RA-19-0368, Emergency Plan Revision 2019-004

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Emergency Plan Revision 2019-004
ML19252A758
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 09/09/2019
From: Burchfield J
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-19-0368
Download: ML19252A758 (8)
v • d • e


Text

( -, DUKE

~ ENERGY~ J. Ed Burchfield, Jr.

Vice President Oconee Nuclear Station Duke Energy ONO 1VP/ 7800 Rochester Hwy Seneca, SC 29672 RA-19-0368 864.873.3478 864.873.4208 September 9, 2019 10 CFR 50.54(q) Ed.Burchfield@duke-energy.com 10 CFR 72.44(f)

Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, Maryland 20852-2746

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, -270, and -287 Emergency Plan Revision 2019-004 Pursuant to 10 CFR 50.54(q), and 10 CFR 72.44(f), Duke Energy is submitting the attached summary of changes to the Oconee Nuclear Station (ONS) Emergency Plan which became effective September 9, 2019.

This revision has been evaluated in accordance with 10 CFR 50.54(q) and it was determined that the change did not reduce the effectiveness of the ONS Emergency Plan. The revised ONS Emergency Plan continues to meet the requirements of Appendix E to 10 CFR 50 and the planning standards of 10 CFR 50.47(b).

If there are any questions or concerns pertaining to this revision please call Sheila Dalton, Manager Nuclear Support Services, at 864-873-3657.

Sincerely, JCJ~J J. Ed Burchfield, Jr.

Vice President Oconee Nuclear Station Attachment Oconee Nuclear Station Emergency Plan 10 CFR 50.54(q) Summary of Changes Attachment 1

RA-19-0368 U. S. Nuclear Regulatory Commission September 9, 2019 Page2 xc: Ms. Laura Dudes Administrator, USNRC Region II Marquis One Tower 245 Peachtree Center., NE Suite 1200 Atlanta GA 30303-1257 Ms. Audrey Klett Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2738 Mr. Adam Ruh NRC Senior Resident Inspector (Acting)

Oconee Nuclear Station

Change Matrix ONS Emergency Plan Section B, P, App 5 Page I of 4 Rev 2019-004 Attachment to 50.54q CHANGE MATRIX

  1. Page Current Proposed Change Reason

/Section

1. p. B-6 7) OAC Support deleted combined OAC and The OAC Support position reports IT responsibilities deleted OAC to the Assistant Emergency for more efficient Support and Coordinator. Key responsibilities use of personnel re- include:

numbered

  • Monitor facility equipment remaining (e.g., computer, sections communications) for proper operation
  • Activate EROS or confirm EROS Operation
2. p. B-18 4) Admin Su1mort (Near Site deleted combined JIC) responsibilities for deleted The Admin Support position more efficient use Admin reports to the Logistics Lead. of personnel Support and Key responsibilities include:
  • Coordinate distribution of re-news releases, statements and numbered messages remaining
  • Prepare for facility activation sections (rooms, work area, equipment, etc.)
  • Provide administrative support for facility operation
  • Distribute fonns, reports, etc.

as needed

3. p. B-19 7) Registration Liaison (Near deleted combined Site JIC) responsibilities for deleted The Registration Liaison more efficient use Registration reports to the Logistics Lead. of personnel Liaison and Key responsibilities include:
  • Register personnel at the renumbered assigned location remaining
  • Monitor facility entrance sections areas
  • Prepare for facility activation (rooms, work area, equipment, etc.)
4. old p.8-25 Current combined OAC and Table B-1b IT responsibilities

Change Matrix ONS Emergency Plan Section B, P, App 5 Page 2 of 4 Rev 2019-004 Attachment to 50.54q CHANGE MATRIX

  1. Page Current Proposed Change Reason

/Section

'.\Ilnimum 1::: for more efficient Functional Area '-1njo1* Tasks Standard ERO Emergency Positions Staffin ~

~~ ~~

= =~ use of personnel Re, omce Administration Log Keepei _(~_ TS_C~) _ _ __

Allocation aml Lo_g Keep~r .~o_s*_c~

  • ) ___ _____,

A<hnin Log Kee

  • lEOF)

