ML18162A101

From kanterella
Jump to navigation Jump to search
2 to IP-EP-120, Emergency Classification
ML18162A101
Person / Time
Site: Indian Point  Entergy icon.png
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)
v • d • e


Text

IPEC EMERGENCY PLAN DISTRIBUTION LIST Page 1 of 2 IP3 CONTROL ROOM DELIVERED BY DOCUMENTS IP3 53FT. CCR IP3 SHIFT MANAGER DELIVERED BY DOCUMENTS IP3 53FT. ELEVATION IP2 CONTROL ROOM DELIVERED BY DOCUMENTS IP2 53FT. CCR IPEC TSC DELIVERED BY DOCUMENTS IP2 53FT. ELEVATION IP2 SIMULATOR DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG.

IP2 SIMULATOR-CLASSROOM4 DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG.

IP2 SIMULATOR - CLASSROOM 5 DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG.

NRG RESIDENT INSPECTOR NRG IP2 88FT. ELEVATION DOC CONTROL DESK OFFSITE.

l.._ ___

NRG OFFSITE NRG OFFSITE

'.:TL:E.NORE TCfU~DA~E.'i' NEW YORK STATE OEM TED FISCH J

WEBSITE' '

  • Ne:'.nilAiL C0°PIE$f:,>i WESTCHESTER COUNTY OEM DENNIS DELBORGO OFFSITE ROCKLAND COUNTY FIRE AND NICHOLAS LONGO OFFSITE EMERGENCY SERVICES ORANGE COUNTY EMERGENCY SHANNON FISHER OFFSITE SERVICES CENTER PUTNAM COUNTY BUREAU OF KEN CLAIR OFFSITE EMERGENCY SERVICES 1 COPY OF ALL EP'S 1 COPY OF ALL EP'S 1 COPY OF ALL EP'S 1 COPY OF ALL EP'S 1 COPY OF ALL EP'S 1 COPY OF ALL EP'S 3 COPIES OF ALL EP'S EXCEPT E-PLAN 1 COPY OF ALL EP'S 1 COPY OF ALL EP'S AND GENERAt RECORDS EXCEPT IP-EP-115 1 COPY OF ALL EP'S AND GENERAL RECORDS EXCEPT IP-EP-115 1 COPY OF ALL EP'S AND GENERAL RECORDS EXCEPT IP-EP-115 1 COPYOFTHE FOLLOWING:

E-PLAN, IP-EP-115, 120, 210,220,230,250,310, 320,340,360,410,420, 430, 620 & IP-1055 1 COPY OF E-PLAN, IP-EP-310 & 340 1 COPY OF E-PLAN, IP-EP-310 & 340 1 COPY OF E-PLAN, IP-EP-310 & 340 1 COPY OF E-PLAN, IP-EP-310 & 340

  • THE FOLLOWING LOCATIONS ARE *ELECTRONIC DISTRIBUTIONS* )-J..-lJ5
Jf-L

--- Entergy Indian Point Energy Center Document Control 450 Broadway Buchanan, NY 10511 TO:

DISTRIBUTION CONTROLLED DOCUMENT TRANSMITTAL FROM: IPEC DOCUMENT CONTROL -- 3RD FLOOR ADMIN BLDG DATE: May 24, 2018 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 Please review to verify receipt, incorporate the,document(s) into your controlled document file, properly disposition superseded, voided, or inactive document(s).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:

IP-EP-120 REV.12

--*----------1 I EFFECTIVE I l MAY 3 0 2018. I I

I

.I fi"""'\\j\\..,,,..E--

I l

L\\r'\\ !

I 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?

rs this activity fully bounded by an NRC approved 10 CFR 50.90 submittal or Alert and Notification System Design Report?

If YES, identify bounding source document number/approval reference and ensure the basis for concluding the source document fully bounds the proposed change is documented below:

Justification:

0 Bounding document attached (optional)

Part m. Applicability of Other Regulatory Change Control Processes DYES 50.54(q)(3)

Evaluation is NOT required.

Enter justification below and complete Part VI.

!?:>!NO Ccn!inoe to next 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 ls this activity an editorial or typographical change such as formatting, paragraph numbering, spelling, or punctuation that does not change intent?

Justification:

1. This change corrects an incorrect URL address for the National Earthquake Center and does not change the intent of the procedure.
2. This change replaces a voided procedure reference wilh the procedure number that replaced ii.

