneNNumber "2305-:
3734 3733 3736 ::"-
3735 3744 3756 3745-:,
3738-,,
3740.70 3762 w/Headset,;
3769 W/Headset 3737 w/Headset
-CECC Ringdown 101/102 Bridge 103 Radcon Bridge Operable Y
N
- .17 N
"--Y-- N' Y j-N
-N, YN Y
N
,all N
Y N
-,Y N,
Initials Technical Assessment Team Area Telephone Number; Operable Initials Telephone Number.
Operable Initials 3741 Y
N 3025
.Y N 2165 Y
N 2202 7 -N 2274 Y
N Pit Assessment Ringdovn.
N Control Rooms Telephone NuinberW Operable Initials Telephone Nunmber Opera'ble initials
!ODS Unit 1/2 Ringdin
.Y N ODS Unit 3 Ringdois*n Y-N' Unit 1/2 Bridge Headset Y
N Unit 3 Bridge Headset'f
--Y-N '
Unit 1/2 Fixed Satellite, Unit 3 Fixed Satellite i
Telephone Y
N Telephoi".
- I
_Y
'. N i N I
, Manager,EP:
Retention Period is 36 months - - Non-QA Rec D a t e : '.
cord I
.,'F.
--PAGE 23 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND /BROWNS FERRY SUPPLIES (In, entorv and EPIP-12 NUCLEAR PLANT Opcrability Procedurc) (Page lof 2)
Operations Support Center Inventory/Operability Check Equipment QTY INV OPER INIT In the Operational Support Center Telecopier 1
Y N
OSC Intercom System 1
Y N
Copier 1
Y N
EP Clock 1
Y N
Computer Terminal 1
Y N
Printer for Computer I
Y N
Accountability Roster I
OSC Zetron Radio System I
Y N
RADCON Zetron Radio System 1
Y N
ICS Terminals 2
Y N
In OSC Equipment & Supply Cabinet Calculators, (Scientific) 6 Y
N Flashlights 12 Y
N Batteries (D-Cells) 24 Y
N Batteries (AA) 24 Y
N Telephone Headsets (Spares) 2 Y
N Staplers 3
Pens (Black Ink) 24 Pencils 12 Tape Dispensers w/tape I
"Post-it-notes" Pads, 12 Message Pads 12 Note Pads (8.5"x 1l")
12 Board Cleaner (Bottles)
I Paper Towels (Rollsi" I
Grease Pencils 12 Dry Erase Markers 12 Copier Paper (Packs) 4 Hand Held 2-Way Radios 10 ERO Logbooks
- Utilize EPIP-7, position attachments to identify what ERO logbooks are intended for use in the OSC PAGE 24 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND r'TbTPI 1
)
SUPPLIES (Inventor. and Lrlr Operability Procedure)
BROWNS FERRY NUCLEAR PLANT (Page 2of 2)
Operations Stipport Center-Invefitory/Operability Check Operations Support Ceniter Telephones S
'fri.,
-,.PAGE25OF'36 I,,,-
Manager, EP:
'-Date:
Retention-P6-riod is 36 mionths - -Non-QA Record --
I REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (In* entory and Operability Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT 0 OSC Staginig Area Inventory/Operability Check Operations Support Center Sta~in2 Area Telephones Telephone Number Operable Initials Telephone Number Operable Initials 2244 Y
N 2115 Y
N 2309 Y
N 2215 Y
N 2303 Y
N
- Utilize EPIP-7, position attachments to identify what ERO logbooks are intended for use in the OSC Staging Area.
Manager, EP:
Retention Period is 36 months - - Non-QA Record Date:
PAGE 26 OF 36 Equipment QTY INV OPER INIT In the OSC Sta2in2 Area Equipment & Supply Cabinet Calculators, (Scientific) 1 V
N Flashlights 12 Y
N Batteries (D-Cells) 24 Y
N Staplers I
Pens (Black Ink) 24 Pencils 12 Tape Dispensers 1
"Post-it-notes" Pads 12 Message Pads 12 Note Pads (8.5"x I1")
12 Accountability Roster I
ERO Logbooks In the OSC Staging Area Ice Vests 12 Ice Packs for vests 72 L _______
I _______
I _______
L y
11I REVISION 0
EMERGENCY EQUIPMENT AND T
1 SUPPLIES (In entorv and rEPIP-12 Operability Procedure)
"BROWNS FERRY NUCLEAR PLANT
,,Attachment 11(Page 1 of 2)-",-;
t,.
Huntsville/DecaturGeneral Hospital Inventory/Operability Check (Circle One)
Hospital Equipment & Supply Cabinet Personnel Dress-Out Clothing "Booties" (Pairs)
Dress Out Packages Surgical Gloves (Pairs)
Surgical Gowns Surgical tape for dressout (Rolls)
Rad Monitoring Instruments ) Dosinietry Bicron Surv eyor 50 (GM) or equivalent Bicron RSO 5(lon Chamber) or equivalent TLD's Electronic Dosimeters Wound Probe w/Cable Zone, Survey & Contamination Control Supplies Floor Covering (Set)
Duct Tape (Rolls)
Rad Posting Signs Contamination Smears Step-Off-Pads Rad Ribbon or rope (Rolls)
Massilin Mop Massilin Cloths Rad Emblem Tape (Rolls)
Flexible-Funnel-w/ ldrain hose Fluid Collection B3ottle (2 Gilloihtin.)
"3ft. Wide Paper (Feet)
Cotton Swabs Radioactive Material Tags Traffic Cones (set)
QTY' _,INV-T 10 10 50 3
4 20 10 10 1
1 2
8 100 2
1 1
20 1
1 S20 12 12 1
V I
1 I
OPER
,Y -N Y --N -
--PAGE 27 OF 36 1
REVISION 0 INIT
EMERGENCY EQUIPMENT AND SUPPLIES (Ira entorn and Opeabihlty Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT 1 (Page 2 of 2)
Huntsville/Decatur General Hospital Inventory/Operability Check
~'_
Manager, EP:
Rctention Period is 36 months - - Non-QA Record Date:
PAGE 28 OF 36 Zone, Survey & Contamination Control QTY INV OPER INIT Supplies (Continued)
Scissors 1
Plastic Bags (Large) 10 Plastic Bags (Aleditna) 10 "Zip Lock" Plastic Bags 24 Skin Deconr Media (Container) 1 Sample Bag Labels 12 Hospital Response Booklet (Hospital Specific) 1 Wall Poster ("Care of,Contamnination Patients")
1 1
NCRP Report f 65 (Issued Date - April 15, 1980)
- 1.
Decontamination Table, bottle and Backboard I
L J _______
L I
REVISION 0
C EMERGENCY EQUIPMENT AND SUPPLIES (Inventory and Operability Procedure)
"TPIP-- 12-*
BROWNS FERRY NUCLEAR PLANT 2 ETS Co niimunications Operabilit Check Description Location Telephone Number OPER INIT Reactor Safety Counterpart Link (RSCL)
TSC (NVRC Area)
(256) 729-3757 Y
N Protective Measures Countcrpart Link (IA fCL)
TSC (I.
Area)
(256) 729-3758 Y
N Management Counterpart Link (.1CL)
TSC (NRCArea)
(256) 729-3759 Y
N Local Area Net,, ork (LAN) Access "TSC (NRfiC.rea)
(2"56)'729-3760 Y
N (Check this line by use of a telephone instrumtent)
Health Physics Netnork (111W)
TSC (NRC Area)
(256) 729-2212 Y
N
-lealth PhN sics Net ork (IIPYr)
TSC (77:4 Irea)
(256) 729-22h2 Y
N
- Emergency Notification Sisteni (ENS)
TSC (NIRC.lrea)
(256) 729-2273 Y
N
- Emergency Notification System tEN, q)
TSC (T I. I rea)
(256) 729-2273 Y
N
- Emergency Notification S.Jstem (EN,
[Unit 1/2 Control Room (256) 729-2273 YV N
- Emergency Notification System (ENS)
Unit 3 Control (256) 729-2273 Y
N
- Notify. the Shift Manager prior to beginning the ENS telephone checks.
