ML20235C401

Informs That on 740821,agreement Reached to Assist Arcs in Early Identification of Potential Problem Areas & Potentially Difficult Novel Features for Each Application. Comparison of Principal Design Characteristics of NSSS Encl

ML20235C401
Person / Time
Site:	Grand Gulf, 05000000
Issue date:	07/17/1978
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Lawroski S Advisory Committee on Reactor Safeguards
Shared Package
ML20234E460	List: ML20234E457 ML20234E570 ML20234E632 ML20234E685 ML20234E736 ML20234E798 ML20235B143 ML20235C320 ML20235C384 ML20235C401 ML20235C457 ML20235C519 ML20235C563 ML20235C636 ML20235C736 ML20235C753 ML20235C830 ML20235C896 ML20235C907 ML20235C912 ML20235C926 ML20235C931 ML20235C941 ML20235C944 ML20235D492 ML20235D516 ML20235D643 ML20235D684 ML20235D736 ML20235D963 ML20235E005 ML20235E021 ML20235E056 ML20235E199 ML20235E244 ML20235E571 ML20235E583 ML20235E615 ML20235E659 ML20235E682 ML20235E732 ML20235E841 ML20235E873 ML20235E912 ML20235E949 ML20235E964 ML20235F083 ML20235F117 ML20235F637 ML20244B882 ... further results
References
FOIA-87-40 ACRS-GENERAL, NUDOCS 8707090405
Download: ML20235C401 (4)

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f,og NUCLEAR REGULATORY COMMISSION

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Docket Nos: 50-416 & 50-417 Dr. Stephen Lawroski, Chairman ense gucTos DM* G ffsI:e Advisory Committee on Reactor Safeguards jijl., i 9 N U. S. Nuclear Regulatory Comission Washington, D. C. 20555 RE .["' '

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Dear Dr.'Lawroski:

SOE!JDCT: REGULA20RY STAFF SUPPORf OF ACitS ACTIVITIES ON GRNID GULF OPERATING LICENSE APPLICATION (GRAND GULF NUCLEAR STATION, UNIT NOS. 1 AND 2)

On August 21, 1974, we agreed to assist the Comittee in the early identification of potential problem areas and potentially difficult novel features for each application. On October 28, 1976, we further agreed to advise the Committee whether our acceptance reviews of tendered applications revealed any features of the application that cause a particular problem relative to any of the Comittee's generic items. We have completed our acceptance review of Mississippi. Power

& Light Company's Grand Gulf Nuclear Station, Unit Nos.1 and 2 operating license application and provide the following information in response to these agreements.

Tne Grand Gulf Nuclear Station is located on the east bank of the Mississippi River in Claiborne County, Mississippi, approximately 25 miles south of Vicksburg, Mississippi. Each unit utilizes a General Electric Company BWR/6 boiling water reactor and a Mark III vapor suppression containment. Each unit is designed for rateo thermal and net electrical outputs of 3833 and 1250 megawatts, respectively.

Unit 1 fuel loading is scheduled for October 1980 and Unit 2 fuel J loading is scheduled for July 1983. The Grand Gulf Nuclear Station is the lead BWR/6, Mark III containment plant.

The principal design characteristics of the Grand Gulf iMR/6 nuclear -

steam supply systems are similar to those of GCSSAR-251 and GECSAR-238.

A comparison of the principal design characteristics of the Grand Gulf, GESSAR-251, and GESSAR-238 nuclear steam supply systems is presented in the Enclosure.

The Grand Gulf Mark III Containment structures and suppression poola are cylindrical steel-lined, reinforced concrete structures with internal design temperatures and pressures of 185 degrees Fahrenheit and 15 pounds per square inch gauge, respectively.

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Dr. Stephen Laaroski July 17, 1978 l The drywells are basically cylindrical reinforced concrete with flat concrete roofs and steel refueling heads, and have internal design temperatures and pressures of 330 degrees Fahrenheit and 30 pounds per square inch gauge, respectively.

The Grand Gulf turbine-generators have been supplied by Allis-Chalmers Power Systems, Inc.

The fuel design has been changed to include two-water-rod 8 x 8 fuel assemblies instead of the one-water-rod fuel assemblies reviewed for the construction permit application. However, the modified design type has been previously reviewed on other BWR applications.

We expect that a raajor effort will be needed on the review of the test'information related to the dynamic loadings on the Mark III containment in order to verify the adequacy of the load criteria approved for the construction permit.

Our acceptance review of the Grand Gulf application did not reveal any other potential problem areas or difficult novel features.

