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Summary of 970521 Meeting W/Entergy Operations,Inc Re Proposed Removal of MSL Lcs,Removal of Pvlc Sys & Increase of MSIV Leakage Requirements in TS
	ML20148F039
Person / Time
Site:	River Bend
Issue date:	05/30/1997
From:	Wigginton D; NRC (Affiliation Not Assigned)
To:	; NRC (Affiliation Not Assigned)
References
	NUDOCS 9706040079
	Download: ML20148F039 (40)
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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON. D.C. 3066H001 o

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May 30, 1997 4

LICENSEE:

ENTERGY OPERATIONS, INC.

FACILITY:

RIVER BEND STATION, UNIT NO. 1

SUBJECT:

SUMMARY

OF MEETING HELD ON MAY 21, 1997, WITH ENTERGY l

OPERATIONS, INC. TO DISCUSS THE PROPOSED REMOVAL OF THE MAIN STEAM LINE LEAKAGE CONTROL SYSTEM, REMOVAL OF THE PENETRATION VALVE LEAKAGE CONTROL SYSTEM, AND THE INCREASE OF MSIV LEAKAGE REQUIREMENTS IN THE TECHNICAL SPECIFICATIONS FOR THE RIVER BEND STATION.

On May 21, 1997, the staff met with representatives from Entergy Operations, Inc., to discuss the proposed license amendment that would remove the main steam line leakage control system, remove the penetration valve leakage control system, and increase the leakage requirements for the main steam isolation valves. Attachment I lists the meeting attendees.

j The licensee's presentation was made from the viewgraphs in Attachment 2.

The basis for the proposed changes is the doses calculated with the proposed leakage rates assuming the leakage is immediately released to the atmosphere from the outboard main steam isolation valve (MSIV). The licensee's calculations show that the calculated doses remain within the 10 CFR Part 100 criteria for offsite doses and within the General Design Criterion 19 of 10 CFR Part 50 for control room operators. The licensee further described its i

defense in depth as being the qualification of the lines beyond the outboard isolation valves and the existing shutoff valves. The licensee plans to discontinue testing the shutoff valves and this was questioned by the staff.

There was discussion on the qualification of the main steam lines and main steam drain lines as a possible alternative to leakage control. The licensee will examine these lines and determine the seismic qualification, if any.

The dose calculations were originally performed with the DRAGON code. The new calculations are performed with the TRANSACT code. The licensee reported that the two codes were benchmarked and had been run on the same configuration with leakage control systems in place with agreeable results. The proposed amendment, however, assumes 100 standard cubic feet per hour (sefh) leakage for u) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 200 scfh thereafter for up to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months . The 100 scfh used )y the licensee is derived from loss-of-coolant accident analysis and is somewhat conservative. The staff uses 200 scfh from 0 to 720 hour0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months s-and may conduct an independent analysis at these values. The licensee understands g%$ h c

9706040079 970530 PDR ADOCK 05000458

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e e that the licensing basis woule autinue to be the 200 scfh; the staff may want this documented for the review. Other conservatisms were discussed and will be reviewed by the staff.

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.d David L. Wigginton, Project Manager N Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-458 Attachments:

1.

List of Meeting Attendees 2.

Licensee Handout cc w/atts: See next page

E LJ May 30, 1997 that the licensing basis would continue to be the 200 scfh; the staff may want this documented for the review. Other conservatisms were discussed and will be reviewed by the staff.

i "AWb GL David L. Wigginton, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-458 Attachments:

1.

List of Meeting Attendees 2.

Licensee Handout j

cc w/atts:

See next page DISTRIBUTION:

Docket-File E-MAIL PUBLIC SCollins/FMiraglia (SJC1/FJM)

RZimmerman (RPZ)

PD4-1 r/f JRoe (JWR)

TGwynn (TPG)

OGC EAdensam (EGA1)

REmch (RLE)

ACRS CHawes (CMH2)

DTerao (DXT)

DWigginton (DLW)

JPulsipher (JCP2) 4 Alee (AJL)

JLee (JYL1)

TScarbrough (TGS)

Dross (SLM3) 4 MDapas (MLDI), ED0/RIV Document Name:

RBSLCS.MTS OFC PM/PD4-) O LA/PD4-1

/

DWiggirfkNh'CHawesCbet

/

NAME v

DATE 6/24/97 5 /30/97

/ //97 COPY YES/NO YES/N0 Y'ES/NO l

OFFICIAL RECORD COPY 3 4 b achec0 1

r l

p(ID I

030022 1

i Entergy Operations, Inc.

River Bend Station cc-I Winston & Strawn Executive Vice President and l

1400 L Street, N.W.

Chief Operating Officer Washington, DC 20005-3502 Entergy Operations, Inc.