Facility Operation, OACjjup- 0_1t_ T_S_C ~- - -- - - - 1 IT_Sll£E_Ott (TSC-~ - - - - - -

new p.B-24 Proposed combined OAC and Table B-lb IT responsibilities FII.Rc1fonaL\rea llajor Tasb St:andard ERO E11:1u~eucy Po;iti1n1~

for more efficient R!!!iource Admiwsu-111100 Lo~ Keeee,r (F§f) use of personnel Al!oc.ation :!nll Lo~Keeee,r (O~)

Admin Log Keeper (EOF)

Se!'.I t es ?,.,~~el (EOF)

F3ciliry0pera!ions IT Support (TSiC)

D:!lta Coordm3t-or (EOF )

I

5. old p.B-26 combined OAC and new p.B-25 ,= IT responsibilities Fig. B-1 ' , for more efficient use of personnel
6. old p.B-29 Current combined Fig. B-4 responsibilities for more efficient use of personnel

Change Matrix ONS Emergency Plan Section B, P, App 5 Page 3 of 4 Rev 2019-004 Attachment to 50.54q CHANGE MATRIX

  1. Page Current Proposed Change Reason

/Section new p.B-28 Proposed combined Fig. B-4 responsibilities for more efficient use of personnel

7. App 5
  • Greenville Health System
  • Prisma Health (formerly Greenville Name change Health System)
8. App 5
  • Memorandum of deleted Incorporated in to Understanding (Joint State, County LOA's Information Center)
9. BS OMP 2-16 Shift Turnover eleted row not an implementing procedure.
10. J2 NSD-114 Site Assembly/Site deleted row superseded to J3 Evacuation RP /0/ A/1000/009 JS/J6 and RP /0/A/1000/010 adjusted remaining rows in table
11. 12 CSM 5.1 Emergency Response deleted row EMERGENCY Guidelines RESPONSE adjusted GUIDELINES remain ing SUPERSEDED by rows in table RP /0/ A/1000/009, Procedure for Site Assembly, RP /0/ A/1000/010, Procedure For Emergency Evacuation/

Relocation of Site

Change Matrix ONS Emergency Plan Section B, P, App 5 Page 4 of 4 Rev 2019-004 Attachment to 50.54q CHANGE MATRIX

  1. Page Current Proposed Change Reason

/Section Personnel, AD-EP-ALL-0106, ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER, AD-EP-ALL-0100, EMERGENCY

RESPONSE

ORGANIZATION (ERO)

Change Matrix ONS Emergency Plan, Rev 2019-004 Page l of 2 Attachment to 50.54q CHANGE MATRIX

  1. Page Current Proposed Change Reason

/Section

1. p. D-64 ATTACHMENT 1 Update ONS specific EAL Bases dry cask models C.negory: ISFSI Subcategory: Confinement Boundary current Initiating Condition: Damage to a loaded cask CONFINEMENT BOUNDARY EAL:

EU1.1 Unusll31 Event Damage to a loaded canister CONFINEMENT BOUNDARY as indicated by an on-contact radiation reading on tl'le surtace of a loaded spent fuel cask > any Tallie E-1 ISFSI dose limit Table E-1 ISFSI Dose Limits Location 24PHB 37PTH 698TH HSM front bird screen 1,050 mremlhr 1,050 mremihr 500mren\/hr OutSlde HSM dOOr 40 mremlhr 4 mrem/11r 4 mreltllllr End shield w.ill extenor 550 mremlhr 8 mremlhr 8 mremlhr Mode Applicability:

p. D-64 ATTACHMENT I Update ONS specific EAL Bases dry cask models Category: ISFSI Subc.itegory: conrmement Bounclary proposed Initiating Condition: Damage to a loadecl cask CONFINEMENT BOUNDARY EAL:

EU1 .1 Unusual Event Damage to a loadecl carnster CONFINEt..lENT BOUNDARY as ind1cate{l by an on-contact radIat1on reacting on Ille sulface of a loaded spent fuel cask > any Table E- 1 ISFSI dose lIm1I Table E-1 ISFSI Dose Limits HSM Module E1-E20. E21-E42, E4 3-E67 , E68-E 74 , E75-E80 . E81-E92,

'lo' 1-W20 W21 -W42 W43-W67 W68-W74 W75-W80 W81-W92 Location 24P' 24P .. 24PHB 24PHB 24PTH 24PTH HSM Front 400 800 1,000 Surface mrem,'hr mrem,'hr mremlhr HSM Front 1,050 1,050 1,200 Bird Screen mremlhr mremlhr mremillr f OutsideHSM 2()0  !