Note: IMMEDIATELY, Report Failures to (1) the Shift Manager, and (2) the NRCOC at 9-1-301-951-0550 from a TVA'tclephone. (The NRC mnay request that Browns Ferry conduct repairs.)
Note: Upon Completion of repairs, perform a test of the affeCtcd tedlephones.' If test is satisfactory, inform the Shift Managetrind the NRCOC.
Manager, EP:
Dhte:.
Retention Period is 36 months - - Non-QA Record PAGE29 O 36 EVISON I
C PAGE 29 OF 36 i
REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (Inventory and Operability Procedurc)
EPIP-12 BROWNS FERRY NUCLEAR PLANT 3 (Page 1 of 2)
Local Recovery Center Inventory/Operability Check PAGE 30 OF 36 Equipment QTY INV OPER INIT In tile LRC Area Met Data Terminal 1
Y N
Printer for Met Data Terminal 1
Y N
ICS Terminal I
Y N
In LRC Equipment & Supply Cabinet Calculators, (Scientific) 4 Y
N Flashlights 12 Y
N Batteries (D-Cells) 24 Y
N Staplers 1
Pens (Black Ink) 24 Pencils 12 Tape Dispensers 1
" Post-it-notes" Pads 12 Message Pads 12 Note Pads (8.5"x 11")
12 Board Cleanir (Bottles) 2 Paper Towels (Rolls) 1 Dry Erase Markers 12 I1 I__
I I
REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (InN entorv and Operability Procedure)
-EPIP-12 BROWNS FERRY NUCLEAR PLANT
'Attachment 13 (Page 2 of 2)
Local Recovery Center:Inventory/Operability Check Telephone Number Operable Initials Telephone Number Operable Initials 2038 Y
N 2692 N
_N, 3666 Y.
N 2460.:
'.Y-N 3636 Y
N' 2064" Y - N 3656 Y
N 3647 Y
N 3645 Y
N,
Portable Satellite Telephone Y
N Manager, EP:
Retention Period is 36 months - - Non-QA Record Date:________
I j I
-PAGE 31 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (Ins entory and Opcrability Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT 4 EP Quarterly Administrative Checks Manager, EP:
Retention Period is 36 months - - Non-QA Record and Reviews Date:
PAGE 32 OF 36 QTY INV DATE INIT Emergency Response List Update
- Nuclear Security :
5 Shift Supervisor's Office (5-Copies)
Call-Out List
- Shift Manager J
L L
REVISION 0 I
--.._j 11
"EMERGENCY EQUIPMENT AND, "SUPPLIES (Inventon and OperabilitN Procedure)
<!EPIP-12
'BROWNS FERRY NUCLEAR PLANT i.. -- 'Attachment 15 EP Once per.Calendar Quarter Administrative Checks and Reviews
, 1PAGE 33 OF 36 SQ TY INV D A TE IN IT Emergency Procedure Telephone Number Review and Update
.3BFNP-Emergency2Pbeparedness
,ALL Implementing Procedures H,$
M anager, EP:
Date: __ ____ _ _,
Retention Period is 36 months - - Non-QA Record i
?
REVISION 0
EMERGENCY EQUIPMENT AND SUPPLIES (InN entory and Operability Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT 6 EP Annual Administrative Checks and Reviews QTY INV DATE INIT Review Emergency Procedures
"* Radiological Emergency Plan NA
"* Browns Ferry, Emergency Plan NA Implementing Procedures Manager, EP:
Retention Period is 36 months - - Non-QA Record Date:
PAGE 34 OF 36 REVISION 0
EMERGENCY EQUIPMENT AND "SUPPLIES (Ira entory and Operability Procedure)
TEPIP-12 BROWNS FERRY NUCLEAR PLANT 7 S-
-Alternate Decontamination Facility Power Service Shop N 4 - TVA, Muscle Shoals Reservation INIT QTY Equipment Supply Cabine Cotton Tipped SwabIs Square Gauze Detergent Surgical Brush Waterless Hand Cleaner' Shampoo Paper Bath Towels Small Coveralls Medium Coveralls Large Coveralls _
Small Tennis Shoes Large Tennis Shoes 4
2 PKG 1 Box 1 Box 12 2 Cans 2 BTL 100 12 12, 12 12 12 A'
44444, 4444' 4
4!
I 4
4 4
Si2natures:
Inventoried/Inspected by_
Manager, EP:
Retention Period is 36 montlis - - Non-QA Record Date:
--Date:_
- 4.
.4
4 4
444
.4 4
4 (4 444 14 PAGE 35 OF 36 REVISION 0 IN V t
1 l
EMERGENCY EQUIPMENT AND SUPPLIES (Inmentorn and Operabilty Procedure)
EPIP-12 BROWNS FERRY NUCLEAR PLANT 8 Personnel Decontamination Treatment Area Si2natures:
Supervisor, Radcon:
Manager, EP:
Retention Period is '36 -months - - Non-QA Record Date:
Date:
LAST PAGE PAGE 36 OF 36 Equipment/Supplies QTY INV INIT Disposable Gloves 2 Box Gauze Pads 2 Box Cotton Swabs I PKG Saline Solution 2 Bottle Surgical Brushes 12 Each Shampoo 2 BTL Soap 5 Bars Laundry Detergent 1 Box Soap (liquid abrasive) 1 Bottle Mechanic's Hland Cleaner 2Cans Shaving Cream 1 Can Razors 5 Each Paper Bath Towels 1 Box Towels 25 Each Scissors 1 Pair Petri Dish 5 Each Duct Tape 2 Rolls Paper Coveralls 10 Pair Tennis Shoes (Sizes 7-12) (half-sizes are OK) one pair each REVISION 0
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-13
.DOSE ASSESSMENT REVISION 9 PREPARED BY:
T. W. CORNELIUS RESPONSIBLE ORGANIZATION. EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE: 10/29/2002 LEVEL OF USE: REFERENCE USE PHONE 2038 DATE: 10/18/2002 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-13 Revision Number:
9 Pages Affected:
ALL Pagination Pages:
ALL Description of Change:
IC-10 The Dose Assessment portion of EPIP-14 was removed and placed in EPIP-13 as a part of EP Standardization. EPIP-13. "Chemistry Procedure" was replaced 11ith the Dose Assessment process.
Applicable portions of EPIP-13 were placed into EPIP-7. Netlher SQN or WBN ha\\e a "'Chemistry Procedure". The EP Peer Team recommended revising EPIP-13 to become the "Dose Assessment" procedure.
DOSE T
BROWNS FERRY -.
ASSESSMENT EPIP-I3 NUCLEAR PLANT' 1.0 PURPOSE The purpose'of this procedure is to describe actions and responsibilities of Radiological Controls'(RADCON) personnel during an assessment of environmental radiological conditions at Browns Ferry.
2.0 SCOPE v
EPIP-13 will be initiated when the RADCON Shift Supervisor or designee is requested or requires information regarding dose assessment.
EPIP-13 contains instructions for RADCON regarding methods for Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from airborne radioactivity releases.
The method for projecting TEDE and/or CDE from airborne radioactivity releases may be requested by operations to support emergency classification and/or protective action recommendations. The use of this method should only be utilized, in the absence of more sophisticated dose models, when the Central Emergency
,Control Center (CECC) is not activated.,,
3.0 INSTRUCTIONS 3.1 Method for Proiecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from-Airborne Radioactivity Releases The method for Projecting TEDE and Thyroid CDE from Airborne Radioactivity Releases is by manual method through the application of matrix tables and calculations.
3.1.1 Manual Method for Projecting TEDE and Thyroid CDE from Airborne Radioactivity Releases 3.1.1.1 The Radcon Shift Supervisor/designee or the TSC Radcon representative is responsible for completing Attachment A of this procedure when releases involves a stack release or Attachment B when the release involves a building or ground level release. The results of the completed attachment "A" and "B" should then be summarized on attachment "C" and forwarded to the Shift Manager /
Site Emergency Director.