12:SJYES SO.S4(q)(l)

!:.valuation is NOT required.

Enter justification and continue to next part or complete Part V!as umilicabh:.

UNO Continue to next part EN-EP-305 REV 6

~:WM.A:'.

~=~

r~

~

~~~~~

~'W'W"'

=*

10 CfR 50.S4(Q)(3) SCRE!i::NSNG

~----

Number: IP-EP-120 12 Eqa!ipme11t/F~emtyJOther: lm:Uan Poir>>t Energy Cantr (!PEC) iit!e:

Classification 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 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]

0 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)

Casey Karsten Sr. Emergency Planner

{Optional) Reviewer Name (Print}

Reviewer Name (Print) 7fmothy F. Garvey Nuclear EP Project Manager Reviewer Signature Reviewer Signature

,~

Approver Name (Prinl)

Approver Signature Frank J. Mitchell L1,:y ~Mikr Gr Fr.,,,k. m;~t-t!I At klw.....

Manager, Emergency Planning or des1gnee

  • O&;te:

Date:

IPEC IMPLEMENTING PROCEDURE PREPARATION, REVIEW, AND APPROVAL IP-SMM-AD-102 Rev:

Page 35 of 43 A1iACHMENi 10.2 IPEC PROCEDURE REVIEW AND APPROVAL Procedure

Title:

Emergency Classification Procedure No.

!P-EP-120 Existing Rev:

11 NewRev:

12 DRN/EC No:

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.

0 EDITORIAL Temporary Procedure Change 0 GENERAL REVISION 0

ADVANCE Temporary Procedure Change 0 PARTIAL REVISION 0 EDITORIAL REVISION Unit 2 Procedure No, 0

CONDITIONAL Temporary Procedure Change 0 VOID PROCEDURE Terminating Condltlon:

0 SUPERSEDED I

Unit 3 Procedure No:

Cl RAPID REVlSiON Document in Microsoft Wore!:

D V01D DRN/TPC No(s):

!El Yes D No 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}

1. D Technical Reviewer:

/\\//A

2. 0
3. llil

____...._"""-='--------------------------

(Print Name/ Slgnatul'E!I Date}

Cross-Disciplinary Reviewers:

Dept Reviewer:

Dept:

Reviewer:

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

~

reduction in the level of nuclear safety

~

voiding or canceling of a procedure, unless requirements are incorporated into another procedure or tin, need for the procedure was e!imlnated

5. 0 On-Shift Shift Manager/CRS:

{Print Name/ Sigrmturel Date)

NO change to less restrictive acceptance criteria NO change to steps previously identified as commitment steps NO deviation from the Quality Assurance Program Manual NO change that may result In deviations from Technical Specifications, FSAR. plant design requirements,

6. 0 User Validation: User:
7. D Special Handling Requirements Understood:

(Print Name/ Signature/ Date)

Validator:

(Print Name/ Signature£ Date)

~Enleroy b

IPEC EMERGENCY PLAN ADMINISTRATIVE PROCEDURES NON-QUALITY RELATED PROCEDURE:.1 Emergency Planning Document Change Checklist Form Revision 10 (All sections must be completed, NIA or place a check on the line where applicable)

Section 1 Doc/Procedure Type:

AdministrativeD EPLAN 0 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 181 NIA D
b.

EN-FAP-OM-023 0

NIA !8J

c.

!P-SMM-AD-102

!8J NIA 0

d.

OSRC O

NIA !8J

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: __

6.

Copy of EPDCC placed in EP file: D NIA D Date: __

N/AO

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

I Ntimb(!r

1.
2.
3.
4.
5.
6.
7.

L Revision Matrix IP-EP-420 "Use of Potassh.1m Iodide Indian Point Personnel Durin an Emergency" Revision 6 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 Section 5.6.1 personnel in the GSB and EEC.

personnel in the GSB/EEC..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 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.. 3 Sheet 1 of 2 How does potassium iodide work?

How does Kl work?

Question#2 The table below shows the smallest Ki dose that The table on the next page shows the smallest Kl different age groups can lake which will protect the dose that different age groups can take which will 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.3 Heallh Commissioner says that. in an emergency, it is the State Health Commissioner says that, in an Sheet i of 2 safe for children at school or day care centers to take emergency, it is safe for clliklren at school or day Question # 10 the whole pill. For children or babies who c.armot take care centers to take the whole pill. ifs better for pills, parents and caregivers can cut or crush the pill to children under 12 years old to take the 65-mg pill, but make lower doses. For example, if 130 mg pill were it is safe to take the *rno~mg pill if that is the only one dissolved in 8 ounces of juice or other liquid, on 01..mce you have. For children or babies wlio cannot take would contain 16 mg of Kl.

