RA-20-0307, Summary of Changes to Emergency Plan, Effective 8/24/2020

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Summary of Changes to Emergency Plan, Effective 8/24/2020
ML20267A651
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 09/23/2020
From: Burchfield J
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-20-0307
Download: ML20267A651 (7)


Text

e..l_~ DUKE

~ ENERGY~

RA-20-0307 September 23, 2020 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, Maryland 20852-2746

Subject:

Duke Energy Carolinas, LLC 10 CFR 50.54(q) 10 CFR 72.44(f)

Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, -270, and -287 EAL Technical Bases Document Revision 001 J. Ed Burchfield, Jr.

Vice President Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672 o 864.873.3478

f. 864.873.4208 Ed.Burchfield@duke-energy.com 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 August 24, 2020.

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, J ctlLJ#ll J. Ed Burchfield, Jr.

Vice President Oconee Nuclear Station Attachments

1. AR 02330466 Changes In ONS EAL Tech Bases Document CSD-EP-ONS-0101-01, Rev.001
2. AR 02340655 Changes In ONS EAL Tech Bases Document CSD-EP-ONS-0101-01, Rev.001

RA-20-0307 September 23, 2020 Page2 xc:

Ms. Laura Dudes Administrator, USNRC Region II Marquis One Tower 245 Peachtree Center., NE Suite 1200 Atlanta GA 30303-1257 Mr. Shawn Williams Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Adam Ruh NRC Senior Resident Inspector (Acting)

Oconee Nuclear Station

AR 02330466 CHANGES IN ONS EAL TECH BASIS DOCUMENT CSD-EP-ONS-0101-01, REV.001 Sect Change From Change To Step

1.

CU5.1 T...,._ C5 Cal11111u,if Mi11o1'1111Cbods T-C5 Communicmon-System

Onsill, Offsile NRC Sysllem Onsitt ~

NRC p.95 Canmen:ial phone service X

X X

Camnen:ial phone-X X

X ONS site phone system X

X X

OHS sit& phone s,stem X

X X

EOF phone syswm X

X EOF phone system X

X Pubic Adlln!ss system X

PllbicAdlfress system X

Onsile radio system X

Onsileradio sys1e!n X

DEMNET X

llEMNET X

Offsaradio system X

NRC ""-""YTelsphoneSys!En, X

NRC Erneivanq,Telepha,eSys!l!m X

Sadelll:el'hone X

s.t-f'hone X

2.

CU5.1

7.

Offsite radio system Removed from document, renumbered p.96 The offsite radio system is battery backed remaining systems supporting communications with: Control Room Units 1&2, TSC, Field Monitoring Teams, EOF, counties and State of South Carolina.

3.

SU7.1 T;ab!e 5-4 Communicalian-T-5-4 Communic.dion-System 0nsile Offsile NRC System 0nsile Oftsile NRC

p.

Commercial plx>ne service X

X X

Commercial phone service X

X X

174 ONS site phcne system X

X X

ONS site plx>ne system X

X X

EOF plx>ne syst,,m X

X EOF phone system X

X PubicAdlnsssystem X

Pubic Address system X

Onsile radio system X

Onsite radio syslem X

DEMNET X

DEMNET X

Ol!sib> radio syst,,m X

NRC Emergency Te lephane Sysll!m X

NRC Emergency Tel$hone Syslem X

s.t.rlm!Phone X

s.telli:e Phone X

~.

SU7.1

7.

Offsite radio system Removed from document, renumbered

p.

The offsite radio system is battery backed remaining systems 175 supporting communications with: Control Room Units 1&2, TSC, Field Monitoring Teams, EOF, counties and State of South Carolina.

5.

CA6.1 Shift Manager/Emergency Director Shift Manager/Emergency Coordinator p.100 SA9.l p.181 Page 1 of 2

AR 02330466 CHANGES IN ONS EAL TECH BASIS DOCUMENT CSD-EP-ONS-0101-01, REV.001 Sect Change From Change To Step RCS E p.214 Cont B

p.219

6.

p.3 Decision-makers responsible for Decision-makers responsible for Emergency implementation of RP/0/A/1000/001, Classification may use this document as a Emergency Classification, may use this technical reference in support of EAL document as a technical reference in support interpretation.

of EAL interpretation.

7.

p.13 RP /0/ A/1000/001 Emergency Classification Removed from document, renumbered p.35 references in basis p.43 p.49 p.138 p.140 p.142

8.
p.
6.

EP/l,2,3/A/1800/001 Loss of

6.

EP/1,2,3/A/1800/001 OD Loss of 173 Subcooling Margin Subcooling Margin

9.
p.
1.

EP/l,2,3/A/1800/001 Inadequate Core

1.

EP/1,2,3/A/1800/001 0C Inadequate 219 Cooling Core Cooling Removed Offsite Radio System from Communication Methods in EAL Technical Basis Document.

Performed minor editorial changes throughout.

Page 2 of 2

AR 02340655 CHANGES IN ONS EAL TECH BASIS DOCUMENT CSD-EP-ONS-0101-01, REV.001 Change to CSD-EP-ONS-0101-01, ONS EAL Technical Basis Document, which is an implementing procedure to the ONS Emergency Plan.

Spent Fuel Pool Level Instrument level adjustment based on EC#418058. EC#418058 identifies instrument uncertainty associated with Guided Wave Radar level instrumentation that should be accounted for in setting EAL threshold to ensure Spent Fuel Pool level 3 values can be determined by Emergency Coordinators under all accident conditions.