PAGE 3 OF 21 RE O
9 REVISION 9
DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEARPLANT 3.0 INSTRUCTIONS (CONTINUED) 3.1.1.2 This method for projecting the TEDE and Thyroid CDE from airborne radioactivity releases should only be utilized in the absence of more sophisticated dose models.
3.1.1.3 This method may be requested by the Shift Manager prior to any emergency classification declaration. Results of this method may be utilized to classify emergency conditions, make protective action recommendations or by TSC personnel conducting evaluations of current plant conditions.
3.1.1.4 When requested the appropriate attachment of this procedure should be completed immediately and the results reported to the Shift Manager or SED.
4.0 ATTACHMENTS Attachment A - Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Stack Airborne Radioactivity Releases Attachment B - Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Ground Level Airborne Radioactivity Releases Attachment C - Projected TEDE and Thyroid CDE Assessment Survey Form PAGE 4 OF 21 REVISION 9
DOSE P
BROWNS FERRY ASSESSMENT
.I
,1 3BO NUCLEAR PLANT ATTACHMENT A (Page 1 of 8)
PROJECTING TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) FROM STACK AIRBORNE RADIOACTIVITY RELEASES CAUTION: USE THIS ATTACHMENT FOR STACK RELEASES ONLY DETERMINE RELEASE PATHWAY a
Contact the affected unit, Unit Supervisor to obtain information regarding the-release pathway.! The two pathway options for a stack release are; (1) stack (filtered) and (2) stack (unfiltered). Remember that when multiple pathways such as, Stack and Ground-Level,'are experienced, both pathway'calculations should be conducted and the results summed and recorded on Attachment C, the projected TEDE Thyroid CDE assessment survey form.
Record data on page 5 of this attachment.
DETERMINE ESTIMATED RELEASE START TIME AND RELEASE DURATION,
Contact the affected unit, Unit Supervisor to obtain information regarding the release start time and, duration Record release duration in hours. If the release duration can not be determined by operations, then a default duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be utilized.
r J
Record data on page 5 of this attachment:.
'.-/
DETERMINE NOBLE GAS RELEASE RATE IN jICI/SECOND The Noble Gas Release Rate should be calculated utilizing data obtained from the SPOS terminals under the screen naarne'"MISCRAD".a From this'screen use the "F5" key t6 view a tabular form ofthe' instruments utilized by the previous screen. Collect data described as "WIDE RANGE GASEOUS EFFL RAD MON and STACK FLOW".
a If the value for the "WIDE RANGE GASEOUS EFFL RAD MON" is equal to or less than 0.00, then discontinue the dose assessme6t'and report that there-are no off-site TEDE conicems for the stack release.
Utilize SPDS history to obtain the highest release concentration for-the incident.- It is recommended that data be reviewed from history approximately thirty (30) minutes prior to the estimated start time as referenced in the preceding step. Plai~e the data in the applicable calculation fields.'.The completed calculation provides the Noble'Gas Release Rate. Record and utilize this rate for the dose assessment calculations.
a If SPDS is unavailable, notify affected unit, operations personnel, to gain the information utilizing control room instrumentation, or if unavailable notify the Shift Manager/Site Emergency Director that TI 67, "Determination of Stack and Hardened Wetwell Vent Release Rates" (backup method), procedure must be performed by Radcon and Chemistry personnel.
The following conversion chart can be utilized to convert curies to microcuries To CONVERT MULTIPLY BY To OBTAIN C1 1.0 X 10 6
ýCi Record data on page 5 of this attachment.
PAGE 5 OF 21,RVIIO:
REVISION 9
DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEARPLANT ATTACHMENT A (Page 2 of 8)
DETERMINE RELEASE TYPE Contact the Plant Assessment Team, Core Damage Assessor (5-751-1633) in the CECC to determine the applicable release type. If the Core Damage Group in the CECC can not be contacted, then use the default release type, "Type 2". The four release type options are; (1) "Type 1", Reactor Coolant System Leakage Release, (2) "Type 2" Fuel Cladding GAP Release, (3) "Type 3", Fuel Over Temperature Release, and (4) "Type 4", Fuel Melt.
Some release types have an additional "F" indicator, this implies that the release type has a filtered release pathway.
Record data on page 5 of this attachment.
DETERMINE METEOROLOGICAL DATA Met data should be obtained from the SPDS terminals under screen name "METDATA" or by accessing the "Met Data Terminal" located in the Technical Support Center.
For stack releases record measurements at the 91 meter instrument readings.
If all Met Data Collection Methods are unavailable contact the National Weather Service by dialing 9-1 205-621-5650. The National Weather Service will provide wind speed and wind direction.
The default value for stability class with no met data available is "D" for stack releases.
The default value for wind speed with no met data available is 4.0 meters/second for the stack.
Record the following data on page 5 of this attachment STABILITY CLASS Note: Stability Class may be electronically displayed as 1,2,3.... This corresponds to A,B,C....
WIND SPEED IN METERS/SECOND The following conversion chart can be utilized for conversions to meters/second.
To CONVERT MULTIPLY BY To OBTAIN MILES/H 0.45 METERS/SEC METERS/SEC 2.2 MILES/H KNOTS 0.5 METERS/SEC WIND DIRECTION IN DEGREES PLUME DIRECTION IN DEGREES NOTE: To OBTAIN PLUME DIRECTION, ADD 1800 TO WIND DIRECTION IF < 1800 OR SUBTRACT 18001F WIND DIRECTION IS> 1800.
PAGE 6 OF 21 REVISION 9
DOSE BROWNS FERRY ASSESSMENT NUCLEAR PLANT ATTACHMENT A (Page 3 of 8)
DETERMINE THE TEDE FACTOR In determining the TEDE Factor you must know the stability class and the wind speed.
Locate the "TEDE Factor" table that corresponds to the applicable stability class located on page 7 of this attachment."
Locate the column within the table that corresponds to the applicable wind speed. If wind speed falls between the two column variables choose the lower value, this is the more conservative factor.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 5 of this attachment.
DETERMINE THE TEDE RATIO In determining the TEDE Ratio you must know the release pathway and the release type.
Locate the "TEDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 5 of this attachment DETERMINE THE THYROID CDE RATIO In determining the Thyroid CDE Ratio you must know the release pathway and the release type.
Locate the "Thyroid CDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered Determine data for the 0.62, 2 and 5 mile distances Record data on page 5 of this attachment.
PAGE 7 OF 21 R
-I -N REVISION 9
DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEARPLANT ATTACHMENT A (Page 4 of 8)
Complete CALCULATIONS AND ATTACHMENT C Input data into applicable calculation fields and calculate. Use caution to input correct factors and ratios for the different mile indications.
Note, to complete the Thyroid CDE calculation, the TEDE calculation must be completed and the TEDE value utilized.
Also use caution when inserting values into the calculations. Use correct terms, i.e. meters/second verses miles/hour.
COMPLETE ATTACHMENT C, PROJECTED TEDE AND THYROID CDE ASSESSMENT SURVEY FORM, AND FORWARD TO THE SHIFT MANAGER OR THE SITE EMERGENCY DIRECTOR. ENTER TEDE VALUES IN REM/HR ON ARROWS FOR APPLICABLE MILEAGE RINGS SHOW PLUME DIRECTION ON SURVEY MAP BY THE USE OF AN ARROW.
PAGE 8 OF 21 REVISION 9
DOSE ASSESSMENT:
EPIP-13, BROWNS FERRY NUCLEAR PLANT ATTACHMENT-A (Page 5 of 8)
Stack Release Data Collection and Calculation Worksheet -
RELEASE PATHWAY E3 STACK (FILTERED) 13 STACK (UNFILTERED)
ESTIMATED RELEASE START TIME________
ESTIMATED RELEASE DURATION NOTE: IF AN ESTIMATED RELEASE DURATION IS UNKNOWN USE-4 HOURS AS THE DEFAULT RELEASE DURATION.
