ML18162A101
| ML18162A101 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/24/2018 |
| From: | Karsten C Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EP-18-0016 EP-120 Rev.12 | |
| Download: ML18162A101 (60) | |
Text
IPEC EMERGENCY PLAN DISTRIBUTION LIST Page 1 of 2 IP3 CONTROL ROOM DELIVERED BY DOCUMENTS IP3 53FT. CCR 1 COPY OF ALL EP'S IP3 SHIFT MANAGER DELIVERED BY DOCUMENTS IP3 53FT. ELEVATION 1 COPY OF ALL EP'S IP2 CONTROL ROOM DELIVERED BY DOCUMENTS IP2 53FT. CCR 1 COPY OF ALL EP'S IPEC TSC DELIVERED BY DOCUMENTS IP2 53FT. ELEVATION 1 COPY OF ALL EP'S IP2 SIMULATOR DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG. 1 COPY OF ALL EP'S IP2 SIMULATOR- CLASSROOM4 DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG. 1 COPY OF ALL EP'S 3 COPIES OF ALL EP'S IP2 SIMULATOR - CLASSROOM 5 DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG.
EXCEPT E-PLAN NRG RESIDENT INSPECTOR NRG IP2 88FT. ELEVATION 1 COPY OF ALL EP'S 1 COPY OF ALL EP'S AND DOC l.._ ___ ,_
CONTROL DESK OFFSITE. GENERAt RECORDS EXCEPT IP-EP-115 1 COPY OF ALL EP'S AND NRG OFFSITE GENERAL RECORDS EXCEPT IP-EP-115 1 COPY OF ALL EP'S AND NRG OFFSITE GENERAL RECORDS EXCEPT IP-EP-115
. .. *.* * ... 1 COPYOFTHE
'.:TL:E.NORE TCfU~DA~E.'i' FOLLOWING:
WEBSITE' ' : E-PLAN, IP-EP-115, 120, NEW YORK STATE OEM TED FISCH J 210,220,230,250,310,
- Ne:'.nilAiL C0°PIE$f:,>i 320,340,360,410,420, 430, 620 & IP-1055 1 COPY OF E-PLAN, WESTCHESTER COUNTY OEM DENNIS DELBORGO OFFSITE IP-EP-310 & 340 ROCKLAND COUNTY FIRE AND 1 COPY OF E-PLAN, NICHOLAS LONGO OFFSITE EMERGENCY SERVICES IP-EP-310 & 340 ORANGE COUNTY EMERGENCY 1 COPY OF E-PLAN, SHANNON FISHER OFFSITE SERVICES CENTER IP-EP-310 & 340 PUTNAM COUNTY BUREAU OF 1 COPY OF E-PLAN, KEN CLAIR OFFSITE EMERGENCY SERVICES IP-EP-310 & 340
- THE FOLLOWING LOCATIONS ARE *ELECTRONIC DISTRIBUTIONS* )-J..-lJ5
- Jf-L
--- Entergy Indian Point Energy Center CONTROLLED DOCUMENT Document Control 450 Broadway TRANSMITTAL Buchanan, NY 10511 TO: DISTRIBUTION DATE: May 24, 2018 FROM: IPEC DOCUMENT CONTROL -- 3RD FLOOR ADMIN BLDG PHONE#: 914-254-6835 TRANSMITTAL#: EP-18-0016 The Document(s) identified below are forwarded for use. Please review to verify receipt, incorporate the,document(s) into your controlled document file, properly disposition superseded, voided, or inactive document(s).
Sign and return the receipt acknowledgement below within ten (10) working days.
AFFECTED DOCUMENT: IPEC EMERGENCY PLAN PROCEDURES DOC # I REV # I TITLE I INSTRUCTIONS THE FOLLOWING PROCEDURE IS BEING "VOIDED", PLEASE REMOVE FROM YOUR BOOKS:
I --*----------1 EFFECTIVE I
l MAY 3 0 2018 . I IP-EP-120 REV.12 I
.I fi"""'\j\..,,,..E--
I II l L\r'\ !
L----------------,
RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFFECTIVE DATE(S)
(IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S). C)c., (!__
NAME(PRINT) SIGNATURE DATE COPYLOCAT~~/(
ATTACHMENT 9.2 10 CfR 50.54(Cl)(3) SCREENING SHEET1 OF3 Equipment'Facmfy/Other: Indian Point Energy Center (IPEC)
Title:
Emergency Classification Part l. Description of Activity Being Reviewed (This is generally changes to the emergency plan, EALs, EAL bases, etc. - refer to step 3.0f6J}:
,. Revised the URL address for the national earthquake center from http:/fearthquako.usgs.gov/eqcenter/ to http:/learthquake.usgs.gov in Note 4 on pages 39, and 49.
.. Replaced interface IP-EP-220, Technical Support Center with EN-EP-610, Technical Support Center {TSC)
Operations.
Part U. Activity Previously Reviewed? DYES !?:>!NO rs this activity fully bounded by an NRC approved 10 CFR 50.90 submittal or 50.54(q)(3) Ccn!inoe to Evaluation is next part Alert and Notification System Design Report? NOT required.