pills, paremts and caregivers can cut or crush the pill to make lower doses, or ~ive the liouid form of KL.3 Deleted the old table and inserted a new table Sheet2 of2 Old Table Question # 10 consistent with lha NYS Fact Sheet.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 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..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 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.

8.

9 10.'

L Revision Matrix IP-EP-420 "Use of Potassium fodidia Indian Point 1.r11:>1fC:,l"U"!Hn,~.3 The manufacturers say Kl stays 'fresh' for 3 - 5 years.

Sheet2 of2 If you keep it in a dry dark and cool place, il should last Question # 13 for manv vears.

lt is not widel;',,vailable in drugstores yet, but since it is.3 not a prescription drug, you can buy it over the internet.

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 NO reduction in the level of m..rclear safety NO voiding or canceling of a procedure, urdess requlrements are incorporated into another procedure or lhe need for the procedure was eliminated

5. D On-Shift Shift Manager/CRS:

{ P rl n t.Name/ Signature! Dat@l NO change to less restrictive acceptance crideriim NO change to steps previously identified as commitment steps

.t:!Q deviation from the Quality Assurance Program Mam.1ai NO change that may result in devieticms from Tec:hnlaii Speciflaitions, FSAR, plant design r@qulrements,

6. 0 User Validation: User:
7. 0 Special Handling Requirements Understood:

(Print Name/ !!1,111at1.1ffl/ Oat}

Validator:

-= Entergy iPEC EMERGENCY PLAN ADMINISTRATIVE PROCEDURES NON-QUALITY RELATED PROCEDURE lEFl::REl~CE USE AttachmeITTJt 9.1 1

Emerg~ncy Planning Document Change Checklist Form Revision 'iO of 1

{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 f8]

NIA D

b.

EN-FAP-OM-023 f8]

NIA 0

c.

IP-SMM-AD-102 18]

NIA 0

d.

OSRC O

NIA iE1

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: *--

6. Copy of EPDCC placed in EP file: D NIA D 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 NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 12 ENNIPEC EMERGENCY PLAN

~ Entergy 1MPLEMENr1NG REFERENCE Use Page 1

of 49 PROCEDURES L.___ _ _ _

1,_ _ _

.1---_ _

EmergenC?Y Classification Prepared by:

Casey N. Karsten c--=-~

Table A-1 column "GE" for.::: 15 min. (Note 1)

AG 1.2 1

2 3

4 5

6 DEF Dose assessment using actual meteorology indicates doses

> 1000 mRem TEDE or> 5000 mRem thyroid CDE at or beyond the site boundary.

AG 1.3 1

2 3

4 5

6 DEF Field survey results indicate closed window dose rates > 1000 mRem/hr. expected to continue for

.::: 1 hr at or beyond the site boundary OR Anakyses of field survey samples indicate thyroid CDE of > 5000 mRem for 1 hr of inhalation at or beyond the site boundary NON-QUALITY RELATED PROCEDURE REFERENCE USE Page IP-EP-120 9.1 - Emergency Action Levels CATEGORY "A" Abnormal Rad Release I Rad Effluent I 1 I 2 I 3 I 4 5

6 I DEF I Any valid radiation monitor reading >

Table A-1 column "SAE" for.::: 15 min. (Note 1)

AS 1.2 I 1 I 2 I 3 I 4 5

6 I DEF I Dose assessment using actual meteorology indicates doses > 100 mRem TEDE or> 500 mRem thyroid CDE at or beyond the site boundary AS 1.3 I 1 I 2 I 3 I 4 I 5 I 6 I DEF I Field survey indicates closed window dose rate> 100 mRem/hr. that is expected to continue for.::: 1 hr at or beyond the site boundary OR Field survey sample analysis indicates thyroid CDE of > 500 mRem for 1 hr of inhalation at or beyond the site boundary 4

5 6 I DEF I Any valid gaseous monitor reading >

Table A-1 column "Alert" for.::: 15 min.

(Note 2)

AA 1.2 4

5 6 I DEF I Any valid liquid monitor reading > Table A-1 column "Alert" for.::: 15 min. (Note 2)

AA 1.3 4

5 6