NOBLE GAS RELEASE RATE I._CI/SECOND NOBLE GAS CONCENTRATIO(N CI/CC FLOW RATE SCFM C 0/CC) X (
SCFM) X (
472
) -
_pCI/SECOND RELEASE CONC FLOW RATE
' -I CONVERSION FACTOR RELEASE RATE RELEASE TYPE 13 TYPE 1F (FILTERED) 13 TYPE 2F (FILTERED) 13 TYPE 3F (FILTERED) 3[-
TYPE 4F (FILTERED)
NOTE: TYPE 2 IS THE DEFAULT RELEASE TYPE.
STABILITY CLASS WIND DIRECTION_
TEDE FACTOR TEDE RATIO 13 TYPE 1 (UNFILTERED) 13 TYPE 2 (UNFILTERED) 13 TYPE 3 (UNFILTERED) 13 TYPE 4 (UNFILTERED)
WIND SPEED METERS/SECOND DEGREES PLUME DIRECTION DEGREES
).62 MILES 2.0 MILES 5.0 MILES 0.62 MILES 2.0 MILES 5.0 MILES THYROID CDE RATIO 0.62 MILES 2.0 MILES 5.0 MILES PAGE 9 OF 21 REVISION 9
DOSE ASSESSMENT EPIP-13 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 6 of 8)
Stack Release Data Collection and Calculation Worksheet TEDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES
( _)X(
ICI/s)X( _
HOURS)X(
X
=
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 2.00 - 4.99 MILES
( _)X(
)
tCIlS) X (
HOURS)X(
X
=
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 5.00 - 10.00 MILES
( _
) X ( _ClS)
X (
HOURS)X(
X
=
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO THYROID CDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES
(
) )X(
)=
THYROID CDE REM TEDE REM THYROID CDE RATIO 2.00 - 4.99 MILES
(_)_
X(
__=_THYROID CDE REM TEDE REM THYROID CDE RATIO 5.00 - 10.00 MILES
(
) X(
) =
THYROID CDE REM TEDE REM THYROID CDE RATIO TEDE REM TEDE REM TEDE REM COMPLETE ATTACHMENT C AND FORWARD TO SM/SED.
PAGE 10 OF 21 I
REVISION 9
DOSE ASSESSMENT' EPIP-ag 73 o
BROWNS FERRY NUCLEAR PLANT ATTACHMENT.A'(Page 7 of 8)
TEDE Factor (rem/h per gCi/s) from a BFN Stack Release wind 'spe6d 2 mIs 3 m/s
-4 m/sI
-. 5
-ms 6 OE-10 4 BE-A 0 3 6E-10 2 4E-10 2 2E-10 1.8E-10 1 3E-10' 87E-11 6 MI/s -
7mis MI 8 m/s--
2 2E-10 0 1.9E-10 1.7E-10 7 8E-1l1 7 E-11 6 IE-11 3 6E-1l1 3 2E-11 2 8E-11
-9 MIS....10 mIs.
1.4E-10 1.2E-10 5 2E-11 4 4E-11I 2 4E-1 1 2.0E-11I Stability B.
-speed "_-_
miles 1 m/s 2 m/s 3 mIs 4 m/s 5 mIs 6 mIs 7 m/s 8 m/s 9 ms 10 MI/s 062 2 3E-09 1.1E-09 9.3E-10 7.1E-10 4 9E-10 4 4E-10 3.9E-10 3 4E-10 2.9E-10 2 4E-10 2
6 5E-10 3.3E-10 2.7E-10 2 0E-10 1 3E-10 1 2E-10 1.1E-10 9.4E-1 1 8 0E-1l 66E-11 5
9 9E-11 6 BE-11 6 6E-11 6 5E-11 6 4E-11 5 KE-lI 5 1E-l1 4 5E-11 3 9E-11 3 2E-11 Stability C
wind'speed miles 1 mIs 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 MIs-9 m/s 10 MI/s 0 62 2.OE-09 1 1E-09 9 2E-10 7.0E-10
-4.8E-10 4 4E-10 3 9E-10 3 4E-10 2 9E-10
' 2.5E-10 2,
1 4E-09 8 1E-10 6 5E-10 4 9E-10 3.3E-10 3.0E-10 2 7E-10 2 3E-10 2 2E-1O 1.7E-10 5
1 6E 1.1E-10 1.1E-10 1.1E-10 1.1E-10 1.0E-10 o90E-11 7.E-11 6.7E-1 55E-11 Stability D'
-wind speed OE-10 OE-101 4 MIS 5 MIS1 67E-101 46E-101 7 6E-101 5 3E-101 3 IE-101 3 2E-101 wind speed 4 m/s 15ms 7.4E-10 5 1E-10 8 OE-10 5 5E-10 4 5E-101 4 6E-10 wind speed 4 MIS 5 MIS 6.1E-10 4 2E-10 7.6E-10 5 4E-10 5 2E-10 5 4E-1 0 wind speed 4 m/s 15 m/s 5 5E-10 3 8E-10 6.3E-10 4 6E-10 4 5E-10 4 8E-10 6 MES 4 1E-101 4 7E-101 2 9E-101 6 m/s 4 6E-1 0 5 OE-10 4 2E-15 mis 6 MIS 3.8E-10 4 9E-10 4 9E-1 0 6 m/s 3 4E-10 4.2E-10 4 4E-10 7 mls 3 7E-101 4 2E-101 2 6E-101 7 MsI 4 1E-10 4 4E-1 0 3 7E-1 0 7 MsI 3 4E-10 4.4E-1 0 4 4E-10 7 MIS 3 9E-10 8 mEI 3 2EE-10 3 7E-1 0 9 92E-1 0 8 MIS 3.6E-10 3 9E-10 3 2E-10 8 m/s 2 9E-101 3 BE-101 3-8E-101 8 MsI 2 7E-10 3 3E-10 3 5E-10 9 mIs 1u m/s 2 8E-10 2 31E-10 3 2E-10 2 6E-10 1 9E-10 I 6E-10 9 MIS 10 m/s 3 1E-10 2 6E-10 3 4E-10 2 8E-10 2 8E-10 2 3E-10 9 m/s 10 M/s 2.5E-10 2 1E-10 3 3E-101 2 8E-10 3 3E-101 2 8E-10n 9 MIS 10 mIs 2 3E-10 1.9E-10 2.8E-10 2.4E-1 0 3.0E-10 2 6E-1 0 PAGE 11 OF 21 RS A
.'tihrihtv miles 2 mi lnnL Stabilrn/s 1 MIS 1.1E-09
-4 4E-10 miles 0 62 2
5 1 mls 1.7E-09 1.9E-09 1 1E-09 1 2E-09 Stability miles 0S62 2
Stability miles 0 62 2
5 Stability miles 0 62 2
5 1 m/s 1 7E-09 2 1 E-09 1 m/s 1 5E-09 1 8E-09 3 MIlS 8 9E-101 9 8E-101 3 1E-101 3 mIs-j 9 7E-101 1 1E-091 4 4E-101 3 m-s 8 OE-10 9.8E-10 5 1E-10 3 MIS 7 3E-10 8 1E-10 4.3E-10 2 MIS 1.2E-09 1 3E-091 2 m/s 9 9E-101 1.2E-091 4 9E-101 2 MElS1 9 OE-10 9 8E-101 1 MIS 1.5E-091 1 6E-091 REVISION 9 5
6 OE-10 4 3E-16T I
DOSE ASSESSMENT EPIP-13 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 8 of 8)
TEDE RATIOS FOR VARIOUS PATHS AND RELEASE TYPES (STACK Release)
Stack (Filtered)
IF_
Type 2F 10 1.0 10 Type 3F 11 10 10 TN pe 4F 1.2 1.1 11 i [
mi 0.62 2
5 1111 Tvpe 1 19 24 35 STACK (u7filtered)
Type' 2 Typ 3 1.92.
