ML19270F206

Summarizes 781211 Appeal Meeting Re Staff Position on Cold Shutdown Capability Per SRP (NUREG-75/087),Revision 1 to Section 5.4.7.Applicant Response Is Insufficient & Matter Remains Unresolved

ML19270F206
Person / Time
Site:	Midland
Issue date:	01/17/1979
From:	Hood D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7902050022
Download: ML19270F206 (17)

Text

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S,S UNITED STATES NUCLEAR REGULATORY COMMISSION 3 T.

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JAN 171979 Docket Nos:

50-329 50-330 APPLICANT:

Consu,ars Power Company FACILITY:

Midland Plant, Units 1 & 2

SUMMARY

OF DECEMBER 11, 1978 APPEAL MEETING ON COLD SHUTDOWN POSITION On December 11, 1978, the NRC staff met in Bethesda, Maryland with members of Consumers Power Company (CPC0), Bechtel Associates, and the Babcock &

Wilcox Company. Attendees are listed in Enclosure 1.

The meeting agenda and other viewgraph slides used during the meeting are shown by Enclosure 2.

The purpose of the meeting was to provide CPC0 the opportunity to appeal the staff's position regarding the capability for cold shutdown as given in Revision 1 of Section 5.4.7 of the Standard Review Plan (NUREG-75/087),

including Revision 1 of Branch Technical Position (BTP) 5-1, " Design Requirements of the Residual Heat Removal System." NRC Task Action Plan A-31 of NUREG-0410 also addresses these matters.

Consistent with the implementation provisions of the BTP, Midland is a " Class 2" plant and compliance is required in accordance with Table 2 therein.

The appeal by CPC0 was made to the Chief of the Reactor Systems Branch and to the Assistant Director for Reactor Safety.

CPC0 Positien_

The Midland design does not incorporate the ability to achieve cold shut-down using only safety grade equipment with only onsite or offsite power avai'able and with a single failure.

Rather, the design provides the ability to achieve, by safety grade means, the hot shutdown condition, and to maintain the hot shutdown condition for an extended period until restoration of offsite power, repairs or other manual action occur such that eventual cold shutdown can proceed.

Details of this CPC0 position are stated in FSAR Revision 14 in response to staff request 211.35.

During nonnal operation, reactor coolant system temperature would be re-duced to 280 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after reactor shutdown and the Decay Heat Removal (DHR) system would then be initiated.

During abnormal operation (i.e., less of ac power) requiring initial cooldown with both of the two atmospheric dump valvas, 280 F would be act.ieved in approximately 46 790205 con >

I Consumers Power Company JAN 171979 hours.

Using only one atmospheric dump valve would require a considerably longer period. The design provides for automatic switchover to the service water system as the inventory of the condensate storage tanks is depleted.

During cooldown without offsite power, this switchover would occur after 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />.

Letdown, in conjunction with high pressure injection from the Borated Water Storage Tank (BWST), is required to achieve cold shutdown in the Midland design if the most reactive control rod assembly is assumed to remain stuck out of the core.

The Makeup and Purification System contains several motor-operated valves with non safety grade controls which must open to achieve letdown and which do not have local handwheels.

CPC0 estimates that if all control rods insert into the core, cold shutdown could be achieved using high pressure injection without letdown if the boron concentration in the BWST were increased about 200 ppm. The letdown system would drain water to tanks and piping not designed to seismic Category I requirements.

Boration from the concentrated boric acid system is achieved through re-dundant trains using pumps which can be powered from the diesels; however, the system is not seismic Category I.

The design lacks provisions for manual actions to reposition power-operated valves.

One atmospheric steam dump valve is provided for each steam generator.

Its relief capacity of 400,000 lb/hr is based upon maintaining hot shutdown rather than achieving cold shutdown, and it is not powered by a Class lE sot'ce.

Handwheels for local operation and isolation valves for mainten-ance are provided.

One power operated relief valve is provided on the pressurizer.