DEF Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates > 200 x Technical Specification (ODCM) limits for.::: 15 min.

(NOTE 2)

AU

[!

An}

A-1 AU

[!

An}

colt AU

[i Cor liqu rele (O[

2.

Onsite Rad Conditions

& Irradiated Fuel Events ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE AA2.1 IP-EP-120 Page I 1 I 2 I 3 4

5 6

DEF Damage to irradiated fuel or loss of water level (uncovering irradiated fuel outside the Reactor Vessel) that causes a valid high alarm on any of the following radiation monitors:

- R-2/R?

Vapor Containment Area Monitors

- R-5 Monitors Fuel Storage Bldg. Area

-R-42 [R-12] VC Gas Activity

-R-25/R-26 Vapor Containment High Radiation Area Monitors AA2.2 I 1 I 2 I 3 4

5 6 I DEF I AU Un~

indi in ti can ANI Vali an~

- R:

- R-

- 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

-:::;:::, Entergy 3

CR/CAS Radiation ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "A" Abnormal Rad Release/ Rad Effluent AA3.1 3

4 5

IP-EP-120 6 I DEF I Dose rates > 15 mRem/hr in areas requiring continuous occupancy to maintain plant safety functions:

Control Room

[R-1 J OR CAS

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE IP-EP-120 Page 9.1 - Emergency Action Levels TABLE A-1 EFFLUENT MONITOR CLASSIFICATION THRESHOLDS Gaseous R-27 7.5 E+07 µCi/sec (2.3 E+OO µCi/cc)

R-44 [14]

N/A Liquid R-54 [18]

N/A R-49 [19]

N/A 7.5 E+06 µCi/sec (2.3 E-01 µCi/cc)

N/A N/A N/A 1.4 E+06 µCi/sec (4.2 E-02 µCi/cc) 4.2 E-02 µCi/cc 4.0E-02 µCi/cc 5.8E-02 µCi/cc

1

,~

~-Entergy Natural &

Destructive Phenomena ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE IP-EP-120 9.1 - Emergency Action Levels CATEGORY "H" HAZARDS Page HA 1.1 I 1 I 2 3

4 5

HU 1.1 6 I DEF I I 1 I 2 Two or more annunciators are lit on the Peak Shock Annunciator panel, one of which is red AND Strong Motion Event Indicator is lit AND Earthquake confirmed by any of the following:

- Earthquake felt in plant by a consensus of Control Room Operators

- 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 Seismic E following:

- Earthqu Control R

- Unit 3 "~

(Panel Annunc

- National (Note 4 HU 1.2 I 1 I 2 3

4 I 5 I 6 I DEF I I 1 I 2 Tornado striking or sustained high winds

> 90 mph (40 m/sec) resulting in EITHER:

Visible damage to any Table H-1 plant structures containing safety systems or components OR Tornado:

boundary OR Sustainec

1 Natural &

Destructive Phenomena (continued)

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels CATEGORY "H" HAZARDS HA 1.2 (cont.)

IP-EP-120 Page Control Room indication of degraded performance of safety systems HA 1.3 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 components OR Control Room indication of degraded performance of safety systems HA 1.4 I 1 I 2 3

4 5

6

/ DEF Turbine failure-generated projectiles resulting in Either:

Visible damage to or penetration of any Table H-1 area containing safety systems or components OR Control Room indication of degraded performance of safety systems HI

[

TL C,

01 D,

HI

[

Fl1 ha rel cu

Natural &

Destructive Phenomena ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels HA 1.5 IP-EP-120 Page I 1 I 2 I 3 I 4 I 5 I 6 I DEF 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

/ 1 / 2

/ 3 / 4 / 5

/ 6 I DEF /

River Water Level > 15 ft. (0MSL)

OR Low Service Water Bay (Intake Structure) level resulting in a loss of service water flow HI

[

Ri (Q

0 SE St

(!2

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels Table H-1 Safe Shutdown Areas IP-EP-120 Page

- 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

2 Fire or Explosion 3

Hazardous Gas ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE IP-EP-120 REFERENCE USE Page HA2.1

! 1 ! 2

! 3

! 4

! 5

! 6

! DEF 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 HA3.1

! 1 ! 2

! 3

! 4

! 5

! 6

! DEF 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

/~

~-

~*Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page 9.1 - Emergency Action Levels Table H-2 Safe Shutdown Access Areas IP-EP-120

- 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

Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES 4

