ML20236R258

Summary of 870827 Meeting W/Util Re Design Adequacy of Nuclear Svc Sys.List of Attendees & Meeting Agenda Encl

ML20236R258
Person / Time
Site:	Catawba
Issue date:	11/18/1987
From:	Jabbour K Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8711230184
Download: ML20236R258 (10)

Text

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,#[ o g UNITED STATES 4 y p, NUCLEAR REGULATORY COMMISSION 7,, j WASHINGTON, D. C. 20555

• % ** ,s / NOV 181987 Docket Nos.: 50-413 and 50-414 LICENSEE: Duke Power Company FACILITY: Catawba Nuclear Station, Units 1 and 2

SUMMARY

OF AUGUST 27, 1987, MEETING WITH DUKE POWER COMPANY ON THE A9EQUACY OF NUCLEAR SERVICE SYSTEM DESIGN FOR CATAWBA NUCLEAR STATION, UNITS 1 AND 2 General On August 27, 1987, the NRC staff met with Duke Power Company (DPC) repre-sentatives to discuss the design adequacy of the nuclear service water (RN) system for Catawba Nuclear Station, Units 1 and 2. A list of attendees and the meeting agenda are included as Enclosures 1 and 2, respectively.

Discussion After brief introductory remarks, the NRC staff noted that during the Quality Validation Inspection Audit conducted at Catawba from July 13 through July 24, 1987, the staff has reviewed the Catawba RN system design and raised concerns regarding whether this system satisfies the necessary General Design Criteria (GDC) 5 and 44.

Subsequently, by letter dated Au staff requested DPC to provide (gust1) an7,1987, analysispursuant justifyingtothe 10 adequacy CFR 50.54(f), of one the RN pump to serve both units or (2) a description of actions implemented or planned to be implemented that would justify continued plant operation. By letters dated August 14 and 21, 1987, DPC responded to NRC staff concerns. The purpose of the meeting was to provide further clarification and discussion of DPC submittals regarding this matter. DPC presentation is summarized in the following paragraphs.

1. Description of the RN System DPC representatives described the RN system using the viewgraphs included as Enclosure 3. The system consists of two redundant trains, A and B, of essential equipment per unit. Both trains are fed by gravity flow from either Lake Wylie or the Ultimate Heat Sink, (Standby Nuclear Service Water Pond (SNSWP)), and some sections are shared between units. The A train is supplied by two A RN pumps and the B train by two B pumps. An A and a B pumps are designated for each unit and are powered from separatt, emergency power sources associated with that unit.

The A and B pumps are interconnected by a common discharge header such that operation of any two of the four pumps is sufficient to supply all cooling water requirements for the two units for startup, cooldown, refueling, or post-accident 07112301B4 871118  !

DR ADOCK05g}43

4 operation including a LOCA in one unit and shutdown cooling of the other unit.

During normal operation only one pump is needed. The crossover connections be-tween trains A and B are automatically isolated on a High-High containment pressure or Low RN pump pit level signal to ensure train integrity. Thus, DPC's position was that the requirements of GDC 5 and 44 were met. Comments regarding heat load analysis, fouling and periodic cleaning of heat exchangers were also discussed.

2. Procedures for Technical Specification Compliance DPC representatives stated that, because some sections of the RN system are shared between units, Technical Specification (TS) 3.7.4 was inadequate in that the Action Statement did not specify its applicability to both units. Thus, in order to operate the station in conformance with the accident analysis and the thermal-hydraulic capability of the RN system, plant procedures were revised ,

in 1986 to require both units to enter the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Action Statement any time a diesel generator on either unit is removed from service. It was also stated that prior to an emergency diesel generator being or expected to be out of l service for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more, plant procedures re unit be placed in a non-degraded condition by (1) quire that thethe pre-aligning unaffected unaffected train for SNSWP (Ultimate Heat Sink) recirculation and (2) isolating or other-wise restricting flow to the degraded train of the degraded unit in a manner which ensures adequate post-accident flows to components on this affected train of the other unit. Following this realignment, the unaffected unit (unit not directly associated with inoperable diesel generator) was taken out of the Action Statement, because it was thought that following the realignment and shutdown of the affected unit, adequate flow was available to supply post-accident heat loads in the unaffected unit given any single active failure, i.e., two complete OPERABLE loops were restored to the operating unit as required by TS. Subsequently, DPC discovered that even after the pre-alignment, a single failure vulnerability existed in the unaffected train in that the single suction valve to the pump pits could close resulting in the loss of both pumps in the unaffected train. Thus, DPC revised the pre-alignment procedure to remove power to the opened RN valve between the SNSWP and the pump pit of the unaffected train. In this situation the unaffected train would not be susceptible to a single active failure.