Loss of offsite power prevents operation of this valve from the control room.

Although a local valve operator is provided, local manual operation of the valve would not be practical since the reactor coolant drain tank rupture disc could open releasing radioactivity inside containment.

No high pressure auxiliary pressurizer spray is provided for depressuri-zation. CPC0 stated the pressurizer heater control system and power source would be upgraded to safety grade requirements in FSAR Revision 16.

CPC0 does not intend to conduct tests to study the mixing of the added barated water and cooldown under natural circulation conditions with and without a failed atmospheric dump valve.

Similarly, CPC0 will establish no procedures for cooling down using natural circulation.

Plant construction status is such that all related systems and equipment are either completely installed, or are in latter stages of installation with all components already delivered to the site.

CPC0 estimates the

JAN 171979 Consumers Power Company minimum cost for full compliance for both units would be 7.9 million dollars, excluding schedule impact.

Including interest and replacement power due to schedule impact, CPC0 estimates a total minimum cost of 342 million dollars. CPC0 feels the necessity for cold shutdown has not been adequately demonstrated by the staff, particularly on a value-impact basis, and that full compliance is not warranted for Midland.

Staff Conclusion T:. staff finds that the applicants response to request 211.35 does not provide sufficient information on which to evaluate the capability of the Midland design to satisfy the staff position, whether in whole or in part.

The staff suggested CPC0 revise the response to further indicate system capability.

In this regard, the staff noted that the position provides that repair and maintenance of equipment is acceptable for Class 2 plants if reasonably justified, and that reasonable time periods to achieve cold shutdown can be acceptable. Also, additional analysis with respect to seismic qualification of systems could prove acceptable. The staff remains firm in its position requiring tests to confirm cooldown under natural circulation conditions on M1iland or an identical plant, and its requirement for the establishment of appropriate operating procedures.

Disposition of Issue The matter remains unresolved.

CPC0 intends to revise its response based upon staff guidance during the meeting and will discuss the re-vised position further with the staff at a later date, presently estimated in early February 19'79.

O u

Darl Hood, Project Manager Light Water Reactors Branch No. 4 Division of Project Management

Enclosures:

As stated cc: See next page

consumers Power Company iI ael I. Miller, Esq.

JAN 171979 Ishani, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Judd L. Bacon, Esq.

Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Mr. Paul A. Perry Sec reta ry Consumers Power Company 212 W. Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esq.

Une IBM Plaza Chicago, Illinois 60611 Mary Sinclair 5711 Summerset Dri ve Midland, Michigan 48640 Frank J. Kell ey, Esq.

Attorney General State of Michigan Environmental Protection Division 720 Law Building Lansing, Michigan 48913 Mr. Windell Marshall Route 10 Midland, Michigan 48640 St r.

S. H.

Howell Vice President Consumers Power Company 212 West hiichigan Avenue Jackson, Stichigan 49201

1 ENCLOSJRE 1

.JAN 171979 ATTENDEES DECEMBER 11, 1978 NRC

• R. Tedesco T. Novak P. Matthews G. Mazetis J. Norberg S. Newberry D. Hood S. Diab W. Lefave H. Daniels CPC0 S. Howell G. Keeley R. Bauman M. Salerno J. Zabritski Bechtel J. Clements M. Pratt B&W R. Reed D. Denton Part Time

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[l$/e' JAN 171979 COLD S!!Ur"C'.C !'EETI:!C AGE?IDA REAC203 SYS'!D'.S ERtJICH DECE'EER 11, 1978 1.

Introduction 2.

Midland Fot Standby resi.7n Carability 3

Armlyci a Tine to Achie,re una cut-in condit tonn a.

Botn Dump Valvec Operable b.

One Dxnp Valve Operable h.

Deprennurization and Ecration '41th Safety Grade Equipment a.

Or.orntor Actions licccesary Cut side the Control 200.1 11 liPI (?'ab un find Purif :. cation) 2.

