ML20197B743

Summary of 980219 Meeting W/Util Re Mods Made to & Operation of Plant,Unit 3 Recirculation Spray Sys.List of Attendees & Slides Distributed at Meeting Encl

ML20197B743
Person / Time
Site:	Millstone
Issue date:	03/03/1998
From:	Andersen J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9803110395
Download: ML20197B743 (29)

Text

_ _ _ _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ .

pMag g \ . UNITED STATES g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. SpeeHOM March 3, 1998 p g.)

j

- LICENSEE: Northeast Nuclear Energy Company (NNECO, the licensee)

FACILITY: Millstone Nuclear Power Station, Unit 3

SUMMARY

OF FEBRUARY 19,1998, MEETING WITH NNECO TO DISCUSS THE MILLSTONE UNIT 3 RECIRCULATION SPRAY SYSTEM (RSS)

On February 19,1998, the NRC staff participated in a publicly observed meeting with NNECO representatives to discuss the modifications made to and the opers' ion of the Millstone Unit 3 RSS system. Tne licensee presented (1) an overview of the RSS system design, which was

. approved by the staff in 1985, (2) an overview of the system design after the modifications made during the current outage, as well as past outages, (3) specific changes made to the system, including the results of the 1 ! CFR 50.5g evaluations, and (4) a discussion of the effects of the changes on accident analysis.

During the meeting, the staff asked a number of questions, which the licensee promised to address in a future letter. Specifically, these were:

- The staff questioned v;hether all the operating crews had been through a simulator l walk-thru since the simulator was upgraded to include the modifications made to the RSS system.

- Appendix K of 10 CFR Part 50 requires that the heat generation ,ates from radioactive decay of fission products be assumed to equal 1.2 times the value for infinite operating -

time in the 1971 ANS Standard. Appendix K alan requires that heat transfer from piping, vessel walls, and nonfuel intemal hardware be taken into account. On page 17 of the licensee's February 18,1998, submittal, the licensee assumed, based on Westinghouse information presented in NSAL 95-001, that 531 gpm is needed for makeup in the long term cooling phase. The staff noted that the NSAL the licensee referenced is based on Westinghouse's best estimate loss-of-coolant accident methodology. The licensee f'f was asked to state the present (approved) methodology and either provide an evaluation of the available flow versus boiloff based on the present methodology or submit a new methodology for staff review.

- The licensee used the LOCTIC Version 23, Level 02 model in 1985 and the Level 03 modelin 1998. The staff questioned whether a rebaselining was done to compare the two models prior to using Level 03.

- The staff asked the licensee to explain the difference between the new debris transport analysis and the approved old analysis. The ataff also requested the licensee to discuss how the model compares with NUREG-0897, Rev.1.

9803110395 980303 I PDR ADOCK 05000423 P PDR NRC Fil.E CENTER COPY

2-Enclosure '. .s a list of the principal participants at the meeting. Enclosure 2 is a copy of the slides distributed at the meeting, t

W. Andersen, Project Manager cial Projects Office - Licensing ce of Nuclear Reactor Regulation Docket No. 50-423

Enclosures:

1. List of the Participants

2. Slides Distributed at the Meeting cc w/encis: See next page

.y 1

i

'2-March 3, 1998 Enclosure 1 is a list of the principal participants at the mowing. I Enc losure 2 is a copy of the slides distributed at the meeting.

_. Original signed-by:

James W. Andersen, Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-423

Enclosures:

1. List of the Participants

2. Slides Distributed at the Meeting  ;

cc w/encis: See next page E-Mail (wlencl 1 only)

SC.ollins/FMiraglia (ABJ/JMW1)

WTravera (WDT)

PMcKee (PFM) _

BBoger (RPZ)

LBeny (LGB) -

- THartin (SLM3)-

E ' nbro (EXI)--

Auehman (JGL)

TComw (ACC1)

HEichenholz (HBE)

MSnodderly WLanning (WDL)

MShuaibl KManoly'_ -

. BMcCabe (BCM)

JDurr, R1 (JDP)

Hard Copy Opphet Peei pggg-SPO-L Reading SPO Reading JAndersen-

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DOCUMENT NAME: G:',ANDERSEN\MTGSUM2.19

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.] OFFICE- SPO-L FM. / SPO-L:LA (\ L SPMDD  !