Enter If YES, identify bounding source document number/approval reference and justification ensure the basis for concluding the source document fully bounds the below and complete Part proposed change is documented below: VI.
Justification:
0 Bounding document attached (optional)
- m. Applicability of Other Regulatory Change Control Processes Part Chock if any other regulatory change processes control the proposed activity.(Refer to EN-Ll-100)
This procedure has been excluded from further EN-U-100 reviews.
A.PPLICAB!UTY CONCLUSION (gJ If there are no other controlling change processes, continue the 50.54(q)(3) Screening.
D One or more controlling change processes are selected, however, some portion of the activity involves the emergency plan or affects the Implementation of the emergency plan; continue the 50.54(q){3) Screening for that portion of the activity. Identify the applicable controlling change processes below.
0 One or more controlling change processes are selecled and fully bounds all aspects of the activity. 50.54(q>(3) is NOT required. ldentifv controllino chani:ie processes below and comolete Part VI.
CONT~OlUNG CHANGE PROCESSES iO CFR 50.54(q) ONLY Part !V. Editorial Change 12:SJYES UNO SO.S4(q)(l) Continue to next ls this activity an editorial or typographical change such as formatting, paragraph !:.valuation is part numbering, spelling, or punctuation that does not change intent? NOT required.
Justification: Enter justification and
- 1. This change corrects an incorrect URL address for the National Earthquake Center continue to next and does not change the intent of the procedure. part or
- 2. This change replaces a voided procedure reference wilh the procedure number that complete Part replaced ii. V!as umilicabh:.
- EN-EP-305 REV 6
~=~ r~ ~ ~~~~~ =*
~----
~:WM.A:'. ~'W'W"'
10 CfR 50.S4(Q)(3) SCRE!i::NSNG
- Number: IP-EP-120 Eqa!ipme11t/F~emtyJOther: lm:Uan Poir>>t Energy Cantr (!PEC) iit!e: Classification 12 Part V. Eim,rgency P!annlng ElementiFunetkm Screen (Associated 10 CFR 50.47{1>) planning standard funcilon identified in brackets) Does this ecilvlty affect any of the following, im;luding program elements from NUREGw 06541FEMA REP-1 Section II?
- 1. Responsibi!ity for emergency respcmse is essigned. [11
.2. The ri1!lsponse organization has the staff to respond and to augment staff on a oonti111.1!11g l::H:1sis {2*
staffing) in accordance with the emergency plan. [1]
- 3. The process ensures that on shlft emergency response responsibilities are staffed and assigned.
- 4. Tho procsss for time!y augmentation of onshift staff Is established and maintai01ed. [2]
- 5. Arrangements for requesting and using off site assistance have been made. [3]
- 6. State and local staff can be accommodated at the EOF in accordance with the emerg@ncy plan. (JJ
- 7. A standard scheme of emergency clasisificaHon and action levels is in use. [4]
- 6. Procedures for notifk:ation of State and local governmental agencies are cpable of alerting them of the declared emergency within i 5 minutes after declaration of an emergency !l!!ld providing foUow-up notifications. [5]
- 9. Administrative and physical means have been established for alerting and providing prompt 0 inslructiom; to the publlc within the plume exposure pathway. [5}
iO. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evalu.iition of Alert am::!
NotiflcaUon Systems for Nuclear Power Plants, or complles w1th the licensee's FEMA-approved ANS report and supporting FEMA approval letter. (5]
i 1. ara established for prompt communication among principal emergency response organizaliorm. {&]
- 12. Systems are estab!ished for prompt communication to emergency response personnel. [6]
. Emergency preparedness information is made available to the public cm a periodic basis within plume exposure pathway emergency planning zone (EPZ}. {71 i4. Coordinated dissemination of public information during emergencies is established. [7]
- 15. Adequate facilities are maintained to support emergency response. [81
- 16. Adequate equipment is maintained to support emergency response. [SJ
- 17. Methods, systems, and equipment for assessment of radloactive releases are in use. [9}
i 8. A range of public PARs ls available for imp!emer.tatlon during emergern::ies. [HJ]
- 19. Evacuation time estimates for the population located in the plume exposure pathway EP:Z are avaHab1e to support the formulation of PARs and have been provided to State and local governmental Bu!horities. [iO]
- 20. A range of protective ac:rlons is available for plant emergency workers during those for hostile sction events.[10]
- EN-EP~305 REV 6
2i. The resources for controlling radiological exposures for emergency ants are made for medical services for contaminated, injured individuals. [12.]
- 23. Plans for recovery and reen!ry are developed. [131
- 24. A drill and exercise program {irn::!uding radiological, medical, health physics rid other areas} is eslab!lshed. [141
- 25. Orms. exercises, and training evolutions that provide performance opportunlties to develop, maintain, and demonstrate key ski!!s are assessed via a formal critique process in order to identify weakm;tt:;ses. [i 4J
- 27. Tratning 1s provided to emergency respcmders. (Hi]
for emergency development and review is establishect ['iSJ 21:i. Plarmers responsible for emergency plan development and maintenance are properly trained. [16]
!2 Jf no Part V criteriu are checked, a 50.54(q}(3} Evaluation is required; document the i:lasls for corn:.:!usion below am:i complete Part VL a If Einy Patt V criteria are checked complete Part Vi and perfo,m a 50.54(q)(:3) Evaluation.
