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| document type = MEETING MINUTES & NOTES--CORRESPONDENCE, MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
| document type = MEETING MINUTES & NOTES--CORRESPONDENCE, MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
| page count = 25
| page count = 25
| project = TAC:MA3738, TAC:MA3739
| stage = Meeting
}}
}}



Latest revision as of 06:41, 9 December 2021

Summary of 981117 Meeting with Util in Rockville,Md Re Proposed Changes to TSs to Provide Longer Allowed Outage Times for Emergency & Balance of Plant Electrical Buses for Plant
ML20196D975
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/30/1998
From: Trimble D
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
TAC-MA3738, TAC-MA3739, NUDOCS 9812030003
Download: ML20196D975 (25)


Text

)

49* *% NC~ y Qd a k UNITED STATES ""~i l, f j NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 2005H001

%.....p tbwrber 30, S9B LICENSEE: Carolina Power & Light Company i FACILITY: Brunswick Steam Electric Plant, Units 1 and 2

SUBJECT:

SUMMARY

OF NOVEMBER 17,1998, MEETING REGARDING PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS TO PROVIDE LONGER ALLOWED OUTAGE TIMES FOR EMERGENCY AND BALAlICE OF PLANT ELECTRICAL BUSES - BRUNSWICK STEAM ELEC' Rn GNT, UNITS 1 AND 2 (TAC NOS. MA3738 AND MA3739)

On November 17,1998, members of the NRC staff met with Carolina Power & Light Company (CP&L or licensee) personnel at the NRC's One White Flint North headquarters in Rockville, Md. The meeting was open to the public. The purpose of the meeting was to discuss changes proposed by the licensee to the Technical Specifications (TS) for the Brunswick Steam Electric Piant Units 1 and 2 (BSEP 1 & 2) which would provide a longer allowed outage time (AOT) of 7 days for planned maintenance on emergency and balance of plant (BOP) electrical buses. The current AOT for these buses is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

The changes were first submitted to the NRC on November 1,1996, as part of CP&L's application for conversion to improved Standard Technical Specifications (ITS). The NRC later determined that it required more information concerning the impact of the AOT extension on plant risk. Thus, at the NRC's request, on September 14,1998, CP&L provided supplemental /

information in support of the AOT extension. /

d The licensee's basis for its request is that the additional time is needed to perform vendor- ,

recommended maintenance on the buses and associated components. The AOT extension .

l would only apply when one unit is operating and one unit is shut down and the planned f  ;

maintenance is to be conducted on the shutdown unit's electrical system. However, because #, y /!

there is some cross sharing of electricalloads between units, a limited number of components /

on the operating unit wou d be affected by such maintenance.

l During the meeting the 'icensee presented further information on the proposed changes and the plant electrical system design. This information will assist the NRC staff in reaching its conclusion on the impact of the proposal on plant risk. In follow-up to the meetira the staff will issue a request for additional information (RAI). The staff asked that the licensee, as part of its response to the forthcoming RAI, determine if the planned maintenance can be l

9812030003 981130

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. accomplished safely in a shorter period of time. If so, the staff asked that the licensee consider reducing the length of the requested AOT. <

A list of meeting attendees as well as the handout provided by the licensee are enclosed.  :

l i

Original signed by: 1 David C. Trimble, Project Manager Project Directorate ll-3  !

,- Division of Reactor Projects -I/ll Office of Nuclear Reactor Regulation

Enclosures:

(1) Attendance List i i

. (2) Licensee Handout Docket Nos. 50-325 and 50-324  ;

cc w/encis: See next page EBRD COPY ,

WAAllte@

DUBLIC PDil-1 RF D. Trimble OGC ACRS 4

E-MAIL S. Collins /F. Miraglia B. Boger  !

J. Zwolinski  ;

T. Martin (SLM3)

D. O'Neal '

A. El-Bassioni M. Wohl P. Kang  ;

J. Lazevnick l F.Ashe I M. Tschiltz l

- J. Johnson, Ril FILENAMf G:\BRUNSWIC\ BRA 3738.MTS OFFICE PM:PDll-3 LA:PDil-2 D:PDil-3 NAME DT ble EDu ton FHebdo

. DATE 11/'I98 11 8 8 11/f?98 COPY ((&s/No (Te)No (ho

" OFFICIAL RECORD COPY

2 i

accomplished safely in a shorter period of time. If so, the staff asked that the licensee consider reducing the length of the requested AOT.

