ML20052D633

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Restart of Core Spray & LPCI Sys on Low Level,NUREG-0737, Item II.K.3.21,LACBWR, Informal Rept
ML20052D633
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 03/31/1982
From: Morken D
EG&G, INC.
To: Mauck J
Office of Nuclear Reactor Regulation
References
CON-FIN-A-6427, TASK-2.K.3.21, TASK-TM EGG-EA-5649, NUDOCS 8205070019
Download: ML20052D633 (8)
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RESTART OF CORE SPRAY AND LPCI SYSTEMS ON, LOW LEm.

NUREG-0737, ITEM.I.K.3.21 LA CROSSE BOILING idATER REACTOR

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Operating Meactors - TMI Lessons Learned, NUREG-0737 Moor w

.31 t-Subeset of ens w Restart of Core Spray and LPCI Systems on te. mevel, y E G-0 " '

Iten II.K.3.21, La Crosse Bot;ing Water Rea t.)r Informal Report Au8teNok D. J. Morken Does of Documeent:

March 1982

'P'= NRC ledMduel and NRC Office er DMeion-J. L. Mauck. Division of Systems Integrat' ion This document was prepared primarity for pre 6eminary or mismalose a a i

full review and approval Since there may be substantive changee,. th L f c -

pot be Cortsidered final EG&G idare t r' c icano Falls Idan" 83415 Prepared fc,r tt

  • U.S Nuclear Regufatorv imrmswr.

Washing!co. J Under DOE Contract No. DE AG7 76 ;00' 510

.NRC FIN No _$b INTERIM RE* li 4

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RESTART Or CGtE SPRAY AND LPCI SYSTEMS ON Low LE vE ENtEG-0737, ITEM II.K.3.21 LA C905SE BOILING b6ATER REACTOR Docket No. 50-409

b. J. Morken Reliability and Statistics Brandh Engineering Analysis Division EGE. Idaho, Inc.

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Inis revism evaluates Dairyland Power Cooperative's assessm.t restart of core spr4r and low pressure core injection on low reacte.ater level at la Crosse Soiling Water Reactor (rJREG-0737, Item !!.K.3.?!'

l FOREWORD This report is submiitted as a sart of the, " Operating Reactors-7

Lessoas Learned, EREG-0737 Response Evaluation" being conducted for ne U.S. aucleer Regulatory Casuitssion, Office of Nuclear Reactor Regaldt on.

Dietsien of Licensing, by EG&G Idaho, Inc., Reliability and Statist :c' Branch.

The U.S. Nuclear Regulatory Commission funded the erk under ne authorization B&R 20 19 01 06, FIN No. A6427.

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2 y.y CONTEM15 1.0 INTD000CTION................

2.0 OE S IGN 8ASE CR I TER I A.............

3.0 D ISCUS$ 10N AND EVALOAT ION............

3.1 Nigh Pressure Core Soray System........

3.2 Al ternate Core Sor ay Sys tem...............

9 4.0 ConCLUS10a5.................................

5.0 REFERENCES

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RESTART OF CORE SPtAY AND LPCI SYSTEMS Oh ;y Lt.L 1UMEG-DIJ/, IILM II.K.3.2i LA CROSSE 50RI% WATER RUC70R 1.0 INTR 000CTION On my 7,1980, the istC requested tne Dairyland Power Cooperatie (DKo) to assess the capabil' tty of the La Crosse Sciting Water Reactor 1

ce spray and low pressure coolar.t injectiun systems to restart automatica: ? y on loss of reactor water level af ter coolant flow nad been stopped by t:,

i reoctor operator. IPCo was also requested to propese design'modificatiom to meet the requirments of the letter including a discussion. of the des ~ v with respect to Settions 4.12, 4.13, and 4.14 of IEEE St andard 279-197' supporting information, drawings and changes to technical specifications.

responded to the IWtC's request by a letter dated Septemer 3.

1980.

This' report evaluates the la Crosse compliance wit % the NRC requir e ents.

2.0 DESIGN BASE CRITERIA The design base criteria that were applied for this tasi are contau r in the May 7,1980, letter from lett to OKo.