- BASIS FOR CONCUJS!ON Yhe proµosod cllar.ga corrects an tncorract URI. in the pmcadum for the il!atlona! Earthquake Center and corrects a procedure mfereni::e. These changes do not change the meaning or Intent of a descriplhm. does not change fsci!l!les or ffl:!Ulpment. and does not ch@nge a proce$S Ne further ovaluation is iequlred for this change.
Preparer Name (Print) O&;te:
Casey Karsten Sr. Emergency Planner
{Optional) Reviewer Name (Print} Reviewer Signature Reviewer Name (Print) 7fmothy F. Garvey Nuclear EP Project Manager Approver Name (Prinl)
,~ Reviewer Signature Approver Signature Date:
Frank J. Mitchell L1,:y ~Mikr Gr Fr.,,,k. m;~t-t!I At klw.....
Manager, Emergency Planning or des1gnee
- IPEC IMPLEMENTING PROCEDURE IP-SMM-AD-102 Rev:
- PREPARATION, REVIEW, AND APPROVAL A1iACHMENi 10.2 Procedure
Title:
Procedure No.
Emergency Classification
!P-EP-120 Existing Rev: 11 NewRev: 12 DRN/EC No:
Page 35 of 43 IPEC PROCEDURE REVIEW AND APPROVAL ORN-18-00163 Procedur~ CJ Converted To IPEC, Replaces: Iem~ol'tiia Pr2&1!QU!l! c111n;1 (MARK Applica (MARK Applicable) 0 NEW PROCEDURE Unit 1 Procedure No. EDITORIAL Temporary Procedure Change 0
0 GENERAL REVISION ADVANCE Temporary Procedure Change 0
0 PARTIAL REVISION 0 EDITORIAL REVISION Unit 2 Procedure No, 0 CONDITIONAL Temporary Procedure Change 0 VOID PROCEDURE Terminating Condltlon:
0 SUPERSEDED Unit 3 Procedure No:
I Cl RAPID REVlSiON Document in Microsoft Wore!:
!El Yes D No D V01D DRN/TPC No(s):
Revlslon Summa.rv. Updated the URL in note four for the current web address of the National Earthquake Center.
lmplemeotatiM Requirements Implementation Phar? D Yes 0 No Formal Training? D Yes tIDNo Special Handling? D Yes tIDNo 4*, =
RPO Dept Emergency Planning Writer: {Print Name/ExtJSign): Casey Karsten I 7789 J c- -~~
Review ano Approval {Per Attachment i 0.1, IPEC Review And Approval Requirements}
____/\//A ...._"""-='--------------------------
- 1. D Technical Reviewer:
(Print Name/ Slgnatul'E!I Date}
- 2. 0 Cross-Disciplinary Reviewers:
Dept Reviewer:
Dept: Reviewer:
- 3. llil RPO- Responsibi!i!ies/Check!ist: Frank J Mitchell/
(Print Name/ Srgnatul'E!I Data)
D PAD required and is complete (PAD Approver and Reviewer quatificatlons have been verlflecl)
!2'l Previous exclusion from further Ll* 100 Review is still valid D PAD not required due to type of change as defined in 4.6
- 4. D Non-Intent Determination Complete:
NO change of purpose or scope
{Print Name/ Sigrmturel Date)
NO change to less restrictive acceptance criteria
~ reduction in the level of nuclear safety NO change to steps previously identified as commitment steps
~ voiding or canceling of a procedure, unless NO deviation from the Quality Assurance Program Manual requirements are incorporated into another procedure NO change that may result In deviations from Technical or tin, need for the procedure was e!imlnated Specifications, FSAR. plant design requirements,
- 5. 0 On-Shift Shift Manager/CRS:
(Print Name/ Signature/ Date)
- 6. 0 User Validation: User: Validator:
- 7. D Special Handling Requirements Understood:
(Print Name/ Signature£ Date)
IPEC NON-QUALITY RELATED Revision 10 EMERGENCY PLAN PROCEDURE:
~Enleroy b ADMINISTRATIVE PROCEDURES Attachment 9.1 Emergency Planning Document Change Checklist Form (All sections must be completed, NIA or place a check on the line where applicable)
Section 1 Doc/Procedure Type:
AdministrativeD EPLAN 0 N/AO Doc/Procedure No: IP-EP-120 Doc/Procr:$dure
Title:
rrective Action: CR#: IP3-2018-00483 CA-2 Section 2 Change Do1scripfio11
- 1. Ensure the following are completed, or are not applicable and are so marked:
- a. 50.54q
- b. EN-FAP-OM-023
- c. !P-SMM- AD-102
- 2. Transmittals are completed: D NIA D *Date: _ _
- 3. Ensure the proper revision is active in Merlin: D NIA D
- 4. Approved doc/procedure delivered to Doc. Control for distribution: D NIA D Date:
- 5. Position Binders updated: 0 NIA D Date: _ _
- 7. Supporting documentatiori is submitted as a general record in MERLIN: D N/A D Date: _ _
- 8. Word files are moved from working drafts folder to current revision folder in the EP drive:
D NIA D Date: _ _
Sheet 1 of 1
- "Use of Potassh.1m Iodide Revision Matrix IP-EP-420 Indian Point Personnel Durin an Emergency" Revision 6 I Ntimb(!r LCM";£1tiO!i -. _ CoillcHtion Proposed Page 4 of 4 The Assembly Area Cacm:Unators SHALL issue Kl to The Assembly Area Coordinators SHAll issue Kl to 1.