24 3.3 3.5 4ý 8 THYROID CDE RATIOS FOR VARIOUS ACCIDENTS AND RELEASE TYPES (STACK Release)
Stack (Filtered)
Type 1F TNpe 2F 1.6 E-03 1.6 E-03) 4.4 E-.02 4.4 E-02 6.9 E-02 6.9 E-02T Type 3F 7.6 E-03 1.7 E-02 2.7E-02I Type 4F 1.4E-02 3.OE-02 4.6E-02 L Ini 0 62 2
5 IF Type I 1.1 E+0 1.8E+0 2 OE+0 S1'A CK (unfiltered)
T3 pe 2 Type 3 0
1.IE+00 3.6E-0I 0
1.8E+00 5.2E-01 0
2.OE+00 5.8E-01 PAGE 12 OF 21
[
11i 0 62 2
5
- Type 10 1.0 1.0 111 T.-pe 4 5.3 8.8 135 mi 0.62 2
5 4 Type 4 3.1E-01 3.7E-01
.3.7E-01 REVISION 9
DOSE ASSESSMENT EPIP-13 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 8)
PROJECTING TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) AND THYROID CDE FROM GROUND-LEVEL RADIOACTIVITY RELEASES CAUTION: USE THIS ATTACHMENT FOR GROUND-LEVEL'RELEASES ONLY DETERMINE RELEASE PATHWAY Contact the affected unit, Unit Supervisor to obtain information regarding the release pathway. The two pathway options for a ground level 'release are; (1) Containment Bypass (CTM) and (2) Main Steam Line Break (MSLB). Remember that when multiple pathways such as, Stack and Ground-Level, are experienced, both pathway calculations should be conducted and the results summed and recorded on Attachment C, the projected TEDE and Thyroid CDE assessment survey form.'
Record data on page 5 of this attachment.
DETERMINE ESTIMATED RELEASE START TIME AND RELEASE DURATION Contact the affected unit, Unit Supervisor to obtain information regarding the release start time and duration. Record release duration in hours. If the release duration can not be determined, then adefault duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be utilized.
Record data bn *3age 5 of this attachment.
DETERMINE NOBLE GAS RELEASE RATE IN OsCIoSECOND To obtain the Total Noble Gas Release Rate for a building/ground level release the 'collection of rates from several building exhaust continuous air monitors (CAM) will be required. The Noble Gas Release Rate data should be obtained from a SPDS terminal under the screens "U1CAMS, "U2CAMS", and
"=U3CAMS". When you reach the applicable window press the "F5" key to retneve a tabular set of CAM data. Collect all CAM data as petitioned by page 4 of this attachment. Sum all rates together to obtain a Total Building Noble Gas Release Rate Record and utilize this rate for the dose assessment calculations. Utilize SPDS history to assist in obtaining the highest release rate for the incident. It is recommended that data be reviewed from approximately thirty (30) minutes prior to the estimated start time as referenced in the preceding step.
If SPDS is unavailable, notify affected unit operations personnel to gain the information utilizing control room instrumentation, orthroughýthe'6ompletion of O-SI-4.B.1.a.1, Attachment 11.
The following conversion chart can beutilized to convert curies to microcuries.
r To CONVERT Ci MULTIPLY BY 1.0 X 106 To OBTAIN I.LCI Record data on page 5 of this attachment.,- T I
PAGE 13 OF 21 E
i,
REVISION 9
DOSE BROWNS FERRY ASSESSMENT EPIP-r13 NUCLERPA ATTACHMENT B (Page 2 of 8)
DETERMINE RELEASE TYPE Contact the Plant Assessment-Team, Core Damage Assessor (5-751-1633) in the CECC to determine the applicable release type. If the Core Damage Group in the CECC can not be contacted, then use the default release type, "Type 2". The four release type options are; (1) "Type 1", Reactor Coolant System Leakage Release, (2) "Type 2" Fuel Cladding GAP Release, (3) "Type 3", Fuel Over Temperature Release, and (4) "Type 4", Fuel Melt.
Some release types have an additional "F" indicator, this implies that the release type has a filtered release pathway.
Record data on page 5 of this attachment.
DETERMINE METEOROLOGICAL DATA Met data should be obtained from the SPDS terminals under screen name "METDATA" or by accessing the "Met Data Terminal" located in the Technical Support Center.
For ground-level releases record measurements at the 46 meter instrument readings.
If all Met Data Collection Methods are unavailable contact the National Weather Service by dialing 9-1 205-621-5650. The National Weather Service will provide wind speed and wind direction.
The default value for stability class with no met data available is "D" for ground level releases.
The default value for wind speed with no met data available is 2.0 meters/second for ground level releases.
Record the following data on page 5 of this attachment.
"* STABILITY CLASS Note: Stability Class may be electronically displayed as 1,2,3.... This corresponds to A,B,C..'
WIND SPEED IN METERS/SECOND The following conversion chart can be utilized for conversions to meters/second.
To CONVERT MULTIPLY BY To OBTAIN MILES/H 0.45 METERS/SEC METERS/SEC 2.2 MILES/H KNOTS 0.5 METERS/SEC
"* WIND DIRECTION IN DEGREES
"* PLUME DIRECTION IN DEGREES NOTE: To OBTAIN PLUME DIRECTION, ADD 1800 TO WIND DIRECTION IF < 1800 OR SUBTRACT 1800IF WIND DIRECTION IS > 1800.
PAGE 14 OF21 REVISION 9
DOSE 1BROWNSFERRY ASSESSMENT EPIP-NUCLEAR PLANT ATTACHMENT B '(Page 3 of 8) "
DETERMINE THE TEDE FACTOR
-In determining the TEDE Factor you must know the stability class and the wind speed.
Locate the "TEDE Factor" table that corresponds to the applicable stability class located on page 7 of this attachment.
T Locate the column within the table that corresponds to the applicable wind speed. If wind speed falls between the two column variables choose the lower value; this is the more conservative factor.
Determine data for the 0.62, 2 and 5 mile distances.
- Record data on page 6 of this attachment:.
DETERMINE THE TEDE RATIO In determining the TEDE Ratio you must know the release pathway and the release type.
Locate the "TEDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 6 of this attachment.
DETERMINE THE THYROID CDE RATIO In determining the Thyroid CDE Ratio you must know the release pathway and the release type Locate the "Thyroid CDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 6 of this attachment.
PAGEi15 OF 21,R-I, REVISION 9
DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT B (Page 4 of 8)
Complete CALCULATIONS AND ATTACHMENT C Input data into applicable calculation fields and calculate. Use caution to input correct factors and ratios for the different mile indications.
Note, to complete the Thyroid CDE calculation, the TEDE calculation must be completed and the TEDE value utilized.
Also use caution when inserting values into the calculations. Use correct terms, i.e. meters/second verses miles/hour.
COMPLETE ATTACHMENT C, PROJECTED TEDE AND THYROID CDE ASSESSMENT SURVEY FORM, AND FORWARD TO THE SHIFT MANAGER OR THE SITE EMERGENCY DIRECTOR. ENTER TEDE VALUES IN REM/HR ON ARROWS FOR APPLICABLE MILEAGE RINGS. SHOW PLUME DIRECTION ON SURVEY MAP BY THE USE OF AN ARROW.