P. O. Box 31995 Manager - Licensing Jackson, MS 39286 Entergy Operations, Inc.

t River Bend Station General Manager - Plant Operations P. O. Box 220 Entergy Operations, Inc.

i St. Francisville, LA 70775 River Bend Station P. O. Box 220 i

Director St. Francisville, LA 70775 Joint Operations Cajun

{

10719 Airline Highway Director - Nuclear Safety P. O. Box 15540 Entergy Operations, Inc.

Baton Rouge, LA.70895 River Bend Station P. O. Box 220 Senior Resident Inspector St. Francisville, LA 70775 P. 0. Box 1050 St. Francisville, LA 70775 Vice President - Operations Support Entergy Operations, Inc.

President'of West Feliciana P. O. Box 31995 Police Jury Jackson, MS 39286-1995 P. O. Box 1921 St. Francisville, LA 70775 Attorney General State of Louisiana Regional Administrator, Region IV P. O. Box 94095 U.S. Nuclear Regulatory Commission Baton Rouge, LA 70804-9095 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Wise, Carter, Child & Caraway P. O. Box 651 Ms. H. Anne Plettinger Jackson, MS 39205 3456 Villa Rose Drive Baton Rouge, LA 70806 Vice President & Controller Cajun Electric Power Cooperative Administrator 10715 Airline Highway Louisiana Radiation Protection Divisica P.O. Box 15540 P. O. Box 82135 Baton Rouge, LA 70895 Baton Rouge, LA 70884-2135 Mr. John R._McGaha Vice President Operations Entergy Operations, Inc.

River Bend Station P.O. Box 220 St. Francisville, LA 70775 j

f e

ATTENDEES AT MEETING OF MAY 21. 1997 l

THE PROPOSED REMOVAL OF THE MAIN STEAM LINE LEAKAGE CONTROL SYSTEM.

REMOVAL OF THE PENETRATION VALVE LEAKAGE CONTROL SYSTEM. AND THE INCREASE OF MSIV LEAKAGE REQUIREMENTS IN THE TECHNICAL SPECIFICATIONS FOR THE RIVER BEND STATION RA!!!g Oraanization Davd Wigginton NRR/PD4-1 J. Lee NRR/DRPM/PERB R. Emch NRR/DRPM/PERB David Terao NRR/DE/EMEB Jim Pulsipher NRR/DSSA/ Cont. Sys.

Arnold J. Lee NRR/DE/ Mechanical Engy. Branch Thomas Scarbrough NRR/DE/EMEB Melody Chilson E01/ Nuclear Safety & Reg. Affairs John Maher E01/ Safety & Engineering Analysis Kishir Chapaneri E01/ Operations-Sta.

T. Gates E01/ Licensing Paul A. Sicard E01/ Safety & Engineering Analysis Charles Bulot E01/ System Engineering Alan Day E01/LLRT Coordinator William D. Roman Southwest Power Consultants, Inc.

Marvin Morris Omega Technical Services, Inc.

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ATTACHMENT 1

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RBS/NRC 4 t__ _

!i, PROPOSED LEAKAGE CONTROL SYSTEMS AMESDMEST

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l Leakage Control Systems Removal l

Entergy Corporation River Bend Station

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a Opening Remarks 1

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i Tim Gates Supervisor - Licensing i

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Introductions

Charles Bulot LCS System Engineer Kishor Chapaneri Operations - Shift Technical l

~ Advisor i

i Melody Chilson Licensing l

Alan Day LLRT Coordinator Tim Gates Supervisor - Licensing I

John Maher Safety & Engineering Analysis i

Marvin Morris Omega Technical Services,Inc.

William Roman Southwest Power Consultants, Inc.

Amir Shahkarami Manager - Mech / Civil Engineering Paul Sicard Manager - Safety &

Engineering Analysis

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Agenda i

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Leakage Control Systems l

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Overview l

Operator Actions with Respect j

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LOCA Dose Analysis Methodology and Assumptions Overview i

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4 Leakage Control 4

Systems Overview j

Amir Shahkarami l

Manager - Mechanical / Civil Engineering i

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i Systems Overview i

Penetration Valve Leakage Control System (PVLCS)

Main Steam - Positive Leakage Control System (MS-PLCS)

- Primary Valves

- Seismic Qualifica: ion of MSL

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MAIN STEAM-POSITIVE LEAKAGE CONTROL SYSTEM

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l MS-PLCS Valve Data l

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Main Steam Isolation Valves

- Eight 24 inch Atwood Morrill Y-Pattern Globe Valves

Main Steam Shutoff:MOVs

- Four 24 inch Velan Gate Valves

Main Steam Line Drain :MOVs

- Four 3 inch Velan Gate Valves

- Four '1 1/2 inch Velan Globe Valves

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Main Steam Isolation 5

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- LLRT, IST Main Steam Shutoff MOVs l