The NRC position states -ine core spray and low pressure coolant injection (LPCI) system flow teay be stopped by the epirrator. These systems will not restart automatically oc loss of water level if an initiation signal is still present. The core spray and LPCI logic should be modified 50 that these systees will restart i

if required, to assure adequate core cooling."

dard 279-1971,jan of syste design should be in accordance with 'EEE Stan-Modificat Section 4.12, 4.13, and 4.16.

3.0' OISCUSSION AfD EVAtuATION La Crosse Be111mg idater Reactor amergency core cooling consists of tre high pressure' core spray 'systen and the alternate core spray system.

The following is a brief description of the existing core spray systems and a discussion of has they compare with the design base criteria.

j 3.1 Migh Pressure Core Spray. The hign pressure core spray (HPCS) systs consists of to core spray pumps, piping, and valves. The manual and remote operated valves in the HPCS flow path are normally open whene. -

the reector is pressurized and boron injection has not been started.

Initiation of the HpCS is from redundant high containment presse e i

switches or redadant low reactor water I Either function will automatically start both HPCS pung;..gvel switches.

The HPOS peu ny be stcppec by manually switching the pump control switches to the sf f.ios i t i o n. >If pop is switched to the off position, the switch is spring loaded to rete -

to the automatic position den the handle is released.

A reactor low w t.

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level. Signal will %eediate!y restart the pumc.

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handle in jhe pullout position can the opera't ton v tme NP:' :, cr s 1

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Evaluation: Drasings were not available for deta ?ed o nbat s neference letpes indicate the **CS is in comoiiance a ttn W N-Sii. > -

tion Ilc.3.21 and IEEE Standard 279-1971.

3.2 Alternata Cere Spray System ( ACS). The ACS is the cr nc o'e em i ters, emergency cere cooling iystem. _ The ACS consists of two oiesel crive

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pieups. automatic valves, and antaastic, start Togic. High cont ainment ore Sure will start he'h pumps. Les reactor unter level opens tne automat ic

' valves pensitting AC$ flow to the spray nozzle when reactor pressure is helen he psty. lenen mater tevel in the reytor rises above the tr?p le n let point, the atomatic valves close. The valves will conti,ue to :yc ?e te ea' stain a cwstant water level tri the reactor. The engine driven cumps renda la operation as long as centalnment pressure remains high.

The matematic valves have manual key operated off on control switcner wits the t metatained under administration control. The engine ar ner Simps altc annual off switches to perett survei lance 'nd testing.

[ Evalmetten: Dramings were not available for detailed evaluatten.

teferenced letters indicate that the ACS is in, compliance with NUREG-0737, Sectten !!.E.2.31. Manual stopping of the diesel pumps is indicated in the centrol reen by red ammisaciatars. Manual closing of the automat)c valves ts tedicated by red and green indicating lights above each switch.

'd.0 COELitS!0R$

The high pressure core spray and alternate core spray systems of Le Crosse Set 11os unter Rgactor da meet the requirements of NUREG-0737, Secttom 11.E.3.21 for automatic system restart.' They also meet the requirements of IHE Standard 279-1971 for indication in the control room when stopping the core spray pisaps or closing the alternate core spray valves.

La Crosse Technical Specifications Sections a.2.2.15 and 4.2.2.13 provide adequate control of the saeval bypass of the Core Spray Pump anc alternate core spray automatic valves.0 5.0 PEFERE EES i

1.

IRC letter, Eisenhut to all operating reactors, dated May 7, IE.

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OPCo letter, Linden to D. E. Eisenhut. Subject- "DPCo La Crosse Boilir, Water Reactor Provisional Operations License llo. CPR-45. "Additiona t -

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TMI Requirements", LAC-7112, dated September 3,1980.

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IEEE Standard 279-1971, "Criterie for Protection Syster=s for Nuclear Power Generating Statfons'.

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/.Taree Mile tiland Short Teca Lessons Learneo. LAC-676), dat :c

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5. " 1 EMS-0737, "Ciarif' cation of TMl Action Plan Requirements" f.x:eu l

pg Regulatory Comission. Office of Nuclear Reactor Regulations.

S.^, Appedt s A,te Prov is ional Oper ating Authoa iz ation No. OPR A-6 T e cn n s c a -

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g/'. 5pecifications for the La Crosse Soiling ndeter Renctor (LAC BW ).

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