The staff noted that DPC should have requested a TS amendment as soon as the problem was identified because the TS must reflect the as-built condition of the plant.

3. Enhancements to the RN System l

DPC representatives stated that the transfer from Lake Wylie to the SNSWP as a source of water for the RN system, in the absence of the loss of Lake Wylie represents an unnecessary challenge to the associated valves. Two modifications are in progress to reduce the potential for these challenges: (a) a modification to remove the High-High containment pressure signal that realigns the RN pump suction from Lake Wylie to the SNSWP which should be implemented prior to the completion of Unit I refueling outage in December 1987, and (b) additional I

transmitters will be added to the pit level instrumentation to go from a 1 out of 2 logic to a 2 out of 3 logic which is targeted for 1988.

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h0V 181987 Conclusion DPC representatives agreed to request a TS amendment that would reflect the as-built condition of the plant and to submit the analysis for one pump supplying both units. q t

\

i6 Kahtan N. Jabbour, Project Manager Project Directorate 11-3 Division of Reactor Projects, I/II

Enclosures:

As stated cc: See next page i

l l

l J

h SEEPREp00 CONCURRENCE D (

PD#II- R -I/II C/PSB/ DEST PD#11-3/DRP-1/II KJabbour/mac *JCraig LCrocker, Acting PD 11/l 6 /87 1/12/87 11//g/87

i Mr. H. B. Tucker Duke Power Company Catawba Nuclear Station cc:

A.V. Carr, Esq. North Carolina Electric Membership Duke Power Company Corp. l 422 South Church Street 3400 Sumner Boulevard Charlotte, North Carolina 28242 P.O. Box 27306 Raleigh, North Carolina 27611 J. Michael McGarry, III, Esq.

Bishop, Liberman, Cook, Purcell Saluda River Electric Cooperative, ,

and Reynolds Inc. 2 1200 Seventeenth Street, N.W. P.O. Box 929 '

Washington, D. C. 20036 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident Inspector . i Suite 600 Route 2, Box 179N i 3100 Smoketree Ct. York, South Carolina 29745 '

l P.O. Box 29513

! Raleigh, North Carolina 27626-0513 Regional Administrator, Region II  :

U.S. Nuclear Regulatory Commission,  !

l L.L. Williams 101 Marietta Street, NW, Suite 2900 Area Manager, Mid-South Area Atlanta, Georgia 30323 ESSD Projects '

Westinghouse Electric Corp.

l MNC West Tower - Bay 239 P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health

l South Carolina Department of Health I and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 l County Manager of York County l York County Courthouse Karen E. Long .i York South Carolina 29745 Assistant Attorney General N.C. Department of Justice P,1 chard P. Wilson, Esq. P.O. Box 629 Assistant Attorney General Raleigh, North Carolina 27602 S.C. Attorney General's Office P.O. Box 11549 Spence Perry, Esquire Columbia, South Carolina 29211 General Counsel Federal Emergency Management Agency Piedmont Municipal Power Agency Room 840 100 Memorial Drive 500 C Street Greer, South Carolina 29651 Washington, D. C. 20472 Mr. Michael Hirsch Federal Emergency Management Agency Office of the General Counsel I Room 840 500 C Street, S.W.

Washington, D. C. 20472 Brian P. Cassidy, Regional Counsel Federal Emergency Management Agency, Region I J. W. McCormach POCH hh cheemrumwc4 cm m

4 Enclosure 1 Attendance List August 27,.'1987 NRC Duke Power Company K. Jabbour R. Sharpe J. Craig H. Barron l

F. Rosa- D. Ward G. Lainas* D. Eaves-J. Wenniel T. ' Wyke W. LeFave W. Hill '

L. Norrholm

'K. Parczewski l S. Brown  !