Section 5.6.1 personnel in the GSB and EEC. personnel in the GSB/EEC.
Attachment 9.3 This fact sheel is about a new policy for people, This fact sheet is about the NYS policy for people, Sheet 1 of 2 especially those who live within ten miles of a nuclear especially those who live within ten miles of a nuclear 2.
Opening power plant. who may be exposed to radiation from a power plant, who may be exposed to radiation from a
. statement nuclear olant emergency. nuclear plant emergency.
Attachment 9. 3
- 3. Sheet 1 of 2 How does potassium iodide work? How does Kl work?
Question#2 ...
The table on the next page shows the smallest Kl The table below shows the smallest Ki dose that dose that different age groups can take which will different age groups can lake which will protect the protect the thyroid. Kl comes in liquid, 65~mg tablets thyroid. At the moment, the pill only comes in a 130 and 130-mg tablets. Since it is hard to cut many pills, mg tablet Since ii 1s hard to cut many pills the State the State Health Commissioner says that, in an Attachment 9.3 Heallh Commissioner says that. in an emergency, it is emergency, it is safe for clliklren at school or day
- 4. Sheet i of 2 safe for children at school or day care centers to take care centers to take the whole pill. ifs better for Question # 10 the whole pill. For children or babies who c.armot take children under 12 years old to take the 65-mg pill, but pills, parents and caregivers can cut or crush the pill to it is safe to take the *rno~mg pill if that is the only one make lower doses. For example, if 130 mg pill were you have. For children or babies wlio cannot take dissolved in 8 ounces of juice or other liquid, on 01..mce pills, paremts and caregivers can cut or crush the pill would contain 16 mg of Kl. to make lower doses, or ~ive the liouid form of KL Attachment 9.3 Deleted the old table and inserted a new table
- 5. Sheet2 of2 Old Table consistent with lha NYS Fact Sheet Question # 10 Attachment 9.3 Ki is helpful for about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. You should keep Kl is helpful for about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. You should keep
- 6. Sheet2 of 2 taking it until the health department says to stop or you taking it once a day 1.mtil the health department says Question # 11 f the emeroencv area.
Attachment 9.3 Kl can come as a pill or a liquid, but right now it is only Kl can come as a pill or a liquid. Pills are available in
- 7. Sheet2 of2 available .ms a pill. It may also be available as a liquid 65-mg or 130-mg doses. Kl is also available as a Question # 12 soon.
- "Use of Potassium fodidia Revision Matrix IP-EP-420 Indian Point 1.r11:>1fC:,l"U"!Hn,~ Revisiofl 6 Attachment 9.3 The manufacturers say Kl stays 'fresh' for 3 - 5 years. The manufacturers say Kl stays "fresh" for 5~7 years.
- 8. Sheet2 of2 If you keep it in a dry dark and cool place, il should last if you keep it in a c:l.y, dark and cool place, it should Question # 13 for manv vears. last for manv vears.
Yes. though it may not widely available in drugstores near you. Since it is not a prescription drug, you can lt is not widel;' ,,vailable in drugstores yet, but since it is buy it over t11e Internet. As with other drugs, make Attachment 9.3 not a prescription drug, you can buy it over the internet. sure the KI you buy has been approved by the FDA.