A list of meeting attendees as well as the handout provided by the licensee are enclosed.

i

&?$

( David C. Trimble, Project Manager Project Directorate ll-3 Division of Reactor Projects -1/11 Office of Nuclear Reactor Regulation l

Enclosures:

(1) Attendance List (2) Licensee Handout Docket Nos. 59 32G and 50-324 l

cc w/ enc!s: See next page l

l 1

l l

i

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L .

~

3 . Noveter 30,1998 2

accomplished safely in a shorter period of time. If so, the staff asked that the licensee consider reducing the length of the requested AOT.

I A list of meeting attendees as well as the handout provided by the licensee are enclosed.

J Original signed by: -

l I David C. Trimble, Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/il Office of Nuclear Reactor Regulation

Enclosures:

'(1) Attendance List -

l (2) Licensee Handout l Docket Nos. 50-325 and 50-324 1

l- cc w/encis: See next page HARD COPY l I

Docket File -

PUBLIC l PDll-1 RF l- .D. Tnmble

! OGC ACRS i

j_ ' E-MAIL

S. Collins /F. Miraglia l B.Boger J. Zwolinski T. Martin (SLM3)

D. O'Neal A. El-Bassioni l M. Wohl P. Kang J. Lazevnick F.Ashe M. Tschiltz J, Johnson, Ril l FILENAME- G:\BRUNSWIC\ BRA 3738.MTS OFFICE PM:PDil-3 LA:PDll-2 D:PDll-3 NAME DT 1ble EDu gton FHebdo DATE 11/498 11 8 8 11/f798 COPY (fas/No MNo tho l

~ OFFICIAL RECORD COPY l

> 1 l

l

. - . . . _ _ l

Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2

.cc:

Mr. William D. Johnson Ms. Karen E. Long .

Vice President and Senior Counsel .

Assistant Attorney General Carolina Power & Light Company State of North Carolina Post Office Box 1551 Post Office Box 629 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Jerry W. Jones, Chairman Mr. Robert P. Gruber Brunswick County Board of Commissioners Executive Director Post Office Box 249 Public Staff- NCUC Bolivia, North Carolina 28422 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Resident inspector U.S. Nuclear Regulatory Commission Director 8470 River Road Site Operations Southport, North Carolina 28461 Brunswick Steam Electric Plant Post Office Box 10429 Regional Administrator, Region il Southport, North Carolina 28461 U.S. Nuclear Regulatory Commission Atlanta Federal Center Mr. William H. Crowe, Mayor 61 Forsyth Street, SW, Suite 23T85 City of Southport Atlanta, Georgia 30303 201 East Moore Street Southport, North Carolina 28461 Mr. Mel Fry, Director Division of Radiation Protection Mr. Dan E. Summers N.C. Department of Environment Emergency Management Coordinator and Natural Resources New Hanover County Department of 3825 Barrett Dr. Emergency Management Raleigh, North Carolina 27609-7721 Post Office Box 1525 Wilmington, North Carolina 28402 Mr. J. J. Lyash (

Plant Manager Ms. D. B. Alexander Carolina Power & Light Company Manager Brunswick Steam Electric Plant Performance Evaluation and Post Office Box 10429 Regulatory Affairs CPB 9 Southport, North Carolina 28461 Carolina Power & Light Company Post Office Box 1551 Public Service Commission Raleigh, North Carolina 27602-1551 State of South Carolina Post Office Drawer 11649 Mr. K. R. Jury Columbia, South Carolina 29211 Manager- Regulatory Affairs .