Security 5

Control Room Evacuation HG 4.1 I 1 I 2 I a I 4 I s I s I DEF A hostile action has occurred such that plant personnel are unable to operate equipment required to maintain safety functions OR A hostile action has caused failure of Spent Fuel Cooling Systems and imminent damage is likely NON-QUALITY RELATED PROCEDURE REFERENCE USE Page IP-EP-120 9.1 - Emergency Action Levels HS 4.1 I 1 I 2 I 3 I 4 I 5 I 6 I DEF A hostile action is occurring or has occurred within the Protected Area as reported by the Security Shift Supervisor HS5.1 I 1 I 2 I 3 I 4 I 5 I 6 I DEF Control Room evacuation has been initiated AND Control of the plant cannot be established within 15 minutes HA4.1 I 1 I 2 I 3 I 4 I 5 I 6 I DEF A hostile action is occurring or has occurred within the Owner Controlled Area as reported by the Security Shift Supervisor OR A validated notification from NRC of an airliner attach threat within 30 minutes of the site HA5.1 I 1 I 2 I 3 I 4 I 5 I 6 I DEF I Control Room evacuation initiated

/ /

~Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES 6

Judgment HG 6.1 I 1 I 2 I a I 4 I s I 6 I DEF other conditions exist that in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve EITHER:

Actual or imminent substantial core degradation or melting with potential for loss of containment integrity OR Hostile action that results in an actual loss of physical control of the facility Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels (1 Rem TEDE and 5 Rem thyroid COE) beyond the site boundary NON-QUALITY RELATED PROCEDURE REFERENCE USE Page IP-EP-120 9.1 - Emergency Action Levels HS 6.1 I 1 I 2 I 3 I 4 I 5 I 6 I DEF Other conditions exist that in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve EITHER:

An actual or likely major failures of plant functions needed for protection of the public OR Hostile action that results in intentional damage or malicious acts; 1) toward site personnel or equipment that could lead to the likely failure of or; 2) that prevent effective access to equipment needed for the protection of the public ANY releases are not expected to result in exposure levels which exceed EPA Protective Action Guidelines exposure levels (1 Rem TEDE and 5 Rem thyroid COE) beyond the site boundary HA6.1 I 1 I 2 I 3 I 4 I 5 I 6 I DEF other conditions exist that in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve EITHER:

An actual or potential substantial degradation of the level of safety of the plant OR A security event that involves probable life threatening risk to site personnel or damage to site equipment because of hostile action Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels beyond the site boundary I-

[

C jl ir 0

p s

s h

n n

u s

-=:::=-Entergy 1

ISFSI ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page IP-EP-120 EU 1:

[IL Dama bound

IP-EP-120

~

  • -= Ent(!f[!Y ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page 1

Loss of AC Power 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION SG 1.1 SS 1.1 SA 1.1 I 1 I 2 I 3 I 4 1r:.. 1+*' hz:i~;\\.I I 1 I 2 I 3 I 4 I I l~:d I I 1 I 2 I 3 I 4 I J <,~,;,r.;,, I 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, 2A/3A,6A)

AND EITHER:

Restoration of at least one safeguards bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is not likely OR Actual or imminent conditions requiring entry into ORANGE or RED path on F-0.2, "CORE COOLING" safeguards buses (5A, 2A/3A, 6A) for 2: 15 minutes (Note 3) reduced to a single power source (Table S-1) for 2:. 15 minutes (Note 3) such that any additional single failure would result in loss of all AC power tc safeguard buses

/'>"~.

~~1Entergy ENNIPEC EMERGENCY PLAN.

IMPLEMENTING PROCEDURES 2

ATWS Criticality 3

Inability to Reach Shutdown Conditions manual trip signals to reduce power range < 5%

AND Actual or imminent conditions requiring entry into EITHER:

RED path in F-0.2, CORE COOLING OR RED path in F-0.3, HEAT SINK NON-QUALITY RELATED PROCEDURE REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION IP-EP-120 I 2 1~:m::: J: > I :*,d:> *

  • I L...____J__

2 ----'--"----'~~=---"='-'-'--"