9 Sheet2 of 2 We hope to give a supply of l '.§ Review and Approval {Per Attachment m. i, IPEC Review A.::.;n;;;.cl~........._
- 1. IRl Technical Reviewer: Michael York/
- 2. D Cmss-DiscipHnary Reviewers:
Dept: Reviewer:
Dept: Reviewer:
RPO- Responsi!:li!ities/Checldist Frank Mitchell I (Print Name/ Slgnatuffl/ Cate)
D PAD required and Is comp!ete (PAD Approver and Reviewer qualifications have been vefiflad)
IE Previous exclusion from further ll-100 Review is still valid D PAD not required due to type of change as defined in 4.6
- 4. Cl Non-!nlent Determination Complete:
NQ change of purpose or scope
{Prl nt .Name/ Signature! Dat@l NO change to less restrictive acceptance crideriim NO reduction in the level of m..rclear safety NO change to steps previously identified as commitment steps NO voiding or canceling of a procedure, urdess .t:!Q deviation from the Quality Assurance Program Mam.1ai requlrements are incorporated into another procedure NO change that may result in devieticms from Tec:hnlaii or lhe need for the procedure was eliminated Speciflaitions, FSAR, plant design r@qulrements,
- 5. D On-Shift Shift Manager/CRS:
(Print Name/ !!1,111at1.1ffl/ Oat}
- 6. 0 User Validation: User: Validator:
- 7. 0 Special Handling Requirements Understood:
iPEC NON-QUALITY RELATED Revision 'iO EMERGENCY PLAN PROCEDURE
-= Entergy ADMINISTRATIVE PROCEDURES lEFl::REl~CE USE 1 of 1 AttachmeITTJt 9.1 Emerg~ncy Planning Document Change Checklist Form
{All sections must be completed, N/A or place a check on the line where applicable)
Section 1 Doc/Procedure Type:
AdministrativeD lmplementino ~ EPLANO N/AO Doc/Procedure No: IP-EP-420 Doc/Procedure
Title:
Use of Potassium Iodide by Indian Point Personnel During an Emen.:iencv Corrective Action: !Yes~ NoLJ N/AO CR#:CR-1p2..201e-02sa2 CA-2 Section 2 Change Description
- 1. Ensure the following are completed, or are not applicable and are so marked:
- a. 50.54q
- b. EN-FAP-OM-023
- c. IP-SMM-AD-102
- d. OSRC f8]
f8]
18]
- 2. Transmittals are completed: D NIA D Date:_ _
- 3. Ensure the proper revision is active in Merlin: D NIA 0
- 4. Approved doc/procedure delivered to Doc. Control for distribution: D NIA D Date:
- 5. Position Binders updated: 0 NIA O Date: * - -
- 7. Supporting documentation is submitted as a general record in MERLIN: D NIA D Date: _
- 8. Word files are moved from working drafts folder to current revision folder in the EP drive:
D N!AO Date:_
Sheet 1 or 1
\
- 11,*
C:01\JTR()LLED ENNIPEC NON-QUALITY RELATED IP-EP-120 Revision 12 EMERGENCY PLAN PROCEDURE
~ Entergy 1MPLEMENr1NG PROCEDURES REFERENCE Use Page 1 of 49
- L . _ _ __ _ _- - - - 1 , __ _. 1 - - -_ _ ____.
EmergenC?Y Classification Prepared by: Casey N. Karsten c--=-~ An}
Table A-1 column "Alert" for.::: 15 min. A-1 Any valid radiation monitor reading Any valid radiation monitor reading >
(Note 2) AU
> Table A-1 column "GE" for.::: 15 Table A-1 column "SAE" for.::: 15 min. (Note 1) min. (Note 1) AA 1.2 [!
AG 1.2 AS 1.2 4 5 6 I DEF I An}
colt 1 2 3 4 5 6 DEF I 1 I 2 I3 I4 5 6 I DEF I Any valid liquid monitor reading > Table A-1 column "Alert" for .::: 15 min. (Note 2) AU Dose assessment using actual Dose assessment using actual AA 1.3 [i meteorology indicates doses meteorology indicates doses > 100 4 5 6 DEF Cor
> 1000 mRem TEDE or> 5000 mRem TEDE or> 500 mRem thyroid liqu CDE at or beyond the site boundary Confirmed sample analyses for gaseous rele mRem thyroid CDE at or beyond the site boundary. or liquid releases indicate concentrations (O[
AS 1.3 or release rates > 200 x Technical AG 1.3 Specification (ODCM) limits for.::: 15 min.
I 1 I 2 I 3 I 4 I 5 I 6 I DEF I (NOTE 2) 1 2 3 4 5 6 DEF Field survey indicates closed window Field survey results indicate dose rate> 100 mRem/hr. that is closed window dose rates > 1000 expected to continue for.::: 1 hr at or mRem/hr. expected to continue for beyond the site boundary
.::: 1 hr at or beyond the site OR boundary Field survey sample analysis OR indicates thyroid CDE of > 500 Anakyses of field survey samples mRem for 1 hr of inhalation at or indicate thyroid CDE of > 5000 beyond the site boundary mRem for 1 hr of inhalation at or beyond the site boundary
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page
& Irradiated Fuel Events Damage to irradiated fuel or loss of water Un~
level (uncovering irradiated fuel outside indi the Reactor Vessel) that causes a valid in ti high alarm on any of the following can radiation monitors:
- R-2/R? Vapor Containment Area Monitors Vali
- R-5 Fuel Storage Bldg. Area an~
Monitors
-R-42 [R-12] VC Gas Activity - R:
-R-25/R-26 Vapor Containment High Radiation Area Monitors
- R-AA2.2 I 1 I 2 I3 4 5 6 I DEF I - R:
AU A water level drop in the reactor cavity, SFP or fuel transfer canal that will result in 11 irradiated fuel becoming uncovered L Un~
rea1 fact
- N1 higl exc
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING
-: :;: :, Entergy PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "A" Abnormal Rad Release/ Rad Effluent 3 AA3.1 CR/CAS 3 4 5 6 I DEF I Radiation Dose rates > 15 mRem/hr in areas requiring continuous occupancy to maintain plant safety functions:
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels TABLE A-1 EFFLUENT MONITOR CLASSIFICATION THRESHOLDS Gaseous R-27 7.5 E+07 µCi/sec 7.5 E+06 µCi/sec 1.4 E+06 µCi/sec (2.3 E+OO µCi/cc) (2.3 E-01 µCi/cc) (4.2 E-02 µCi/cc)
R-44 [14] N/A N/A 4.2 E-02 µCi/cc Liquid R-54 [18] N/A N/A 4.0E-02 µCi/cc R-49 [19] N/A N/A 5.8E-02 µCi/cc
,~~-Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page IP-EP-120 9.1 - Emergency Action Levels CATEGORY "H" HAZARDS 1 HA 1.1 HU 1.1 Natural & I 1 I 2 3 4 5 6 I DEF I I 1 I2 Destructive Two or more annunciators are lit on the Seismic E Phenomena Peak Shock Annunciator panel, one of following:
which is red
- Earthqu AND Control R Strong Motion Event Indicator is lit
- Unit 3 "~
AND (Panel Earthquake confirmed by any of the Annunc following:
- Earthquake felt in plant by a consensus of - National Control Room Operators (Note 4
- National Earthquake Information Center (Note 4)
- Control Room indication of degraded performance of systems required for the safe shutdown of the plant HA 1.2 HU 1.2 I 1 I 2 3 4 I 5 I 6 I DEF I I1 I2 Tornado striking or sustained high winds Tornado:
> 90 mph (40 m/sec) resulting in EITHER: boundary Visible damage to any Table H-1 plant OR structures containing safety systems or components Sustainec OR
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "H" HAZARDS 1 HA 1.2 (cont.)
Natural & Control Room indication of degraded Destructive performance of safety systems Phenomena (continued) HA 1.3 HI I 1 I 2 3 4 5 6 / DEF
[
Vehicle crash resulting in Either:
Visible damage to any Table H-1 plant structures containing safety systems or TL components C,
OR 01 Control Room indication of degraded performance of safety systems D,
HA 1.4 HI I 1 I 2 3 4 5 6 / DEF Turbine failure-generated projectiles [
resulting in Either: Fl1 Visible damage to or penetration of any ha rel Table H-1 area containing safety systems cu or components OR Control Room indication of degraded performance of safety systems
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels HA 1.5 Natural &
Destructive I 1 I 2 I 3 I 4 I 5 I 6 I DEF Phenomena Flooding in any Table H-1 area resulting in Either:
An electrical shock hazard that precludes necessary access to operate or monitor safety equipment OR Control room indication of degraded pertormance of safety systems HA 1.6 HI
[
/ 1 / 2 / 3 / 4 / 5 / 6 I DEF /
Ri River Water Level > 15 ft. (0MSL) (Q OR 0 Low Service Water Bay (Intake SE Structure) level resulting in a loss of St service water flow (!2
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels Table H-1 Safe Shutdown Areas
- Control Building and associated Electrical Tunnels and Battery Rooms
- Service Water Pump Structure and Valve Pits
- Fuel Storage Building
- Primary Auxiliary Building / Fan House
- Vapor Containment Building
- EOG Buildings
- Auxiliary Feed Pump Building
- Condensate Storage Tank
- Refueling Water Storage Tank
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 2 HA2.1 Fire or ! 1 ! 2 ! 3 ! 4 ! 5 ! 6 ! DEF Explosion Fire or explosion resulting in EITHER:
Visible damage to any Table H-1 area containing safety systems or components OR Control Room Indication of degraded performance of safety systems 3 HA3.1 Hazardous ! 1 ! 2 ! 3 ! 4 ! 5 ! 6 ! DEF Gas Access to any Table H-2 area is prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of systems required to maintain safe operations or safety shut down the reactor
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120
~- IMPLEMENTING
~*Entergy PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels Table H-2 Safe Shutdown Access Areas
- Control Building and associated Electrical Tunnels and Battery Rooms
- Service Water Pump Structure and Valve Pits
- Vapor Containment Building
- Primary Auxiliary Building/ Fan House
- Auxiliary Feed Pump Building
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING Entergy PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels 4 HG 4.1 HS 4.1 HA4.1 Security I1 I 2 I a I 4 I s I s I DEF I1 I 2 I 3 I 4 I 5 I 6 I DEF I1 I 2 I 3 I 4 I 5 I 6 I DEF A hostile action has occurred A hostile action is occurring or has A hostile action is occurring or has such that plant personnel are occurred within the Protected Area as occurred within the Owner Controlled unable to operate equipment reported by the Security Shift Area as reported by the Security Shift required to maintain safety Supervisor Supervisor functions OR OR A validated notification from NRC of an A hostile action has caused airliner attach threat within 30 minutes of failure of Spent Fuel Cooling the site Systems and imminent damage is likely 5 HS5.1 HA5.1 Control Room I1 I2 I3 I4 I5 I 6 I DEF I1 I2 I3 I 4 I 5 I 6 I DEF I Evacuation Control Room evacuation has been Control Room evacuation initiated initiated AND Control of the plant cannot be established within 15 minutes