l l NAME JAndersenA: i LBerry lft / PMMe l DATE 02/t/98 /i OLJ98 \

O b 98 02/ /98 02/ /98

1. L OFFICIAL RECORD COPY

l.lST OF PARTICIPANTS February 19,1908 hlgrne .Omantration P.McKee NRR/SPO J. Andersen NRR/SPO M. Bowling NU M. Bonaca NU P. Grossman NU H, Miller NU G. Drechsler NU fc P. Dillon NU

.W. Hoffner NU B. Meinhert MMWEC B. Garde LHC G. Imbro NRR/SPO J. Luehman NRR/SPO T. Come NRR/SPO H. Eichenholz NRR/SPO l M. Van Hattem NU l R. DeConto NU

! J. Thalacker HSBC l H. Delton Minority owners i

M. Snodderiy NRR/SCSB W. Lanning NRR/SPO M. Shuaibi NRR/SRXB Z. Schreiber SILCAP K. Malone CIBC Oppenheimer K. Manoly NRR/EMEB e

Enclosure 1

~ -

Millstone Unit 3 RSS System f

February 19,1998

/ N

, Northeast Nuclear Energy

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RSS Presentation

+ Marty Bowling -Introduction

+ Ray DeConto - Overview of RSS

+ Marty Van Haltern - RSS Changes and integrated Safety Assessment

+ Harry Miller - Other issues

+ Marty Bowlir.g - Closing

/ \

g Northeast Nuclear Energy l

s -

Overview of RSS System Ray DeConto Unit 3 Design Engineering .

i I

/ \

3 .

Northeast Nuclear Energy ,

l Three Functions of The RSS System I

+ Containment Heat Removal

+ Emergency Core Cooling

+ lodine Scrubbing

/ x 4 Northeast Nuclear Energy

s -

~

. The Three Phases of the RSS Original Design include

+ Injection Phase

+ Cold Leg Recirculation Phase

+ Hot Leg Recirculation Phase

/ x 5 Northeast Nuclear Energy

! .l I

RSS HX (TYP) l 4 OLD I

SIH PUMP A RSS PUMP D CONTAINMENT r

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(

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SIH PUMP B RCS RSS PUWP C ^

LECS m r

( ,)

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1. as- .

M aT,euMPA S

RSS PUMP B g l

b

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RSS PUMP A w- . .

CHS PUMP A CHS PUMP B INJECTION PHASE l (1985 - ORIGINAL SYSTEM ALIGNMENT)

FIGURE I A.

o 4 COLD RSS HX (TY F ) w F{, [F

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RSS PUMP D CONTAINMENT SIHPUMP B RCS F

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l l 4 CRD RSS PuuP C LEGS m i

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F

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RSS PUMP A CHS PUMP A CHS PUMP B COLD LEG RECIRCULATION PHASE (1985 - ORIGINAL SYSTEM ALIGNMENT)

FIGURE IB

~

4 HOT LEGS RSS HX (TYP)

SIH PUMP A T

\ -

RSS PUMP O CONTAINMENT SIH PUMP B RCS F

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RSS PUu? C LE S L S y

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c-Ik4 COLD RSS PUMP B 1

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CHS PUMP A l

g l

RSS PUMP A I

CHS PUMP B pa o g l V FAILURE : I FULLY QUALIFIEDI I I

l HOT LEG RECIRCULATION PHASE (TWO PATH RECIRCULATION)

(1985 - ORIGINAL SYSTEM ALIGNMENT )

FIGURE 1C

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

s -

Current '98 Design Changes include

+ Injection Phase - Same as original design

+ Cold Leg Recirculation Phase

- 2 RSS pumps aligned to ECCS cold leg recirc mode and remain aligned to l Containment Spray l

- Direct injection into cold leg is isolated

+ Hot Leg Recirculation Phase

- Direct injection into hot leg is not open

- s y Northeast Nuclear Energy

ll i

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RSS PUMP A CHS PUuP A l I

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CHS PUuP B q _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _l (ONLY IF SIH OR CHS UNAVAILABLE FULLY QUALIFIED)

COLD LEG RECIRCULATION PHASE (1998 - SYSTEM ALIGNMENT)

FIGURE 28

4 HOT RSS HX (TYP) p H UMP A

=

RO ITYP) l

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F 3\

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RSS PUuP O CONTAINMENT SIH PUMP B RCS