Failure of an automatic trip signal to Failure of an automatic trip signal to reduce power range < 5%

reduce power range < 5%

AND AND Manual trip actions taken at the reactor control console are not successful Manual trip actions taken at the reactor control console are successful

4 Inst. / Comm.

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION 2

3 4

IP-EP-120 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

. Fuel Clad Degradation 6

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION Site;AZrea IP-EP-120 SU 5.1 I 1 I 2 I

[Unit 3]: 1, Fuel Detec SU5.2 I 1 I 2 I Coolants.

> 60 µCi/g1 SU 6.1 Unidentifie leakage>

OR Identified le

7 Loss of DC Power ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "S" SYSTEM MALFUNCTION SS7.1

< 1 05 VDC bus voltage indications on all safety-related DC buses for ~ 15 minutes (Note 3)

IP-EP-120

c:~

!I..~.

~*Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES 2

3 NON-QUALITY RELATED PROCEDURE REFERENCE USE Page IP-EP-120 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

-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

-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 EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels HOT CONDITIONS Table S - 2 Significant Transients Page

- Automatic turbine runback > 25% thermal reactor power

- Electrical load rejection > 25% full electrical load

- Reactor Trip

- Safety injection activation

- Thermal power oscillations of > 10%

IP-EP-120

-~-Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels HOT CONDITIONS Page Table S - 3 Safety System Indicators Reactivity Control RCS Inventory Reactor Trip Decay Heat Removal Fission Product Barriers IP-EP-120

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE IP-EP-120 Page 9.1 - Emergency Action Levels HOT CONDITIONS Table S - 4 Communications Systems

\\J,Yst~m

',,.. :~:~,;:,:*.~~\\,;-;~ :~i

',\\'c~z:~'c,'.,

Plant Telephone System Plant Radio System Page / Party System Emergency Notification System

  • :Q'risite (rnten:,al)

~

X X

X

)(

)(

~ Entergy 1

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES FG 1.1 NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels HOT CONDITIONS Page CATEGORY "F" FISSION PRODUCT BARRIERS FS 1.1 FA 1.1 IP-EP-120 Fission Product Barrier Loss of any two barriers AND Loss or potential loss of any two barriers (Table F-1)

Any loss or any potential loss of either Fuel Clad or RCS (Table F-1)

Loss or potential loss of third barrier (Table F-1)

A.CSFST ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 Emergency Action Levels HOT CONDITIONS Page TABLE "F-1" FISSION PRODUCT BARRIER MATRIX FUEL CLADDING E3ARRIER<;

. (FC)

\\\\ <li<.

DLOSS 0 POTENTIAL LOSS DLOSS OPOTENTIAL LOSS D

D D

D IP-EP-120 CG

... * :l OLOS:

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

IP-EP-120

--- Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE

. REFERENCE USE Page DLOSS B. Core D

ExitTCs

2. Core exit TCs>

1,200° F 9.1 Emergency Action Levels HOT CONDITIONS TABLE "F-1" FISSION PRODUCT BARRIER MATRIX OPOTENTIAL LOSS DLOSS OPOTENTIAL LOSS DLOSS D

D D

D

2. Core exit TCs

[Unit 2] > 700° F

[Unit 3] > 715° F

C.

Radiation ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 Emergency Action Levels HOT CONDITIONS IP-EP-120 Page TABLE "F-1" FISSION PRODUCT BARRIER MATRIX

, **<<*; FuefCladciing 13arrie;

.,J<. i~<FC)(::.n DLOSS D

3. Containment radiation monitor R-25 or R-26 >

17 R/hr D POTENTIAL LOSS

. *React~m,Cc>'olantSysttril '<! i'.

. f" (~C§):.

DLOSS D

1. [Unit 2]

R-41 > 1.2E-5

µCi/cc or 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 DPOTENTIAL LOSS DLOS:

D.

Inventory ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES DLOSS DPOTENTIAL LOSS D

D

3. RVLIS

[Unit 2] < 41%

[Un it 3] < 33%

With no RCPs running NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels HOT CONDITIONS IP-EP-120 Page TABLE "F-1" FISSION PRODUCT BARRIER MATRIX DLOSS D

2. RCS leak rate resulting in a loss of RCS sub-cooling ( 10 gpm AND Un-isolable steam release from affected SG to the environment
  • ,-
    :;;;* Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE E. Other F.