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120
/
/
EMERGENCY PLAN IMPLEMENTING
~Entergy PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels 6 HG 6.1 HS 6.1 HA6.1 I-Judgment I 1 I 2 I aI 4 I sI 6 I DEF I1 I 2 I3 I4 I 5 I 6 I DEF I1 I 2 I 3 I 4 I 5 I 6 I DEF [
other conditions exist that in the Other conditions exist that in the other conditions exist that in the C judgment of the Emergency judgment of the Emergency Director judgment of the Emergency Director jl Director indicate that events are indicate that events are in progress or indicate that events are in progress or ir in progress or have occurred have occurred which involve EITHER: have occurred which involve EITHER: 0 which involve EITHER: p An actual or likely major failures of An actual or potential substantial Actual or imminent substantial plant functions needed for protection of degradation of the level of safety of the s core degradation or melting with the public plant s potential for loss of containment h OR OR n integrity Hostile action that results in intentional A security event that involves probable n OR damage or malicious acts; 1) toward life threatening risk to site personnel or u Hostile action that results in an site personnel or equipment that could damage to site equipment because of s actual loss of physical control of lead to the likely failure of or; 2) that hostile action the facility prevent effective access to equipment Any releases are expected to be limited Releases can be reasonably needed for the protection of the public to small fractions of the EPA Protective expected to exceed EPA ANY releases are not expected to Action Guideline exposure levels Protective Action Guideline result in exposure levels which exceed beyond the site boundary exposure levels (1 Rem TEDE EPA Protective Action Guidelines and 5 Rem thyroid COE) beyond exposure levels (1 Rem TEDE and 5 the site boundary Rem thyroid COE) beyond the site boundary
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN
-=:::=- Entergy IMPLEMENTING PROCEDURES REFERENCE USE Page 1 EU 1:
[IL Dama bound
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120
~
EMERGENCY PLAN IMPLEMENTING
- -= Ent(!f[!Y PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION 1 SG 1.1 SS 1.1 SA 1.1 Loss of AC I1 I2 I3 I4 1r:.. 1+*' hz:i~;\.I I 1 I 2 I 3 I 4 I I l~:d I I1 I2 I3 I4 I J <,~,;,r.;,, I Power Loss of all offsite and all onsite Loss of all offsite and all onsite AC AC power capability to 480 V AC power (Table S-1) to 480 V power (Table S-1) to 480 V safeguards buses (5A, 2A/3A, 6A) safeguards buses (5A, safeguards buses (5A, 2A/3A, 6A) reduced to a single power source 2A/3A,6A) for 2: 15 minutes (Note 3) (Table S-1) for 2:. 15 minutes (Note 3)
AND EITHER: such that any additional single failure Restoration of at least one would result in loss of all AC power tc safeguards bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> safeguard buses is not likely OR Actual or imminent conditions requiring entry into ORANGE or RED path on F-0.2, "CORE COOLING"
ENNIPEC
/'>"~. NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN .
~~1Entergy IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION 2
ATWS I 2 1~:m: : J: > I :*,d:> ** I 2 L...____J__----'--"----'~~=---"='-'-'--"
Criticality Failure of an automatic trip signal to Failure of an automatic trip signal to manual trip signals to reduce reduce power range < 5% reduce power range < 5%
power range < 5%
AND AND AND Manual trip actions taken at the Manual trip actions taken at the Actual or imminent conditions reactor control console are not reactor control console are successful requiring entry into EITHER:
successful RED path in F-0.2, CORE COOLING OR RED path in F-0.3, HEAT SINK 3
Inability to Reach Shutdown Conditions
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION 4
Inst. / Comm. 2 3 4 Loss of > approximately 75% of Unplanned loss of > approximately Control Room Overhead 75% of Control Room Overhead annunciators or Control Room annunciators or Control Room indicators Table S-3 associated with indicators Table S-3 associated with safety systems safety systems for?. 15 mi nut es (Note AND 3)
Any significant transient is in AND EITHER progress, (Table S-2) Any significant transient is in progress, AND (Table S-2)
Compensatory indications are OR unavailable Compensatory indications are unavailable
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION Site;AZrea SU 5.1
. Fuel Clad I1 I2 I Degradation
[Unit 3]: 1, Fuel Detec SU5.2 I1 I2 I Coolants.
> 60 µCi/g1 6 SU 6.1 Unidentifie leakage>
OR Identified le
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION 7 SS7.1 Loss of DC Power < 105 VDC bus voltage indications on all safety-related DC buses for ~ 15 minutes (Note 3)
ENNIPEC IP-EP-120 c:~
- !I..~.