P. Van Doorn l

.B. Bonser i D. Hood W. Troskoski G. Brown

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l 1

Part-time attendance

Enclosure 2- 'j CAT *wsA Nuct.3AR aTAT20N n chant savIct wA m erstiet m a in u meratt a to o m a ASBIDA

1. Functional dG80'tiption of system operation.

2. Plant procedures for Tech'apee coinpitane..

3. Other accident and failure seenarios.

4. Itodificationsinprocessforenhancedsystemreliability.

4

. . men w unuma graygg - ---

NUCLEAR SERVICE WATER SYSTEM i

SNSW Lake 28 1A (7 A Wylis M 3A 48 6B ysQ--Q<0 5A Lake wy1je l

I 4

i ir 1r v o se #2A #2 #2B 2A ESS N-ESS ESS D/G o ^ 4 -

t 67A D/G 488 47A 69B X X X X 1 l

~""

1 67A 488 47A #

69B sr Dx0 X X X 0/0 1A v v ,,

Component #1 1B N-ESS Liquid Cooling Essential

Header Waste Containment spray Control Room 59 -

Cooling Assured Aux 52B 2B Feedwater ESS 2A ESS o sr <,

<r <r 57A 8438 54A 53B 63A #2 l

58B N-ESS 2A 1A IB 2B D/G D/G D/G D/G e o SNSWP SNSWP l

LAKE WYLIE lA SA SNSWP-28 3A 48 2

' PRESSURE SERVICE WATER u y v y LIQUID WASTE 67A 488 47A X X -

X X 69B k232A232A 49A 292B 1A' D/G 1A 50B IB l'B f2928 ESS ESS NON D/G W h HDR ESS 847A 846A 51A p s 52B B498

--.n 67A 48B 47A 69B 2A

'M X X '

X 847A D/G 49A 2B M 2A 50B 2B D/G 846A ESS NON ESS HDR 8498 ESS HDR p

8488 8488 52B g )u v 54A 53B 57A 8438

[63A

[58B V

SNSWP "

m e

m_______ _ _ _ _ _ . _

CATAWBA NUCLEAR STATION

,. NUCLEAR SERVICE WATER SYSTEM UNIT 1~,'A TRAIN ESSENT!AL HEADER FROM A TRAIN' RN PUMPS i

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IRN232A 1RN67A 2RN67A 2RN232A 0-D/G

[ 0-SS '

START k(

{ -} 1 l

D/G M 1A 1RN48B 1RN287A 1RN144A 'C-SP(1)'

0-SS

[1RN250A.

0-LOW PRESSURE C-SP(2) l WITH LPL(A)1

-1RN236

{ CONTAINMENT CONTROL' COMPONENT SPRAY HX AUXILIARY ROOM .j 1RN847A COOLING HX FEEDWATER CHILLER C- (A,B) SUPPLY l

1RN846A 1RN291

[1RN148A 5(1RN244A 4

CHILLER l

0-LPL(A,B) 1RN835 .

syLYE*" X RN57A

><a )

RN8438 RN63A 4 C-SP l o.3p C-LPL(A,B) 0-LPL(A,B)

F' SNSWP 1

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l MEETING

SUMMARY

' DISTRIBUTION l

)

32fiD6Efit((ilet, fiOV IS E67- NRC Participants 'l

- NRC PDR K. Jabbour L PDR J. Craig '

NSIC .

F. Rosa-PRC System G. Lainas L PD#II-3 Rdg J. Wermiel L Project Manager K. Jabbour W. Lecave M. Duncan W. Hill  ;

L B. Kolostyak L. Norrholm l

W. Troskoski (MNBB 6113) 'K. Parcezewski 1 OGC-Bethesda S. Brown i ACRS(10) D. Van Doorn B. Bonser ,

D. Hood )

-W. Troskoski  !

G. Brown OTHERS 1 J. Smith i

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bec: Licensee & Service List .;

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