+

l l 4 COLO 2 HOT GSS PUMP C LEGS LEGS

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4 COLD I RSS PUMP B [ 8 LEGS l I I 1 g CHS PULP A I g

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CHS PUMP B FA UR O I l

FAILURES: l FULLY QUALIFIED) l I

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-______________7__J ,

I I HOT LEG RECIRCULATION PHASE [(WT FULLY QUAUFIED)j (TWO PATH RECIRCULATION)

(1998 - SYSTEM ALIGNMENT)

FIGURE 2C L__ _ _

N /

~

Summary of Design Changes Affecting RSS Operation

+ 1936 - Elimination of Direct injection

+ 1991 - Containment Opt ratira Pressure

+ 1998 - RSE Pump Restriction Orifices and ,

Reduction of Spray Nozzles i

+ 1998 - Use of Cold Leg Direct injection to Deal with Potential Passive Failures

+ 1998 -Increase Allowed Time to Complete Switchover to Cold Leg Recirculation

/ N y Northeast Nuclear Energy

Summary

+ Millstone Unit 3 RSS Design fulfills  !

the following requirements:  ;

Containment Heat Removal Emergency Core Cooling lodine Scrubbing

/ N 14 Northeast Nuclear Energy

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l RSS Changes and Integrated Safety Assessment Marty Van Haltern Safety Analysis Branch

/ N 35 Northeast Nuclear Energy E_ _

s -

10CFR50.59 Review of RSS Modifications i

+ Changes which affect system performance or acceptance criteria

. + Changes which restore system reliability

+ Changes which affect analysis or analytic methods

/ N gg Northeast Nuclear Energy

\ /

~

50.59 Reviews of Functional Changes

+ Elimination of direction injection caused a redundant safety function with no operator action to become a contingent safety function requiring operator action. This is an USQ.

+ Change to CTMT operating pressure. This was approved by the NRC.

+ Pump Restriction Orifices - Not an USQ

+ Canditions for the use of Direct injection clarified - Not an USQ

+ Increase Allowable Switchover Time to Cold Leg Recirculation - Not an USQ r x g Northeast Nuclear Energy

s -

Accident Analysis

~ ~

~ AFFECTED B THE RSS MdDIFICATIDN ~~

YES NO CORE COOLING Peak Clad Temperature: SB > No Peak Clad Temperature: LB No Long-term Core Cooling No Boron Precipitation Control No

...t

~ ~

CONTAINMENT:LOCA I Peck Pressure No  ;

y. - . .

....._.3 Peak Temperature ,

No '

Post-LOCA Yes ,

i l

Depressurization ,

i~ a Sump femperature No I

Fission Product Removal ! No Offsite Dose No EEO Yes CONTAINMENT:MSLB ,

3

. . _ . . _ _. a_ _

Peak Pressure No Peak Temperature l No .

~

Liner TerrIp'e[ature ~ Yes

.i EEQ  : No

/ x gg Northeast Nuclear Energy 1

L______-__

O

\ /

System Changes

+ Changes to address:

- Suction Flashing

- Water hammer

-Trapped Air

- Expansion joints and piping, component thermal stress

- Pump testing

^

- Vortex Suppression

- 's 19 Northeast Nuclear Energy

p System Changes l

+ Required to assure or improve system design

+ No USQ l

e x gg Northeast Nuclear Energy

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Chariges to Analysis

+ LOCTIC - Containment Analysis

- Modified to model separate RSS trains

- Minor Heat Sink changes

+ Debris Transport

- Addresses start up transient as well as long term

- Similar to NUREG 0897 Rev 1

- Sump changes evaluated with old method

/ 2 y

Northeast Nuclear Energy

9 s -

Conclusions of Analysis

+ LOCTIC changes were minor in nature and acceptable

+ Debris transport changes are acceptable and the new methodology is consistent with NUREG 0897 and was used to evaluate the transient.

Also assessed changes with oid methodology and found them

, acceptable.