Ictdo m L/cten 3

Boron Recoverv Syste.a h.

Che :ical Addition 3: cte.a b.

Dapreccurizing 3CS ith the Parer Operated 2clief Valvr Includin;; Fote.ntial l'or Quench Tnnk 3natura and Pa.liorsctive Eir/ironvent Incide Contain~.cnt 5

it-te n Circulnt inn era t'eron r"xing Teatn 6.

Operating Procedurec 7.

Plant Construction Status Uith Rc.sard to Ccid Shutdown Systems a.

HPI 1.

Auxiliary r> pray 2.

Pressurizer Spray Valves b.

D'lR Pura Suction V.51vcc c.

Electromatic Relief Vtives d.

Letdown Sycte:

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Cce.ponent Coolin:;.' ate-to Letdown System f.

C':cmical Ant',1 t icn am t,ca.

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Atn.cspheric Dran /alves 3.

Econonic and Sch: dale Impact 9

Imple entatica 10.

Su ;mtion

'tir.ler-o 12 9/73

MIDLAND C00LDOWN FOLLOWING LOSS OF AC POWER USING E5TIMATED LOW FLOW LIMIT FOR MODULATING ATMO5PHERIC DUMP VALVES 600 NOTE:0) MAXIMUM cootDOWN 15100*F/HR g

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COMPONE!ff AITD SYSTEM CAPABILITIES 1.

Atmospheric Dump Valves a.

Seismic Qualification for Boundary Integrity b.

Power Supplies and Controls IIcn-1E Capable of Operation Ascuming Loss of Offsite Pcver c.

d.

Handwheel Provided for Each Valve 2.

HiSh Pressure Injection a.

Seismic Category I b.

Power Supplies and Controls lE 3

Makeup and Purification System (Iotdown)

Seismic Category I and Clacs lE to Containment Isolation Valve n.

b.

Remainder Seismic Qualification for Boundary Inte8rity and Exclusively Offsite Fevered c.

No Provisions for Manual Actions on Power-Operated Valves d.

BRS Syctem has no Scismic Design Basis h.

Chemical Addition System a.

Seismic Qualificatien Downstream Batch Controller b.

A1:nost Entirely Powered From Offsite Cnly c.

Diesel Power Available to Boric Acid Addition Pumps d.

No Provisions ror Manual Actions on Power-Operated Valves 5

Electromatic Relief Valve a.

Seismic Qualification for Boundary Integrity b.

Manual Operation Capability c.

Non IE Pcver Supply MJSalerno 12/7/78

COLD S11UI'DC'G MoDIFICATICIT COSTS CCMPILED 12/5'/78 (a)

Upgrade the Existing !GD Valves to Safety Grade b)

Add h Additional Safety Grade !'AD Valves d)

Motorir.e DIIR Pung Cuetion Valvec el) Upgrade Existing Electromatic Relief Valve and Controls to Claes IE Upgrade Existing Electronatic Relief Valve and Add a Redundant Clase.'E c2 Valve (f)

Provide Safety Grade ILDI Spray Capability (g)

Upgrade Letdown System to Safety Grade (h)

Upcrade Chemical Addition System to Safety Grade All Cocts in $1,0COs M Av h /d And Item a

b d

el e2 f

g h

Material llo h63 26 62 lhh Labor 3h 73 13 lo k9 Subcontract h

h Subtotal Direct Field Costs IG Sho 39 72 193 Dictributablec y

Sh 10 J

35

Tot Prere'tly Total Field Coat 173 59h 79 226 Availno a Eng.i nee r i n., iirwe otTiec N

90

't 1r 3h Enculutton,

'ont in;.cncy S1 1:'6 Ch y

7H Total 1cchtel Cost Units 1 and 2 (Excludin; AFUDC)