Sincerely, D. B. Vassallo, Assistant Director for Light Water Reactors Division of Project Management  ;

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Enclosure:

Comparison of Principal Design Characteristics of Grand Gulf, I

GESSAR-251, and GESSAR-238 Nuclear Steam Supply Systems l

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l tilCLOSURE CO!PARISOU OF PRINCIPAL DESIGu CiiiOMCfERISTICS OF GPMD GULF, GCLSAH-251, AND GES3/V1-23o NUCLEAH S'1Livl SUPPLY SYdfGIS 1

i ChAHAJi'ERIS1'1C GfW4D GULF GCSSAR-25] JCSsAi: .'3s Rateo Core Thermal Pouer Level, megawtts 3833 3000 Design Core Poser Level, vegawatts 3579 4025 3676 37bJ Steam Flow Hate, 106 poun'Js per hour 16.491 Core Coolant Flow Eate, 106 r'ounds por hour 16.351 13.4 112.5 122.5 10:-

ceeawater flow Hate, los p7unds car hour 16.455 10.306 l '- '

Hominal Syster.i Pressure in Steata Doue, pounds per sauare inch aosolute 1940 104U lu40 Avera y) Fower Density, kijouatts per liter 51.1 51.3 Se . '

Maximo. 't1:er.nal Output, kilowatts per foot 13.4 13.4 daxir.n. tioat Flux, British Thermal Units 13.4 per nour square toot 362,000 324,500 3 5 i ,-

Maximu.a Fuel Temperature, degrees Fahrenheit 3430 3337 J371 Minimur. Critical Power Ratio 1.07 1.07 L.

coolant Cntnalpy at Core Inlet, Gritish Thorual Units per pound 527.9 529.9 5 '7 Core Maximuu Cxit voids Within Fuel' Assei.olies, pereent 76 75 i>

/eedwater Teracerature, degrees Fanrenheit 420 420

.Juncer of Fuel Assel.d>] ies 4a 600 840 U2 Fuel itou Array 8x6 8xB  %+

Fuel RoJs Per Fuel Assemoly 62 63 o .<

Uater Poas Per fu?1 Assemoly 2 1 1 Wumber of Control Rods 193 205 1,;

dumoer of Fixed Incore Deutron Detectors 176 167 iei leactor Vess'l Design Pressur e, pounuc per square inch gauge 1250 1150 I ..

Reactor Vessel Design Mmeerature, degrees Fahrenheit 575 575 bib Reactor Vessel Insiue Diatueter , inches 251 251 2 h.

heactor Vessel height, feet - inches 73-0 73-0 Reactor Vessel Base tietal Tnickness, inches 70-ic 6.14 6.14 5.7 Reactor Vessel flinimum Cladding Thickness, inches 0.125 0.125 0. ] :

dumoer of Recirculation Loops 2 2 2 Recirculation Loop . Pipe Diameter, inches 24 24 22/21 Recirculation Flow Rate, gallons per minute 44,900 47,100 35, M '

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GPMD GE7SAR GLSSAn CHrWCTEllISTIC GULF 251 238

- Nurber of Jet Pungs 24 24 20 Number of Hain Steau Lines 4 '4 4 Main Steamline Diameter, inches 2B '2d 2u I Number of Safety-Relief Valven 20 22 19 Number-.of Low Pressure Core L . Spray Systeu Loops 1 1 1 l -Low Pressure' Core Spray System- 7115 at _128 7000 at 122 0000 at J r Flow Hate, gallons per minute

. Ibs per sg . _

lbs per sg Jbs per sg I in differential in differen- :in cifferen pressure tial creesure tihl pr.u-dumoer of.High Pressure Core Spray Systen Loops 1 1 1

! High Pressure Core Scray Systeu Flos 1650 at 1147 los 1650 at 114/ Jos ' 1465 at 111

) Rate, gallons por minute per sq in dif fer per sy in differ Jbs per 2.

l ential pressure ential pressure. offfereuti>

pressure 7115 at 200 lbs 7000 at 200 los 6000 at 2vi per sg in dif fer- per sg in differ los per sq ential pressure ential pressure differenti1

, pressure Numoet of Automatic Depressurization __

Systeas 1 1 1 Nuraber at Valves in Automatic Depressuris:ation System 6 3 6 Humber of Low Pressure Coolant Injection Systems J l 1 Nurrmt of Lou Pressure Coolant Injection System Pumps 3- 3_ 3 Low Pressure Coolant Injectiun

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7450 at 24 lbs 7450 at 30 les 7100 at 3v Systeu Pump Flow hate, gallons - per sg in difier per so in citter- lbs oer s.i i per minute ential pressure enti.31 pressure offierent i' pressuie Resiuual Heat Removal System )

-Pumps 3 3 3 Residual Heat. Removal System Pump Flow Rate, gallons per minute 7450 7450 '7450 LNumber of Residual Heat Removal System Heat Exchangers 2 2 2 Number of Reactor Core Isolation

-Cooling Systems 1 1 1 Reactor. Core Isolation Cooling 800 at 1120 lbs 800 at 1147 los 700 at 1120 System Pump Flow, gallons per per sq in differ- per sy in differ- Ibs per s.; i minute ential pressure ential pre ssure differential pressure

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