udgment FJerc,~~~ftg,~~.. ~i~~,,:\\ *.*

DLOSS D 4. Primary coolant activity

> 300 µCi/gm 1-131 dose equivalent D 5. ANY condition in the opinion of the Emergency Director that indicates loss of the Fuel Clad barrier

'(FC)

DPOTENTIAL LOSS D 4. ANY condition in the opinion of the Emergency Director that indicates potential loss of the Fuel Clad barrier DLOSS 0 4. ANY condition in the opinion of the Emergency Director that indicates loss of the RCS barrier DPOTENTIAL LOSS D 3. ANY condition in the opinion of the Emergency Director that indicates potential loss of the RCS barrier IP-EP-120 Page DLOSS D 5. Inability to iso all valves in any one AND Direct downstream pathway to the environment exists; Containment isolati<

signal D 6. ANY conditior the opinion of the Emergency Directo1 indicates loss of the Containment barrie1

-=-Entergy 2

3 ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE 0-400 401 -800 801 -1200 1201 - 2500

< 1000 1000-1900

> 1900 REFERENCE USE 9.1 - Emergency Action Levels HOT CONDITIONS Table "F-2" RCS Sub-cooling 52 36 23 19 40 40 40 IP-EP-120 Page

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels HOT CONDITIONS IP-EP-120 Page Table "F-3" Minimum Containment Cooling Systems FCUs

<3 3

5 Spray Pu11 2

1 0

ENN IPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels NOTES HOT CONDITIONS:

IP-EP-120 Page NOTE 1: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as.soon as it is determined that the condition will likely exceed the applicable time. IF dose assessment results are available, THEN declaration should be based on dose assessment instead of radiation monitor values. (See EAL AS1.2/AG1.2) Do not delay declaration awaiting dose assessment results.

NOTE 2: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined the release duration has exceeded, or will likely exceed, the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.

NOTE 3: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

NOTE 4: The National Earthquake Information Center (NEIC) can be contacted by calling (303) 273-8500 to confirm recent seismic activity in the vicinity of IPEC. Provide the analyst with the following IPEC coordinates: 41° 0 15' 55" north latitude, 73° 0 57' 08" west longitude.

Alternatively go to the USGS NEIC website: http://earthguake.usgs.gov f

NOTE 5: Not applicable to this chart.

Revision 12

~

~

-::::::* Entergy 1

Loss of AC Power ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE IP-EP-120 REFERENCE USE Page 9.1 - Emergency Action Levels CATEGORY "C" COLD SHUT DOWN/REFUEL SYSTEM MALFUNCTION CA 1.1 l:.*~;J~{tk':+;:*:J, J,' L<*l s I s I DEF Loss of all off site and all onsite AC power (Table C-4) to 480V safeguards buses (5A, 2A/3A, 6A) for 2:. 15 minutes. (Note 3)

s~bj:~,i:i~~(

2 RPV Level ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels IP-EP-120 Page CATEGORY "C" COLD SHUT DOWN/REFUEL SYSTEM MALFUNCTION CG 2.1 l>.'.C':[::,fN <

'.1 **.::<\\I s I s I I Reactor vessel level < top of active fuel (57' 9.6" elev.- 56%

on RVLIS) for~ 30 minutes (Note 3)

AND Any Containment Challenge indication, (Table C-5)

CG2.2 v

~i~:,,)~Zh~,~: *.;J ;:.*::;.1 5 1 6 w~\\* 1 Reactor vessel level cannot be monitored for~ 30 minutes with core uncovery indicated by ANY of the following (Note 3)

- Containment High Range Radiation Monitor reading upscale

- Unexplained rise in any Table C-1 sump/tank level

- Erratic Source Range Monitor indication AND Any Containment Challenge indication, Table C-5 cs 2.1 rw;,:'J.. j.:.:*:1** :**:1 5 I 6 1*/fE~}I With Containment Closure (Note 5) not established, reactor vessel level < 6" below the bottom of the RCS hot leg (59' 10.8" elev.

- RVLIS 60.8%)

CS2.2 1

2~~~*.j)t\\*t:;;:.:)j,*.**:.1 s I s I * 'I With Containment Closure (Note 5) established, reactor vessel level< top of active fuel (57' 9.6" elev. 56 % on RVLIS)

CS2.3

I
".:r:: lPi, 1 s I s I : I Reactor vessel level cannot be monitored for~ 30 minutes (Note 3) with a loss of inventory as indicated by any of the following:

- Containment High Range Radiation Monitor reading upscale