PAGE 160F21 REVISION 9
DOSE ASSESSMENT EPIP BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 5 of 8)
Ground-Level Release Data Collection and Calculation Worksheet RELEASE PATHWAY
[E CTM BYPASS El MAIN STEAM LINE BREAK ESTIMATED RELEASE START TIME ESTIMATED RELEASE DURATION NOTE: IF AN ESTIMATED RELEASE DURATION IS UNKNOWN USE 4 HOURS AS THE DEFAULT RELEASE DURATION NOBLE GAS RELEASE RATE
, ICI/SECOND RELEASE TYPE DESCRITPTION UO CAM-RB VENT EXH BETA GAS U1 CAM-RB VENT EXH BETA GAS Ul CAM-TB VENT EXH BETA GAS Ul CAM-TB VENT EXH BETA GAS DESCRITPTION, U2 CAM-RB VENT EXH BETA GAS U2 CAM-TB VENT EXH BETA GAS U2 CAM-TB VENT EXH BETA GAS DESCRITPTION U3 CAM-RB VENT EXH BETA GAS U3 CAM-TB VENT EXH BETA GAS U3 CAM-TB VENT EXH BETA GAS TOTAL NOBLE GAS RELEASE RATE CURRENT VALUE
_ jJ.LC I/SEC
__ jtC I/SEC
_ 9iCI/SEC CURRENT VALUE CIISEC _
__CI/SEC
__ _ __-__.,_tLClISEC
-CURRENT-VALUE CI/SEC S-1.CI/SEC
__CI/SEC CI/SEC
[] TYPE I (UNFILTERED)
LI TYPE 2 (UNFILTERED)
LI TYPE 3 (UNFILTERED).
LI TYPE 4 (UNFILTEIRED)
NOTE: TYPE 2 IS THE DEFAULT RELEASE TYPE.
STABILITY CLASS WIND DIRECTION WIND SPEED METERS/SECOND DEGREES PLUME DIRECTION DEGREES PAGE 17 OF,21 1E-I 9
SPDS "UlCAMS" "F5" "HISTORY" SPDS "U2CAMS" "F5" "HISTORY" SPDS "U3CAMS" "FY" "HISTORY" POINT ID 90-252c0 90-250cl 90-251cl 90-249cl POINT ID 90-250c2 90-251 c2 90-249c2 POINT ID 90-250oc3 90-251 c3 90-249c3 REVISION 9
DOSE ASSESSMENT EPIP-13 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 6 of 8)
TEDE FACTOR TEDE RATIO 0 62 MILES 2.0 MILES 5.0 MILES 0 62 MILES 2.0 MILES 5.0 MILES THYROID CDE RATIO 0.62 MILES 2 0 MILES 5 0 MILES TEDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES
(
) X (
_iC0/S)
X (
HOURS) X ( _
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO
)
__=_TEDE REM 2.00 - 4.99 MILES
(
_)X
(
ItCl/s)X(
)
HOURS)X(
X)=
TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 5.00 - 10.00 MILES
( _
) X
( _
CllS) X (
HOURS) X ( __)
=
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO THYROID CDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES TEDE REM THYROID CDE RATIO TEDE REM THYROID CDE REM 2.00 - 4.99 MILES
( T D R x (
) =
TEDE REM THYROID CDE RATIO THYROID CDE REM 5.00 - 10.00 MILES
(
) )X(
) =
THYROID CDE REM TEDE REM THYROID CDE RATIO COMPLETE ATTACHMENT C AND FORWARD TO SMISED.
PAGE 18 OF 21 REVISION 9
DOSE ASSESSMENT EPIP-13 BROWNS FERRY NUCLEAR PLANT ATTACHMENT-B (Page 7of 8)
TEDE FACTOR (remlhr per, iLCs) FROM A GROUND-LEVEL RELEASE Stability A
wind speed miles' 1 m/s 2 m/s 3 n/s 4ms 5 m/s, 6 ms 7 m/s' 8 m/s 9 m/s 10 m/s 062mi 1 6E-09 8OE-101 64E-101 48E-101 32E-101 29E-101 2.5E-101 2.2E-10 1 9E-10 1.6E-10 2mi 55E-10 28E-10 22E-10 1.7E-10 1 1E-10 1 OE-10, 90E-11 78E-11 67E-11 55E-11 5mi 7 5E-11 52E-11 5 2E-11 51E-11 51E-11 46E 40E-11 3 5E-11 3 0E-11 2 5E-11 I
Stability B
wind speed miles 1 n/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9m/s im/s 062 7.5E-09 3 7E-09 3 OE-09 2 2E-09 1.4E-09 1 3E-09 1 2E-09 1 OE-09 8 9E-1 0 7 5E-1 0
)
I 72E.-n1 3 F6-1 0 9E-1 0 22E-10 1.4E-10 1 3E-10 1 2E-10 1 CE-10 87E-11 72E-11 5
99E1-11 68E-11 6.7E-11 67E-11 66E-11
.60E-1111 53E-11 46E-11 40E-11 33E-11 Stability
.C
-wind speed miles 1 m/s 2 nm/s 3 m/s 4 m/s
-5 ms 6 m/s 7 m/s
- 8m/s-9/s_-
10m/s 062 2 2E-081
- 1 1E-08 9 0E-09 6 7E-091 -4 3E-09 3 9E-09.
3 5E-091 3 0E-09 2 6E-09 2 2E-09 2
29E-09 1 4E-09 1 2E-09 88 E-10 59E-10 53E-10
-47E-10 41E-10 35E-10 29E-10 5
1.9E-10 1 3E-10 1 3E-10 1 3E-10 1 3E-10 1.2E-10" 1.1E-10 93E-11 79E-11 65E-11 Stability D
wind speed miles 1 in/s 2 m/s 3 /s 4 /s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 062 63E-081 3.2E-08 26E-08 1 9E-08 1 2E-08 1 1E-08 1 OE-08 88E-09 75E-09 63E-09 2
1 OE-08 5 4E-09 4 3E-09 3 2E-09 2 2E-09 1 9E-09 1.7E-09 1 5E-09 1 3E-09 1 OE-09 5
83E-10 5 8E-10 5 7E-10 5 6E-10 5 6E-10 5 OE-0 45E-1 3.9E-1 I 34E-1n 2 8E-10 Stability E
wind speed miles I m/s 2m/s 3 m/s 4 m/s m5
/s 6 m/s 7 m/s 8 m/s gm/s 10 m/s 062 1.1 E-07 5 5E-08 4 4E-08 3 3E-08 2 2E-08 2 OE-08 1 SE-08 1 6E-08 1 3E-08 1 1E-08 2
2 1E-08 1 OE-08 8 3E-09 6 3E-09 4 2E-09 3 8E-09 3 4E-09 2 9E-09 2 5E-09 2 1E-09 5
1 8E-09 1 2E-09 1 2E-09 1.2E-09 1.2E-09 1.1E-09 98E-10 86E-10 7.3E-10 60E-10 Stability F
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 rS/s 6 m/s 7
/s 8 m/s 9 m/s 10m/s 062 2 2E-071 1.OE-071 8 3E-08 6 3E-081 4 2E-08 3 8E-08 3 4E-081 3 OE-08 2 6E-08 2.2E-08 2
4 9E-08 2 5E-08 20E-08 1.5E-08 9 7E-09 8 8E-09 7 8E-09 6 8E-09 5 8E-09 4 9E-09 5
4 6E-09 3 2E-09 3 1 E-09 31 E-09 3 OE-09 2 7E-09 2.4E-09 2 1 E-09 1 8E-O9 1.5E-09 Stability G
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 062 4 8E-07 2 3E-071 1 8E-071 1 4E-071 9 E-081 8 1E-081 7 2E-08 6 3E-08 5 4E-08 4 6E-08 2
1.1E-07 5.1 E-08 4 OE-08 3 CE-08 2.0E-08 1 8E-08 1 6E-08 1 4E-08 1.2E-08 1 CE-08 5
1 1E-08 7.5E-09 7 3E-09 7 2E-09 7.CE-09 6 3E-09 5 6E-09 4 9E-09 41 E-09 3 4E-09 PAGE 19 OF 21 R
S 9
REVISION 9
DOSE ASSESSMENT EPIP-13 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 8 of 8)
TEDE RATIOS FOR VARIOUS PATHS AND RELEASE TYPES B pass M1SLB Type 2 Type 3 5.9 7.6 60 7.6 13 17
-I-Type 4 22 21 52 I mi 0.62 2
5 Type I 10 11 23 III Type 2 10 11 23 Type 3 8.9 9.2 21 TI Type 4 24 25 59 I THYROID CDE RATIOS FOR VARIOUS ACCIDENTS AND RELEASE TYPES CT3IBv ass AI&LB Type 2 T pe 3 Type 4 mi Type I Type 2 TNype 3 YType 4 6.2E+00 2.OE+00 1.4E+00 0 62 1 1E+01 I1.1E+01 4.8E+00 3.3E+00 62E+00 2.OE+00 1.4E+00 2
1.1E+01 1.1E+01 4.8E+00 3.3E+00 62E+00 20E+00 1.4E+00 5
I1.IE+01 I.IE+01 4.8E+00 3.3E+00 PAGE 20 OF 21 CT11 - mii 0 62 2
5 lii 0.62 2
5 Type 1 23 23 55 Type 1 1.1E-01 1.IE-01 1 IE-01 REVISION 9 I
I
DOSE ASSESSMENT EPIP-13 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
PROJECTED TEDE and Thyroid CDE ASSESSMENT SURVEY FORM
[-M STACK RELEASE
-GROUND-LEVEL RELEASE TIME OF ASSESSMENT RELEASE RATE Cl/S WIND SPEED WIND DIRECTION MILES/HR STABILITY CLASS PLUME DIRECTION PREPARED BY DATE 5 Miles 1800 LAST PAGE PAGE 21 OF 21 Rem TEDE Rem Thyroid CDE Rem TEDE Rem Thyroid CDE Rem TEDE Rem Thyroid CDE REVISION 9
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-14 RADIOLOGICAL CONTROL PROCEDURES "REVISION '17 Is PREPARED BY:
T. W. CORNELIUS RESPONSIBLE ORGANIZATION. EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE 10/29/2002 LEVEL OF USE: REFERENCE USE PHONE: 2038 DATE-10/18/2002 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-14 Revision Number: 17 Pages Affected:
All Pagination Pages:
All Description of Change:
IC-20 The revision is being conducted to revise the manual method for calculating total effective dose equivalent and include a method for calculating thyroid committed dose equivalent.