/ ---

N 22 Northeast Nuclear Energy l

O

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IPE Insights

• Elimination of Direct Injection

-Increase in CDF (~1X104)

- Direct Injection remained available with operator action l

+ Other Changes

- Either reduce CDF or no change

- PRA insights used in redesign

. RSS mini-flow recirc valve

. Test flow lines

/ N 23 Northeast Nuclear Energy

. Northeast Nuclear Enerpo Comp:ny Millstone Nucie:r Power St: tion Unit 3 oc:

Lillian M. Cuoco, Esquire Mr. WilAm D. Meinert Senior Nuclear Counsel Nuclear F aginee:'

Northeast Utilities Service Company Massachusetts Municipal Wholesale P. O. Box 270 E'ectric Company Hartford, CT 06141-0270 P.O. Box 426 Ludlow, MA 01056 Mr. Kevin T. A. McCarthy, Dimetor Mordtoring and Radiation Division _ _ Joseph R.- Egan, Esquire -

Department of Environmental Protection Egan & Associates, P.C.

79 Elm Street 2300 N Street, NW Hartford, CT 06106 5127 Washington, DC 20037 Regional Administrator, Region 1 Mr. F. C. Rothen U.S. eluclear Regulatory Commission Vice President - Work Services 475 Allendale Road Mortheast Utilities Service Company King of Prussia, PA 19406 P. O. Box 128 Waterford, CT 06385 First Selectmen Town of Watedord Emest C. Hadley, Esquire Hall of Records 1040 B Main Street 200 Boston Post Road P.O. Box 54g Waterford, CT 06385 West Wareham, MA 02576 Mr. Wayne D. Lanning Mr. John Buckingham Deputy Director of Inspections Department of Public Utility Control Special Pro}ects Office Electric Unit 475 Allendale Road 10 Liberty Square King of Prussia, PA 19406 1415 New Britain, CT 06051 Mr. M. H. Bmthers Mr. James S. Robinson, Manager Vice President Operations Nuclear investments and Administration Northeast Nuclear Energy Company New England Power Company P.O. Box 128 25 Research Drive Waterford, CT 06385 Westborough, MA 01582 Mr. M. R. Scully, Executive Director Mr. D. M. Goebel Connecticut Municipal Electric Vice President - Nuclear Oversight Energy Cooperative Northeast Utilities Service Company 30 Stott Avenue P. O. Box 128 Norwich, CT 06360 Waterford, CT 06385 Mr, David Amerine Deborah Katz, President Vice President - Nuclear Engineering Citizens Awareness Network and Support P.O. Box 83  ;

Northeast Utilities Service Company Shelbume Falls, MA 03170 P. O. Box 126 Waterford, CT 06365 i

+t9n l J

\

Northe:st Nuclear Energy Company Millstone Nucl6ar Power Station Unit 3 cc:

Mr Allan Johanson, Assistant Director Mr. Don Schopfer othee of Policy and Management Verification Team Manager Policy Development and Manning Sargent & Lundy Division 55 E. Monroe Street 450 Capitol Avenue - MS# 52ERN Chicago,IL 60603 P. O. Box 341441 Hartford, CT 06134-1441 Mr. J. P. McElwain Vice President (Acting)- Millstone 3 Citizens Regulatory Commission Northeast Nuclear Energy Company ATTN: Ms. Susan Perry Luxton P.O. Box 128

'680 Great Neck Road Waterford, CT 06385 Waterford, CT 06385 Mr. G. D. Hicks The Honorable Terry Concannon Unit Director Millstone Unit 3 Nuclear Energy Advisory Council Northeast Nuclear Energy Company

, Room 4035 P.O. Box 128 l Legislative Office Building Waterford, CT 06385 Capitol Avenue Hartford, CT 06106 Senior Resident inspector I Millstone Nuclear Power Station Legislative Office Building clo U.S. Nuclear Regulatory Commission Captiol Avenue P. O. Box 513 Hartford,CT 06106 Niantic, Connecticut 06357 Mr. Evan W. Woollacott Mr. Manin L. Bowiing Co-Chair Recovery Officer- Millstone Nuclear Energy Advisory Council Unit No. 2 128 Terry's Plain Road Northerst Nuclear Energy Company Simsbury, CT 06070 clo Ms. Patricia A. Loftus Director- Regulatory Affairs Littl, 'iarbor Consultants, Inc. P. O. Box 128 Millstone -ITPOP Project Office Waterford, CT 06385 P.O. Box 06'30 Niantic, CT 06357-0630 Mr. B. D. Kanyon Chief Nuclear Officer- Millstone Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06315 Mr. Daniel L. Curry Project Director Parsons Power Group Inc.

2675 Morgantown Road Reading, PA 19607

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