ML20127B363

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Responds to 840302 Memo Questioning Whether Right Reactor Core Used Consistently in License Submittal & Confirming Whether Reactor Core Referenced in License Section 2.1.2 Actually Corresponds to Core in Reactor
ML20127B363
Person / Time
Site: Grand Gulf, 05000000
Issue date: 03/06/1984
From: Dircks W
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To: Gilinsky
NRC COMMISSION (OCM)
Shared Package
ML19263A614 List:
References
FOIA-84-459 NUDOCS 8403200364
Download: ML20127B363 (5)
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  • Io*g UNITED STATES p NUCLEAR REGULATORY COMMISSION

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MEliORANDUM FOR: Commissioner Gilinsky .,

FROM: William J. Dircks Executive Director for Operations

SUBJECT:

GP.AND GULF REACTOR POWER Your March 2,1984 memorandum, citing four power level values (3323 MWt, 3833 Mut, 3993 MWt and 3876 MWt), questioned whether the right reactor core was used consistently in the license submittal. You also requested confirnation whether the reactor core referenced in license Section 2.1.2 actually corresponds to the core in the Grand Gulf reactor.

As discussed below, the appropriate reactor core was consistently used and evaluated in the licensing process and the reactor. core referenced in the -

license and in the Technical Specifications actually corresponds to"the core in the Grand Gulf reactor.

~The rated core power has been identified as 3833 MWt starting with the initial Construction Pernit (CP) review. As noted on page 1-1 of our CP stage Safety Evaluation Report dated January 1974, "Each unit is designed for a rated thermal output of 3833 MWt. . ." This value also appears throughout the FSAR and the staff's operating license stage SER (See FSAR Section 1.1.1 and SER (0L) Section 1.2 including Table 1.1). The Grand Gulf License NPF-13 cites 5% of full power as 191 megawatts which translates into a core full. power level of 3833 MWt. Further, the Technical Specifications define (Definition 1.33 on page 1-6) rated thermal power to be a total reactor core heat transfer rate to the reactor coolant of 3833 MWt.

The value of 3993 MWt corresponds to an assumed initial overpower condition conservatively used in accident analyses and dose calculations by both the licensee and the HRC staff. This value, which is about 104 percent of rated power, corresponds to a steam flow rate of 105 percent of rated steam flow. 1 Its use is consistently cited in the FSAR (Tables 6.3-2, 15.6-2 and 15.6-5), l in the SER (Section 15.1 and Tables 15.4 and 15.5) in the bashs for the Grand Gulf Technical Specifications (page B3/4 2-3), Table B 3.2.1-1). With regard ,

to FSAR Section 6.3, your memorandum indicated that this section indicated (an '

j overpower level) of 3876 MUt. The 3876 MWt value that had been in 6.3 was  ;

based on GESSAR-238 (having a 238 inch diameter vessel) and was changed to the Grand Gulf specific value (Grand Gulf has a 251 inch diameter vessel) as a result of the staff's review. Table 6.3-2 of the FSAR was amended (Amendment No. 46 to the application) to show that 3993 MWt was used for the core thermal  !

power input in the Loss-of-Coolant Accident Analysis. A copy of the current  !

FSAR Table 6.3-2, which was in niace prior to licensing Grand Gulf Unit 1, is i attached, W wavAe -a  ;

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GG FSAR TABLE 6.3-2 .

, SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT'NALYSIS A

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Plant Parameters o Core Thermal Power MWt 3993 l46 .

.o Vessel Steam Output LB ,/hr 17.3'x 108 o ' Corresponding percent of rated percent 105

' steam flow .

o Vessel Steam Dome Pressure psia . 1060 o Maximum Recirculation Line- ft2 3.1 l<4 6 Break Area' '

Emergency Core Cooling System Parameters ,

Low-Pressure Coolant Injection System

$3 o Vessel Pressure at which flow psid (vessel 225

. de' may commence to drywell) o Minimum Rated Flow at Vessel GPM 22000 "

Pressure '

psid (vessel 20 to drywell) o' Initiating signals low-low-low water level ft above top 21.0 46

'o r of active' fuel  ;

high drywell pressure psig 52.0 l o Maximum allowable time delay sec .

27.0 from initiating signal to pumps at rated speed o Injection valve-fully open sec after DBA 540.0 Low-Pressure Core Spray System .

o Vessel pressure at which flow psid'(vessel 289 may commence to drywell)  ;

i o Minimum rated flow at Vessel GPM 7000 46 Pressure paid (vessel 122 to drywell

GG FSAR TABLE 6.3-2 (Cont.) j l

o Initiating signals -

low-low-low water level ft. above top 21.0 or -

of active fuel 46 high drywell pressure psig 52.0 o Maximum allowed (runout) flow GPM 9100 o Maximum allowed delay time sec 27.0 from initiating signal to pump at rated speed .

46 o ' Injection valve fully open sec after DBA 540.0 High-Pressure Core Sprav o Vessel pressure at which flow psid 1177 may commence -

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o Minimum flow available at see . .

48 vessel to pump suction head _  ?,igur.e 6.3-3 t

-s. o Initiating signals -

~jj low-low water level ft. above top. 210.5- ,

or of active fuel 46 high drywell pressure psig , 12.0 o Maximum ~ allowed (runout) fl,ow 'GPM 9100 o Maximum allowed delay time 'sec 27.0 from initiating signal to . .

rated flow available and injection valve wide open

. Automatic Depressurization System .

o Total number of valves installed 8 o Number of' valves nsed in 8

. analysis

  • 46 o Minimum Flow Cap'acity of '

lb/hr 6.4 x 106 8 valves at vessel psid (vessel 1125 pressure suppression '

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FSAR TABLE 6.3-2 (Cont.)

o initiating signals * *

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low-low-low water level ft above top 21.0 and of active fuel high drywell pressure psig- 52.0 and -

46 o Delay time from all initiating sec 5120 signals completed.to the time valves are open FUEL PARAMETERS o Fuel type --

Initial Core o' Fuel Bundle Geometry --

P8x8R 55 o Lattice .

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'N o Number of fueled rods 62

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o Peak Technical Specification kw/ft 13.4  !

' Linear Heat Generation Rate o Initial Minimum Critical Power --

1.17. l46

. Ratio 1

Amend. 55 4/82 Sheet 3 of 3 .

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