- Unexplained rise in any Table C1 sump/tank level

- Erratic Source Range Monitor indication CA2.1 I :rr:1:::*,1:~;;,**::.j;;l\\':':::.1 s I s l:.":i::I Reactor vessel level< bottom of the RCS hot leg (60' 4.8" elev.

- RVLIS 62%)

OR Reactor vessel level cannot be monitored for~ 15 minutes (Note 3) with unexplained rise in any Table C-1 sump/tank level

3 RCS Temperature 4

Communications ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels IP-EP-120 Page CATEGORY "C" COLD SHUT DOWN/ REFUEL SYSEMT MALFUNCTION CA3.1 k t:fl: 't!;;,k ~~~g:;

11 s I s I ' ;I ANY unplanned event resulting in RCS temperature> 200° F for

> Table C-3 duration OR RCS pressure increase > 10 psig due to a loss of RCS cooling (not applicable to solid plant operations)

5 Inadvertent Criticality 6

Loss of DC Power ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels IP-EP-120 Page CATEGORY "C" COLD SHUT DOWN/REFUEL SYSTEM MALFUNCTION cu 5.1

[]TI Unplan rate ob instrurr cu 6.1 L21]

< 105.

all Te 125 \\J (Note

ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels COLD CONDITIONS Containment sumps CCW surge tank PRT RCDT IP-EP-120 Page

-~-Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES System Plant Telephone System Plant Radio System Page/Party System Emergency Notification System NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels COLD CONDITIONS Onsite (Internal)

X X

X IP-EP-120 Page Offsite (External X

~*Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES RCS Intact and not Reduced Inventory Not intact OR Reduced Inventory NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 -* Emergency Action Levels COLD CONDITIONS Containment Closure N/A Established Not Established IP-EP-120 Page Duri 60 Mi 20 Mi 0 Mi1

  • If an RCS heat removal system is in operation within this time frame and RCS temperature is being reduc applicable

I *

"- Entergy UNIT 2

3 ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE IP-EP-120 Page 9.1 - Emergency Action Levels COLD CONDITIONS Onsite Offsite

  • 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
  • 480 V EOG 31
  • Unit Auxiliary Transformer
  • 480 V EOG 32
  • Station Auxiliary Transformer
  • 480 V EOG 33
  • 13W92 Feeder
  • Appendix "R" Diesel
  • 13W93 Feeder
  • With 86P or 86BU tripped, all offsite power supplies must be considered as one power supply.

-,- Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES NON-QUALITY RELATED PROCEDURE REFERENCE USE 9.1 - Emergency Action Levels COLD CONDITIONS Containment Closure (Note 4) not established Containment hydrogen concentration ~ 4%

Unplanned rise in containment pressure IP-EP-120 Page

NON-QUALITY RELATED PROCEDURE IP-EP-120 Revision 12

~ Entergy ENNIPEC EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 49 of 49 T

9.1 - Emergency Action Levels NOTES COLD CONDITIONS:

Note 1:

The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time. IF dose asse~sment results are available, THEN declaration should be based on dose assessment instead of radiation monitor values. (See EAL AS1.2/AG1.2) Do not delay declaration awaiting dose assessment results.

Note 2:

The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed, the applicable time, in the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.

Note 3:

The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

Note 4:

The National Earthquake lnformati_on Center (NEIC) can be contacted by calling (303) 273-8500 to confirm recent seismic activity in the vicinity of IPEC. Provide the analyst with the following IPEC coordinates: 41 ° 15' 55" north latitude, 73° 57' 08" west longitude. Alternatively go to the USGS NEIC website: http://earthquake.usgs.gov Note 5:

The site specific procedurally defined actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under existing plant conditions. As applied to IPEC, Containment Closure exists when the requirements of Section 3.9.3 of Technical Specifications are met (all un-isolated flow paths are promptly closes and at least one door in each air lock is closed following an evacuation of containment).

Retrieved from "https://kanterella.com/w/index.php?title=ML18162A101&oldid=4982467"