Sect Change From Change To Step

1.

RS2.

Lowering of spent fuel pool level to -23.5 ft.

Lowering of spent fuel pool level to -22 1

ft.

p.58 EAL

2.

RS2.

This EAL is applicable once the post-Fukushima Post-Fukushima order EA-12-051 1

level instrumentation becomes operational on required the installation of reliable SFP its associated unit.

level indication capable of identifying

p. 58 normal level (Level 1), SFP level 10 ft.

Basis Post-Fukushima order EA-12-051 required the above the top of the fuel racks (Level 2) installation of reliable SFP level indication and a SFP level of -23.5 ft. at the top of capable of identifying normal level (Level 1),

the fuel racks (Level 3).

SFP level 10 ft. above the top of the fuel racks (Level 2) and SFP level at the top of the fuel SFP level instruments 1/2/3SFP0010 racks (Level 3).

(primary) and 011 (backup) measure SFP level instruments 1/2/3SFP0010 (primary)

SFP level relative to normal water level (El. 840 ft.) from + 1 ft. to -23.S ft. (El.

and 011 (backup) measure SFP level relative to 816.4 ft).

normal water level (El. 840 ft.) from + 1 ft. to -

23.5 ft. (El. 816.4 ft).

The EAL Threshold Value of -22 ft will be For ONS Level 3 corresponds to an indicated used to account for Total Loop Uncertainty (TLU).

water level of -23.5 ft. (El. 816.S ft.) (ref. 1).

This EAL addresses a significant loss of spent This EAL addresses a significant loss of spent fuel pool inventory control and fuel pool inventory control and makeup makeup capability leading to IMMINENT capability leading to IMMINENT fuel damage.

fuel damage. This condition entails This condition entails major failures of plant major failures of plant functions needed functions needed for protection of the public for protection of the public and thus and thus warrant a Site Area Emergency declaration.

. warrant a Site Area Emergency declaration.

It is recognized that this IC would likely not be Page 1 of3

AR 02340655 CHANGES IN ONS EAL TECH BASIS DOCUMENT CSD-EP-ONS-0101-01, REV.001 Sect Change From Change To Step met until well after another Site Area It is recognized that this IC would likely Emergency IC was met; however, it is included not be met until well after another Site to provide classification diversity.

Area Emergency IC was met; however, it Escalation of the emergency classification level is included to provide classification diversity.

would be via IC RGl or RG2 Escalation of the emergency classification level would be via IC RGl or RG2.

3.

RS2.

1.

Engineering Change EC 105805 &

1.

Engineering Change EC 105805 1

105806

& 105806 p.58

2.

NEI 99-01 AS2

2.

NEI 99-01 AS2 Refe

3.

OSC-11203, WR SFPLI renc Instrument Loop Uncertainty es Calculation

4.

EC EVAL 418058

14.

RG2.

Spent fuel pool level cannot be restored to at Spent fuel pool level cannot be restored 1

least -23.S ft. for~ 60 min. (Note 1) to at least -22 ft. for~ 60 min. (Note 1) p.59 EAL

5.

RG2.

This EAL is applicable once the post-Fukushima Post-Fukushima order EA-12-051 1

level instrumentation becomes operational on required the installation of reliable SFP its associated unit.

level indication capable of identifying p.59 normal level (Level 1), SFP level 10 ft.

Basis Post-Fukushima order EA-12-051 required the above the top of the fuel racks (Level 2) installation of reliable SFP level indication and a SFP level of -23.5 ft. at the top of capable of identifying normal level (Level 1),

the fuel racks (Level 3).

SFP level 10 ft. above the top of the fuel racks (Level 2) and SFP level at the top of the fuel SFP level instruments 1/2/3SFP0010 racks (Level 3).

(primary) and 011 (backup) measure SFP level instruments 1/2/3SFP0010 (primary)

SFP level relative to normal water level (El. 840 ft.) from + 1 ft. to -23.5 ft. (El.

and 011 (backup) measure SFP level relative to 816.4 ft).

normal water level (El. 840 ft.) from+ 1 ft. to -

23.5 -ft. (El. 816.4 ft).

The EAL Threshold Value of --22 ft will be For ONS Level 3 corresponds to an indicated used to account for Total Loop Page 2 of 3

AR 02340655 CHANGES IN ONS EAL TECH BASIS DOCUMENT CSD-EP-ONS-0101-01, REV.001 Sect Change From Change To Step water level of -23.5 ft. (El. 816.5 ft.) (ref. 1).

Uncertainty (TLU).

This EAL addresses a significant loss of spent This EAL addresses a significant loss of fuel pool inventory control and makeup spent fuel pool inventory control and capability leading to a prolonged uncovery of makeup capability leading to a spent fuel. This condition will lead to fuel prolonged uncovery of spent fuel. This damage and a radiological release to the condition will lead to fuel damage and a environment.

radiological release to the environment.

It is recognized that this IC would likely not be It is recognized that this IC would likely met until well after another General Emergency not be met until well after another IC was met; however, it is included to provide General Emergency IC was met; classification diversity.

however, it is included to provide classification diversity.

6.

RG2.

1. Engineering Change EC 105805 & 105806
1.

Engineering Change EC 105805 1

& 105806

2. NEI 99-01 AG2 p.59
2.

NEI 99-01 AG2 Refe

3.

OSC-11203, WR SFPLI renc Instrument Loop Uncertainty es Calculation

4.

EC EVAL 418058 Page 3 of 3