• 250 870 80 120 3ho 630 2,100 2.h00 Consumera Power overheads 59 205 19 28 So 142 kg6 566 Total Cost Excluding Schclule Impact M 1075 02 lh8 h20 Th2 2,596 2,o66 Mininum Full Compliance Cost Excluding Schedule Impact (a, b, d, el, f, g, h) 7,935

' (4F UDC = al% ~r y,f.J< p.-) Jialq ce. f ~ I k IUSalerno 12/6/73

SGEARY OF SQEDULE EtPACT (a)

Upgrade the Exictinn !'AD Valves to Safety Grade (b)

Add h Additional Safet? Grade MAD Valves (d)

Motorice DI!R Pump Cuction Valves el) Upgrade Existin;; Electrc ntic Relier Valve and Controls te Class 1E e2) Updrade Exicting Electromatic Eclief Valve and Add a Redundant Clacc II 7a;ve (f)

Provide Safety Grade HPI Spray Capa'oility (g)

Upgrade h tdown Syctem to Safety Grade (h)

Upgrade Q1enical Addition Systen to Safety Grade All Cocto in $1,000,0C0

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Item Delay

/u"UDC Cost of Power Total Delav Cast a

Unit 2 - 7 Months 34.8 57.4 92.2 b

Unit 2 - 7 Months 34.8 57.h 92.2 6I.9 100.1 lini.t 1 - 11 Months h h. ".

6 d

tinit ?

14 fiont.hn 39.H M. I, 105. '.

el t> nit ? - 5 Montha Ph.t) hl 65 9 e2 Unit 2 - 18 Monthc*

89.o 147.6 237.2 f

Unit 2 4 Months 19 9 32.8 52 7 r;

Unit 9 - Yl "onthn

• 84.7 139.h 22L.1 h

linit ? - 10 i&,nths h9.8 62 ll i. >

Minin,m Full Cc=nliance+

Schedule Dnpact Coct (h tc) 333.8 Mini::au.i Total Contax (Cenctruction and Ocneilule Lapact) 341.7 MJSalerno 12.u:- l7d

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14 January 1973 - Reviced Implementation for MRC "'ack Action Plan A-31 rt. Creatc<l rnore <!crinite irnplemen t..ti cn D3.in's.

Pl in t.

r! t.c Pinnt Ctitun P'rnt 1 > d e en' i nn I

All plants (cuctct or standard )

Full cc.p]iance with revision to CRP ~.h.7 CP cr PD/i docketed after then:

Full ec..nliance ith January 1, 197,a, Regulatory Guide 1.179 II All plants (cuc: cat or standard)

Partial ecmpliance CD or PDA dec':eted before Guidance of Table 2 Januttr7 1, l'rl3 01, i ? :.u n n,. :: r c ' e t i t' t < ?

.T: tu'i t

1, I 'f,' O III All operat!'. plants Cac e-by-C:: c t: IMc i n 01, 1: :uance.,: ncr u.nl h: fore Cor thin ~1 I M' ti. ! "CH J:tnu:trY l, l '17')

reviev

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a REGUIAT0!iY GUIDE 1.139 IM PI? _"_";T,' ?_rn::_ _.

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in whi.h t b.

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n n e c e t. t. t.1 < -

1' r-ntiti ve ne t hs,1! For c.

,.:u,.;i i h t h.. 1;,ciCied porLicrn, ol the '.. ". i : i on '-

ret;ulaiiona, t.h : m.c t no ri described herein vi]l bc used in the evalu c. en of cub.ittals in connecticn wit'i

'licatienc for cenctructicn pcr.it fcr 111 planta (r.tand

trd rind cuatcm ), r :.ufac tu r' 'n.c licencec, and prelir:u nry ricci:.a or nf t r J:.. n ?.* 3, 3978 All ut nl i ention:- !oct;"Lc !

apprrvals doc!:eted o befo c,1u.u"zy 1, ]970 zill ur. r e 2 <;wed :n Jti:'. : t thi c <*.uid e en rt c:., e -1, 7 -c it. : n a

bacic.

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