- LLRT, IST, MOV Required j

Testing i

Main Steam Line Drains

- In Board - LLRT, IST, I

MOV Required Testing l

- Otr: board - LLRT, MOV Required Tes::ing, some IST 4

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Challenges Identified and Resolved i

i MSIVs i

- Stuck Open MSIV Anti-rotational Modification j

Main Steam Shutoff MOVs

- Acalator Thrust Incuced j

Cracking i

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4 In Summary l

MSIVs will provide continuous j

leakage control during DBA 4

LOCA l

l Defense-in-Depth Maintained 1

- Main Steam Shutoff MOVs 1

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- Seismic Qualifica: ion of Main l

Steam Lines l

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l Operator Actions with j

Respect to Leakage Control i

i Kishor Chapaneri 4

Operations - Shift Technical i

Advisor

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Emergency Operating Procedures Developed from XRC Approved BWROG Emergency Procedure Guidelines, Rev. 4 Symptom Based Address Broad Spectrum of Accidents i

i Operator Actions i,

l EUP-0001., RPV Control i

- Assure initiation of automatic l

actions including isolations l

- Take manual Operator action to l

initiate actions which should have initia:ed, but did not i

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i Operator Actions I

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- General Philosophy d

- Role of MSIVs

- Role of Main Steam Shutoff MOVs j

- Role of Main Steam Line Drains i

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l Operator Actions j

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Containment Control

- Use indications to determine if l

main steam line releases occur in mam steam tunnel (Secondary l

Con:ainment Control Leg?

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- Take appropriate actions to stop or reduce offsite radiological releases (Radioactive Release Control Leg)

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In Summary Defense-in-Ddpth Maintained j

- Au:oma:icIsolations i

- Operator Actions

- Leak Detection Ins:rumentation/

Indications

- Radiological Release Control

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i LOCA Dose Analysis Methodology and j

j Assumptions I

Paul Sicard i

Manager - Safety & Engineering Analysis

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Overview Similarities-Differences Scenario Time Steps Leakage Assumptions and Release Paths Calculated Doses

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Similarities i

l The new analysis utilizes the l

current dose methodology and data as much as possible, but l

removes some conservatisms j

used in the current design basis l

calculation to more realistically l

represent the River Bend l

Station design.

e Differences Previous

New Analysis Analysis

- ICRP 30

- ICRP 2

- DRAGON

- TRANSACT

- No Credit

- Suppression Taken for Pool Scrubbing ofIodines Suppression Pool Scrubbing (DF of 10)

- Control Room

- No Control Shine Room Shine i

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Scenario Time Steps New Analysis Previous Analysis

. 189 sec., PPP 24 sec. - 189 sec. - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 213 sec., PPP

- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months - 720

- 213 sec. - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months hours

- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months l

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l Leakage Assumptions j

Unchanged i

Containment Leakage l

0.26% Cont. Vol. per day l

Annulus Bypass Leakage i

13,500 cc/hr l

ESF Leakage l

60 gph i

Previous Analysis New Analysis

- Main Steam Leakage 150 scfh for 0 - 25 min.

100 scfh for 0 - 2 hrs O scfh for 25 min to 720 200 scfh for 2 - 720 hs ks Sec. Cont. Bypass Leakage 170,000cc/hr for 0 - 25 170,000 cc/hr min.

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Dose Values Thyroid Whole Body (Rem) l (Rem)

EAB Dose Limit 300 25 Previous Analysis 293 6.8 New Analysis 37.5 4.7 LPZ Dose Limit 300 25 Previous Analysis 102 10.2 New Analysis 62 2.8 CR Dose Limit 30 5

Previous Analysis 12.1 4.02 New Analysis 11.2 0.43 l

In Summary Unnecessary Conservatisms Removed From Current Design Basis Calculation Requirements of 10CFR100 Met No Significant Hazards to Health and Safety of Public

A Closing Remarks Tim Gates Supervisor - Licensing hn-a

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Leakage Control System Removal l

i Xo Challenge to RBS DBA l

LOCA Response Capability l

Defense-in-Depth is Maintained l

- Plant design

- Operator actions l

Xo Significant Hazards to Health and Safety of Public i

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Over S20 Million Cost Benefit Licensing Action Operation & Maintenance S4.4 million 4

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Testing l

S6.7 million l

Outage i

S9.2 million i

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ML20148F039

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