Page 6 Revised the instruction portion of the procedure to include tlhroid CDE and add a statement to ensure that Attachment F is completed.
Page 7 Revised to update the title of attachments and the instruction section header Page 11-27 Revised to update the method for calculating and reporting the results for TEDE dose projection and include a method for calculating and reporting the results for Thyroid CDE.
IC-21 EPIP-14 is being revised as a part of EP Standardization. The portion of EPIP-14 that addresses Dose Assessment is being removed from this procedure and placed into EPIP-13 No portion of the procedure is being changed. The dose assessment process is not being changed. only the location of the procedure This revision deleted pages 11-23 Pages 11-23 are not marked as revisions due to the electronic processing of tables and management of the procedure. The deleted pages NA ere placed into EPIP-13.
RADIOLOGICAL' BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT 1.0 PURPOSE The purpose of this procedure is to describe actions and responsibilities of.,-.
Radiological Controls (RADCON) personnel during a radiological emergency at
-'Browns Ferry -
'>7 2.0 SCOPE
.EPIP-14 will be initiated when RADCON Shift Supervisor or designee receives indications that the Emergency Planhas been activated or information regarding processes contained within this procedure are required.
EPIP-14 contains instructions for RADCON during the implementation of the
- Emergency Plan event classifications. The procedure additionally contains instructions for RADCON duringSite Assembly and Evacuation, RADCON Lab Habitability, Issuance of Potassium Iodide, the use of the Health Physics
,.Network, and the Alternate Personnel Decontamination Facility.*
3.0 INSTRUCTIONS 3.1 Notification of Unusual Event 3.1.1 No offsite radiological problems are postulated during a Notification of 1,-ý Unusual Event.,(NOUE). -This situation should not have any major impact on RADCON.-
3.1.2 Although RADCON will not automatically be called, should assistance be needed, RADOON will follow.standard practices and procedures during response activities.,.-
5*-,,"
t,
,+
1 REVISION 17
,- PAGE I OF 9
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2 Alert 3.2.1 When a Site Assembly is conducted, (see Section 3.4) all RADCON personnel will report to their assigned assembly areas.
3.2.2 If radiological conditions warrant, RADCON personnel will periodically take radiation, airborne (particulate and iodine), and contamination surveys of all assembly areas inside the protected area (Refer to EPIP-8, Appendix "K and "B" for list of assembly areas).
3.2.3 A RADCON technician will accompany any personnel dispatched into areas of potential radiological hazard.
3.2.4 RADCON personnel will assist in the development of recovery plans as deemed necessary by the recovery organization. Recommendations will be made to keep exposure as low as reasonable achievable and to recommend and approve any clean up activities.
3.3 Site Area Emergency or General Emergency 3.3.1 RADCON technicians report to the lab as directed by their Shift Supervisor or designee. A site evacuation will be conducted at the SAE or GE classification, if not already completed (see Section 3 5) 3.3.2 RADCON personnel will periodically take radiation, contamination and airborne surveys as necessary to ensure no radiological hazards exist in occupied Emergency Response Facilities, (TSC, OSC, Staging Area, RADCON Lab, Chemistry Lab, Control Rooms, or other Operations areas).
3.3.3 A RADCON technician will accompany any personnel dispatched into areas of potential radiological hazard.
3.3.4 Equipment listed in CECC-EPIP-9, Attachment J, Section 1.0 may need to be transported to the environmental monitoring van. Nuclear Security (NS) will allow equipment to be removed from the protected area.
REVISION 17 PAGE 2 OF 9
RADIOLOGICAL iEP IPt BROWNS FERRY CONTROL PROCEDURES
-EPr
- j. ;NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED)
- 3.3 Site-Aiea Emer-gency or General Emergency (continued) 3.3.5 Initial offsite environmental assessment will be conducted per CECC-EPIP-9."
3:3.6 Dispatch RADCON technician to the site access control point established
-.by NS personnel:. Survey vehicles and personnel leaving the site using "RM-14 friskers-(or equivalent) and smear techniques, if radiological conditions warrant.
3.4,-Site Assembly and Evacuation c Lt 3.4.1 RADCON technicians proceed to the RADCON Lab and read your badge into the accountability reader. If uninhabitable,-see Section 3.5.
3.4.2 Sign the 'Accountability Roster., "" -. -
3.4.3 If any plant personnel are unaccounted for, NS will form search teams, each having at least one RADCON technician as a part of the team.
3.4.4 RADCON will survey personnel and vehicles leaving the site at the NS access control point, if radiological conditions warrant Contaminated
'individuals will be evacuated to the Power Service Shop No-4 Locker
'Room at Muscle'Shoals Reservation, as-directed by the OSC.
3.4.5 Should conditions ex'ist~that RADCON cannot survey all people and vehicles leaving the site, RADCON will set up a monitoring station as
> -'{
directed by the SED:-
3.5-Radiological Control Lab Habitability
'-w..
3.5.1 [NRC/C] When conditions within the RadconLab become uninhabitable the RADCON technicians will proceed to mechanical equipment room, cditrdl bay, Unit 3, elevation617:.r[NRC/C 81-19-:17]-,1
, 3J5.2 [NRC/C] -Report-location to the RADCON Manager in the TSC.
H",,
[NRC/C 81-19-17].
, PAGE 30O 9 REVISION 17
" i.
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES ENUCLEAR PLANT 3.6 Issuing Potassium Iodide (KI) 3.6.1 If the TSC RADCON Manager has reason to believe that a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine might exceed 10 rems (see Attachment A), the exposed person should be started immediately on a dose regimen of KI. This decision shall be immediately communicated to the SED.