EMERGENCY PLAN IMPLEMENTING NON-QUALITY RELATED PROCEDURE
~*Entergy PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels HOT CONDITIONS Table S - 1 Safeguards Bus AC Power Sources
.ON$1TE>i
-480 V EDG 21 - Unit Auxiliary transforr
-480 V EDG 22 - Station Auxiliary transl 2 -480 V EDG 23 - 13.8 KV gas turbine au
- Appendix "R" Diesel
- 480 V EDG 31 - Unit Auxiliary transforr
-480 V EDG 32 - Station Auxiliary transl 3 -480 V EDG 33 - 13W92 feeder
- - Appendix "R" Diesel - 13W93 feeder
- With86P or 86BU tripped all offsite power supplies must be considered as one pow
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels HOT CONDITIONS Table S - 2 Significant Transients
- Automatic turbine runback > 25% thermal reactor power
- Electrical load rejection > 25% full electrical load
- Safety injection activation
- Thermal power oscillations of > 10%
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN
-~-Entergy IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels HOT CONDITIONS Table S - 3 Safety System Indicators Reactivity Control RCS Inventory Reactor Trip Decay Heat Removal Fission Product Barriers
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels HOT CONDITIONS Table S - 4 Communications Systems
- \J,Yst~m *
- Q'risite ..
(rnten:,al)
',, . :~:~,;:,:*.~~\,;-;~ :~i ',\'c~z:~'c,'., ' .' *,'"**, ' ~
Plant Telephone System X )(
Plant Radio System X Page / Party System X Emergency Notification System )(
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING
~ Entergy PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels HOT CONDITIONS CATEGORY "F" FISSION PRODUCT BARRIERS 1 FG 1.1 FS 1.1 FA 1.1 Fission Product Barrier Loss of any two barriers Loss or potential loss of any two Any loss or any potential loss AND barriers (Table F-1) of either Fuel Clad or RCS Loss or potential loss of third (Table F-1) barrier (Table F-1)
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 Emergency Action Levels HOT CONDITIONS TABLE "F-1" FISSION PRODUCT BARRIER MATRIX FUEL CLADDING E3ARRIER<; CG
. (FC) . \\ <li<.
.. *:l DLOSS 0 POTENTIAL LOSS DLOSS OPOTENTIAL LOSS OLOS:
A.CSFST D D D D D
- 1. Core -Cooling 1. Core Cooling 1. Integrity- RED entry RED entry ORJ:,NGE entry conditions met conditions met conditions met OR OR Heat Sink- RED entry Heat Sink - RED entry conditions met and conditions met and heat sink is required heat sink is required
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING
--- Entergy PROCEDURES . REFERENCE USE Page 9.1 Emergency Action Levels HOT CONDITIONS TABLE "F-1" FISSION PRODUCT BARRIER MATRIX DLOSS OPOTENTIAL LOSS DLOSS OPOTENTIAL LOSS DLOSS B. Core D D D D D ExitTCs
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 Emergency Action Levels HOT CONDITIONS TABLE "F-1" FISSION PRODUCT BARRIER MATRIX
, **<<*; FuefCladciing 13arrie; . *React~m,Cc>'olantSysttril '<! i' .
.,J<. i~<FC)(::.n . f" (~C§): . ,
DLOSS D POTENTIAL LOSS DLOSS DPOTENTIAL LOSS DLOS:
C.
D D Radiation
- 3. Containment 1. [Unit 2]
radiation monitor R-41 > 1.2E-5 R-25 or R-26 > µCi/cc or 17 R/hr R-42 > 1.02 E-2
µCi/cc
[Unit 3]
R-11 > 1.2E-5
µCi/cc or R-12 > 5.0E-2
µCi/cc
ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 9.1 - Emergency Action Levels HOT CONDITIONS TABLE "F-1" FISSION PRODUCT BARRIER MATRIX
.. * ... 1
.. **Con1 1
DLOSS DPOTENTIAL DLOSS D POTENTIAL LOSS DLOSS LOSS D. D D D D D 1. A Containrr Inventory
[Unit 2] < 41% resulting in a loss indicated greater than by a rapid unexpli
[Un it 3] < 33% of RCS sub- 87 gpm drop in Containm1 With no RCPs cooling (
'., ., . . .... * , '* Cori .. (RC;~)y: .** . . * ** I OLOSS OPOTENTIAL LOSS OLOSS OPOTENTIAL LOSS DLOSS D. D 4. Primary-Inventory to-secondary (continued) leak rate > 10 gpm AND Un-isolable steam release from affected to the environment ENNIPEC NON-QUALITY RELATED PROCEDURE IP-EP-120- ,-
- ; ;* Entergy IMPLEMENTING PROCEDURES REFERENCE USE Page FJerc,~~~ftg,~~. ~i~~,,:\ *.*
- 3
- s~bj:~,i:i~~(
- Containment sumps
- CCW surge tank
- If an RCS heat removal system is in operation within this time frame and RCS temperature is being reduc applicable
- 480 V EOG 21
- Unit Auxiliary Transformer*
- 480 V EOG 22
- Station Auxiliary Transformer*
- 480 V EOG 23
- 13.8 KV Gas Turbine Auto Trans
- Appendix "R" Diesel 3
- 480 V EOG 31
- Unit Auxiliary Transformer
- 480 V EOG 32
- Station Auxiliary Transformer I
- With 86P or 86BU tripped, all offsite power supplies must be considered as one power supply .
- Containment Closure (Note 4) not established
- Containment hydrogen concentration ~ 4%
- Unplanned rise in containment pressure
- elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.
*t:;;:.:)j,*.**:.1 s 2