Carolina Power & Light Company Mr. J. S. Keenan, Vice President Post Office Box 10429 Brunswick Steam Electric Plant Southport, NC 28461-0.t29 Carolina Power & Light Company Post Office Box 10429 l

Southport, North Carolina 28461

l 1

\

MEETING ATTENDANCE LIST I

Licensee: Carolina Power & Light Company Plant (s): Brunswick 1 and 2

Subject:

Proposed Changes to the Technical Specifications to Provide Longer Allowed Outage Times for Emergency and Balance of Plant Electrical Buses l l Date: November 17,1998 I Location: Room O-12802, One White Flint North Building,11555 Rockville Pike, Rockville, l Md.

l Time: 10:00 a.m.

l NAME NRC STAFF F.Ashe l

A. El-Bassioni l

J. Larevnick '

D. O'Neal M. Wohl D. Trimble CP&L G. Atkinson G. Ellis (contractor - Excel Services)

R. Delong D. LaBelle W. Dorman G. Miller M. Turkal i

l l

Enclosure 1

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1 l-l Discussion Topics l

ePurpose Of Request i eElectrical Distribution System Overview

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eTechnical Specification Overview l

4 eRisk insights

!, oConclusion 4

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3

O Purpose Of Request l e Modify Technical Specifications (TS) 3.8.1 l

and 3.8.7 To:

+ Provide Sufficient Time For Bus Maintenance l + Avoid incurring A Dual Unit Outage l o7 Day AOT Established Based On:

! + Most Restrictive AOT On Operating Unit l + Acceptable Risk Evaluation l mBenefit Of Performing Maintenance l mAvoid Unnecessary Transient On Operating Unit

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      • "" BRUNSWICK NUCLEAR PLANT 1 -

ELECTRICAL DISTRIBUTION SYSTEM i LEGEND:

summusus ALTERNATE OFF-SITE POWER SOURCE (BOTH UNITS $40seLAR)

- PftEFERRED OFF-SITE POWER SOURCE (80 Tis UNITS Sles!LAR) 4 N asummmus CLASS IE SYSTEtt t

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Electrical Distribution System System Configuration - E-Bus Loads E1 E2 E3 E4 Unit 1 ECCS CS Div 1 CS1A CS Div 11 CS18 LPCI Div i RHR1C RHR 1 A & Valves LPCI Div 11 RHR1D RHR 1B & Valves Unit 2 ECCS CS Div I CS 2A CS Div 11 CS 2B LPCI Div i RHR 2C & Valves RHR 2A LPCI Div ll RHR 2D & Valves RHR28 Service Water Nuc SW 1A 18 2A 2B Unit 1 Con SW 1B 1C 1A Unit 2 Con SW 2C 2A 2B

. 5 '

ll

Technical Specification Overview Comparison i

Operability Operability AOT AOT Requirements Requirements (Current) (Proposed)

(Current) (Proposed)

TS 3.8.1 4 Offsite Circuits (2 per 4 Offsite Circuits (2 per 2 Offisite Circuits and 2 Offinite Circuits and unit) unit) EDG Inop EDGloop Enter LCO 3.0.3 Enter LCO 3.0.3 4 EDGs 4 EDGs (Unpianned)

I . 2 Offisite Circuits and EDG Inop (3/D Unit) 7 Days to Restore -

12 Hrs to Mode 3 (Planned)

TS 3.8.7 2 AC & 2 DC Divisions 2 AC & 2 DC Divisions 1 AC Divisioninop 1 AC Division Inop of Electrical Power of Electrical Power 8 Hrs to Restore 8 Hrs to Restore 12 Hrs to Mode 3 12 Hrs to Mode 3 (Unplanned) 1 AC Division Inop (S/D

Unit) 7 Days to Restore 12 Hrs to Mode 3

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1 (Planned) 4

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Technical Specification Overview Examples eProposed T5 And Bases Changes oApplication Of Required Action B.1 ePractical Examples sessa 7

SFDP .

1 TS 5.5.11.b.1 Example 7 Day AOT(Proposed) .

Emergency Bus E4 TS 3.8.7 Inoperable u 7 Day AOT 7 Day AOT 1 A Core Spray Pump TS 3.5.1 IB LPCI Loop Inoperable Loss Of Safety Function u

g ,y [Tl, j, .

Enter LCO 3.0.3 mua

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SFDP TS 5.5.11.b.2 Example 7 Day AOT 125 VDC Control Power To Div II ESS Logic TS 3.8.7 Cabinet Inoperable v

24 Hrs. To Trip 1B LPCI Loop Logic

Channels

,7 Day AOT 7 Day AOT 1 A Core Spray Pump IB LPCI Loop Inoperable TS 3.5.1 Loss Of Safety Function EMJSE.