3.6.1.1 If the TSC is not staffed or the RADCON Manager position has not been filled, then the senior onsite RADCON Supervisor has the authority to issue KI utilizing the bases describe in step 3 6.1 3.6.1.2 The initial dose of KI should be not delayed since thyroid blockage requires 30 to 60 minutes. Anyone authorized to initiate KI shall be familiar with the Food and Drug Administration approve package insert and be sure that each recipient is similarly informed 3.6.1.3 Prior to issuing KI to an individual, the person should be asked if he/she is allergic to iodine If the person indicates a possible sensitivity to iodine they should not be issued KI.
3.6.2 KI is stored in the plant RADCON supply cage and the REP Van instrument kits.
3.6.3 RADCON normally will not dispense a container or package of KI to TVA Personnel involved in activities to support a radiological emergency.
RADCON will however dispense a single individual dose of KI to team members dispatched from the OSC.
3.6.4 Follow the dosage outlined on the package insert (Attachment B). A copy of the Food and Drug Administration approved package insert shall accompany the issuance of KI. If KI is distributed in individual doses, verbal instructions of the significant information on the package insert by a knowledgeable individual is sufficient.
3.6.5 Complete the KI Issue Report (Attachment C) or an RWP time sheet as appropriate for issuance of KI. An RWP time sheet may be used for this documentation instead of completing the Attachment C. If the RWP time sheet is used to document distribution of the KI, note the time of KI distribution on the back of the time sheet.
REVISION 17 PAGE 4 OF 9
RADIOLOGICAL
- 1.
BROWNS FERRY CONTROL PROCEDURES EP NUCLEARPLANT 3.7 Use of the NRC Health Physics Network (HPN) 3.7.1 The HPN contact with the NRC will be made by the RADCON group.
3.8 Browns Ferry Alternate Personnel Decontamination Facility 3.8.1 The BFN alternate personnel decontamination facility is located at the rPower Service Shop No. 4 LockerRoom on the Muscle Shoals Reservation. It will be activated when the BFN personnel decontamination facility is inaccessible or incapable of handling the number of contaminated personnel.
3.8.2 When the decision is made to transport contaminated personnel to the alternate decontamination facility, BFN RADCON shall make notifications to the CECC, and the Power Service Shops.
The notification to the CECC shall include all available information at that time. Interface with state and local authorities (i.e., transportation route considerations) will be made available via the CECC.
The notification to the Power Service Shops shall include a request that the Shop 4 sewer lift station sump be emptied, followed by tagging out the power supply to the two pumps. (The sump and control panel are located adjacent to the North East corner of the Gas and Diesel Building, approximately 500 feet east of Shop 4). In the event a volume of effluent in excess of 1800 gallons is anticipated, additional containment capabilities will need to be arranged. The primary point of contact is the Supervisor, Maintenance Group, with the back-up being the Mechanical Supervisor. Notification phone numbers are listed in the Radiological Emergency Notification Directory (REND).
REVISION 17 1
, PAGE 50OF 9
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 Browns Ferry Alternate Personnel Decontamination Facility (continued) 3.8.3 Browns Ferry RADCON is responsible for the following:
Providing appropriate personnel and equipment to operate the alternate decontamination facility.
Calculating the amount of radioactive material in the decontamination effluent. Effluent releases will be in accordance with Standard Program and Process (SPP) -5.1.
Documenting appropriate records on all contaminated personnel.
Ensuring the alternate decontamination facility is secured following decontamination activities and assisting in recovery efforts.
4.0 ATTACHMENTS Attachment A - Occupational Dose From Inhalation of Iodine-1 31 Attachment B - Patient Package Insert Attachment C - Potassium Iodide Issue Report REVISION 17 PAGE 6 OF 9
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page'1 of 1)
OCCUPATIONAL DOSE FROM INHALATION OF IODINE-131 I.00E-03
-1.00E-04 0.1 1o0 1
10 Exposure Time (hours)
REVISION 17 I.-
50 rem remre
_~~1
__e__m I ~ __________________________
0 E
0 IU 0
4t9 "1.00E-05 1.OOE-06 1.OOE-07 1.OOE-08 1.OOE-09
- t. PAGE 7 OF 9
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 1)
PATIENT PACKAGE INSERT INDICATIONS THYROID BLOCKING IN A RADIATION EMERGENCY ONLY DIRECTIONS FOR USE Use only as directed be State or local public health authorities in the event of a radiation emergency Dose ADULTS AND CHILDREN ONE YEAR OF AGE OR OLDER One (1) tablet once a day Crush for small children BABIES UNDER ONE YEAR OF AGE: One half (1/2) tablet once a day Crush first DOSAGE Take tablets 10 days unless directed otherwise by State or local public health authonties Store at controlled room temperature between 15o and 30 0C (590 to 860F). Keep package dry and foil packets intact WARNING POTASSIUM IODIDE SHOULD NOT BE USED BY PEOPLE ALLERGIC TO IODIDE Keep out of the reach of children In case of overdose or allergic reaction, contact a physician or the public health authority.
DESCRIPTION Each IOSATTm TABLET contains 130 mg of potassium iodide HOW POTASSIUM IODIDE WORKS Certain forms of iodine help your thyroid glands work right Most people get the iodine they need from foods, iodized salt or fish The thyroid can "store" or hold only a certain amount of iodine In a radiation emergency, radioactive iodine may be released in the air This matenal may be breathed or swallowed it may enter the thyroid gland and damage it. The damage would probably not show itself for years Children are most likely to have thyroid damage IOSAT Tablets (POTASSIUM IODIDE TABLETS, U S P)
(pronounced poe-TASS-e-um EYE-oh-dyed)
(Abbreviated KI)
TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU IN A RADIATION EMERGENCY, RADIOACTIVE IODINE COULD BE RELEASED INTO THE AIR. POTASSIUM IODIDE (A FORM OF IODINE) CAN HELP PROTECT YOU IF YOU ARE TOLD TO TAKE THIS MEDICINE, TAKE IT ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN MORE WILL NOT HELP YOU AND MAY INCREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE THIS DRUG IF YOU KNOW YOU ARE ALLERGIC IODIDE (SEE SIDE EFFECTS BELOW)
REVISION 17 If you take potassium iodide, it will fill up your thyroid gland This reduces the change that harmful radioactive iodine will enter the thyroid gland WHO SHOULD NOT TAKE POTASSIUM IODIDE The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for example, a thyroid hormone or antithyroid drug)
Pregnant and nursing women and babies and children may also take this drug.
HOW AND WHEN TO TAKE POTASSIUM IODIDE Potassium Iodide should be taken as soon as possible after public health officials tell you you should take one dose every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> More will not help you because the thyroid can "hold" only limited amounts of iodine Larger doses will increase the nsk of side effects You will probably be told not to take the drug for more than 10 days SIDE EFFECTS Usually, side effects of potassium iodide happen when people take higher doses for a long time You should be careful not to take more than the recommended dose or take it for longer than you are told Side effects are unlikely because of the low dose and the short time you will be taking the drug Possible 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 stomach upset and diarrhea)
A few people have an allergic reaction with more serious symptoms. These could be fever and joint pains, or swelling of parts of the face and body and at times severe shortness of breath requiring immediate medical attention.
Taking iodide may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).
WHAT TO DO IF SIDE EFFECTS OCCUR If the side effects are severe or if you have an allergic reaction, stop taking potassium iodide. Then, if possible, call a doctor or public health authority for instructions HOW SUPPLIED IOSATTm TABLETS (Potassium Iodide Tablets, U S P) packages of 14 tablets (NDC 51803-001-01)
Each white, round, scored tablet contains 130 mg potassium iodide Distributed by ANBEX, INC 15W 75th St, New York, N Y 10023 PAGE 8 OF 9
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
POTASSIUM IODIDE ISSUE REPORT NAME SSN Time of Time of Package Issue Agent Exposure Initial KI Insert Dose Issued 2
3 4
5
- 6.
- 7.
8 9
10 11 12 13
- 14.
15 16
- 17.
18 19 20
- 21.
- 22.
23 24 25 26 27 28 29 30 LAST PAGE PAGE 9 OF 9 REVISION 17