40 40 140 160 Door mrem;tir mrem/hr mrem/hr mremlhr mremlhr

  • End shield 40 600 550 600 800 wan exterior nuemlhr mrem.lllr mrem/hr mremlllr mrem/1\r
  • HSM E1-E20 3nd W 1-'li::Gwere loJde<t v.,;h ;::.:,p t-3n:~te-q; under the Site Spec.die L1ce n~e SNM ..~503 and only have Tecnn:cal Spectficatondosei rate fi n 1tfor HSM S:urtace

... HSf~s E21-E42 and W:2 1-'.1/2\f4:? 'N!'f'e lo3ded with :?-lP c3n1Stt::rs under the Gener31Lte.ense CoC ioo.:

Mode Applicability:

2. p. D-65 Confinement boundary is defined Confinement boundary is defined as editorial, correct 2nd par. as the barrier(s} between areas the barrier(s} between areas typographical error containing radioactive substances containing radioactive substances and the environment. Therefore, and the environment. Therefore, damage to a confinement damage to a confinement boundary boundary must be a confirmed must be a confirmed physical breach

Change Matrix ONS Emergency Plan, Rev 2019-004 Page 2 of2 Attachment to 50.54q CHANGE MATRIX

  1. Page Current Proposed Change Reason

/Section physical breach between the betweenthespentfuelandth e spent fuel and the environment environment for the DSC.

for the TSC

3. p. D-65 The Table E-1 values shown are 2 The Table E-1 values shown are 2 editorial, added 3rd par. times the limits specified in the times the limits specified in the ISFSI reference ISFSI Certificate of Compliance Certificate of Compliance Technical Technical Specifications for Specifications for radiation external radiation external to the to the applicable loaded DSC (ref. 1, applicable loaded DSC (ref. 1, 2). 2, 4).

~- p. D-65 1. USN RC Certificate of 1. USN RC Certificate of Compliance for Editorial, update Compliance for Spent Fuel Spent Fuel Storage Casks, No. 1004, references Storage Casks, No. 1004, Amendments 0,1,2,3,4,6,7,8,9,13, and Amendment 13, Attachment A, 15 Attachment A, Technical Technical Specifications for Specifications for Transnuclear, Inc.,

Transnuclear, Inc., Standardized Standardized NUHOMS Horizontal NUHOMS Horizontal Modular Modular Storage System Storage System 2. OSC-8716, Oconee ISFSI Dose Rate

2. OSC-8716, Oconee ISFSI Dose Evaluations, Rev. 0 (4/29/05)

Rate Evaluations, Rev. 0 3. NEI 99-01 E-HU1 (4/29/05) 4. Site Specific license SNM 2503,

3. NEI 99-01 E-HU1 Appendix A
5. p. D-64 The Standardized NUHOMS The Standardized NUHOMS System Update ONS specific last System is a horizontal canister is a horizontal canister system dry cask models paragraph system composed of a steel dry composed of a steel dry shielded shielded canister (DSC), a canister (DSC), a reinforced concrete reinforced concrete horizontal horizontal storage module (HSM),

p.D-65 storage module (HSM), and a and a transfer cask (TC). The welded first transfer cask (TC). The welded DSC provides confinement and paragraph DSC provides confinement and criticality control for the storage and criticality control for the storage transfer of irradiated fuel. The and transfer of irradiated fuel. concrete module provides radiation The concrete module provides shielding while allowing cooling of radiation shielding while allowing the DSC and fuel by natural cooling of the DSC and fuel by convection during storage (ref. 1, 2).

natural convection during storage The ONS ISFSI utilizes the 24P, (ref. 1, 2). The ONS ISFSI utilizes 24PHB, and 24PTH DSC designs.

the 24PHB, 37PTH and 698TH DSC designs.

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