' ' ~ ^ " ~ '

Enter LCO 3.0.3

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3 SFDP l TS 5.5.11.b.2 Example 7 Day AOT l 125 VDC Control Power To Div II ESS Logic TS 3.8.7 Cabinet Inoperable 4

24 Hrs. To Trip u Channels 24 Hrs. To Trip 1 A Core Spray Loop TS 3.3.5.1 1B LPCI Loop Logic Channels Logic Inoperable

, , 7 Day AOT , ,7 Day AOT

IB LPCI Loop 1 A Core Spray Pump i

1 Loss Of Safety Function C(w{&L t

Enter LCO 3.0.3

. 10 5 .

1 Risk-informed Overview l Risk Management Process eBrunswick Risk Management Process l Complies With a(3) Of Maintenance Rule l o Additional Controls in TS 5.5.11, SFDP l + Redundant Safety Functions l eBrunswick Procedure AP-25:

l o Prevents Removal Of Additional High Risk j Components I + Contains Guidance For Actions if Unforeseen l Configurations Occur

. 11 i

__[.___i,_____.___.-_.__..___________.___ _ _ _ _ _ _ _ _

1 l Risk-Informed Overview j Risk Management Process l eintegrated Assessment Of Plant l Configuration l o Based On Level 1 Internal Events PSA l + PSA Model includes Buses, Breakers,

Offsite And Onsite AC Sources That .

Represent The Proposed Configuration

)

> PSA Model 1s Updated Periodically

+ Equipment Performance is Monitored By Maintenance. Rule Program

! EM

l. 12 i

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. - - . _ _ . _ _ _ _ . _ . . _ , , _ _ _ . . . . _ _ _ . _ . . _ . . _ . _ _ . . _ . _ . . . _ . _ _ _ . _ _ _ . _ . _ _ _ _ _ . _ . _ . ~ . _ , _ , . _ _ _ _ . . .

Risk-informed Overview impact of TS Change elmpact On The Operating Unit:

+1 RHR Pump

+1 RHR Service Water Pump (Same Division)

+ AC Power To 1 Loop Of LPCI Valves

+ 1 Conventional Service Water Pump mE1 Or E4 Outages Only e Adequate -Redundancy Exists On Remaining Equipment seet.

13

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Risk-informed Overview o '"

,n d, Y

Impact of TS Change "

l i

oOperating Unit i o Base Case CDF 9.2E-6/ year

+ Analyzed Case CDF 9.7E-6/ year

sincremental Change 4.6E-7/ year ed'L'Q.

i i

! + Actual CDF Change Would Be Less l

mActual Out Of Service Time Much Less i

mNo Credit Taken c or improved Reliability Of E-Bus l (f!OR!!_

. 14 i

l i

l Risk-informed Overview

! Impact of TS Change i

MOST IMPORTANT SYSTEMS IMPACTIF ALSO CONTROLS TO i

REMOVED FROM PRECLUDE

(E-BUS OUT OF SERVICE) SERVICE UNAVAILABILITY Core Spray TS LCO 3.0.3 YES 1

1 Conventional Service Water 7 day AOT YES Diesel Generator TS LCO 3.0.3 YES

! High Pressure Coolant injection 72 hr. AOT YES Reactor Core Isolation Cooling 14 day AOT YES aaea wum 15

! Risk-informed Overview l Impact of TS Change l

eLarge Early Release Not Significant .

l + Affected Systems Have Minimal impact On i Containment Performance l <> Some Isolation Valves Will Be in isolated l Position

! OExternal Events impact Not Significant

o Proposed Configuration Does Not Create

! Additional Challenges Or increased initiating l Event Potential sPM -

- 16 ,

l i

9 Risk-informed Overview impact of TS Change o TSs Allow This Configuration Indefinitely

+ Risk is Managed By Defense-in-Depth Philosophy (NUMARC 91-04) mConcurrent Outage Activities Are Limited o E-Bus Work is Performed Late in The Outage mLower Decay Heat oAdequate Redundancy Exists To Maintain Required Defense-in-Depth ses4 17

! Risk-informed Overview Conclusion - - . _ - _- - ____ --

l eProposed Change Has An Acceptably l Low Impact On Plant Risk  ;

l cAdequate Plant Controls Are in Place To l Reduce The Likelihood Of Risk-Significant Configurations .

l sExisting Programs And Procedures Meet j The Recommendation For A Risk-

informed Plant Configuration Control l Program

! ;se 18

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