ML20148S480

Forwards Cycle 6 Core Design Info Identifying Reactor Core Locations Containing Control Rods & Fuel Assembly Burnup at Rodded Locations,As Committed in 960408 Response to NRC Bulletin 96-001, Control Rod Insertion Problems

ML20148S480
Person / Time
Site:	Seabrook
Issue date:	06/30/1997
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-001, IEB-96-1, NYN-97071, NUDOCS 9707080238
Download: ML20148S480 (5)

Text

-

h i % rth North Atlantic Energy Service Corporation P.O. Box 300 Atlantic Seasroot,su o3874 (603) 474-9521 i

The Northeast Utilities System June 30,1997 Docket No. 55-443 NYN-97071 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555 Seabrook Station Cycle 6 Information for Bulletin 96-01 North Attentic Energy Service Corporation (North Atlantic) responded to NRC Bulletin 96-01',

2

" Control Rod litsertion Problems" on April 8,1996. North Atlantic committed in its response to NRC Bulletin 96-01 to submit, upon completion, Cycle 6 core design information identifying the l

reactor core locations containing control rods and the fuel assembly burnup at the rodded

^

locations. The design of the Cycle 6 core has been completed and the committed core design information is enclosed. Cycle 6 operation of Seabrook Station commenced on June 28,1997 with the resumption of generation following the fifth refueling outage.

Should you have any questions regarding this letter please contact Mr. Terry L. Harpster, Director of Licensing Services, at (603) 773-7765.

Very truly yours, NORTH ATLANTIC ENERGY SERVICE CORP.

1 Ted C. Feig(Y

~

l

/

nbaum j

Executive Vice President and ChiefNuclear Officer

' NRC Bulletin 96-01," Control Rod Insertion Problems" dated March 8,1996 2

Nonheast Utilities Letter, "Haddam Neck Plant, Millstone Nuclear Power Station, Unit No. 3, Seabrook Station, Response to Bulletin 96-01" dated April 8,1996 fflfyg{flEla@lPMEHH 9707000238 970630 lmagg PDR ADOCK 05000443 sm 4

o 1

g pg j

i U.S. Nuclear Regulatory Commission NYN-97071/Page 2 cc:

H. J. Miller, Region I Administrator A. W. De Agazio, Sr. Project Manager, Seabrook Station W. T. Olsen, Sr. Resident NRC Inspector 4

i Y'

)

i I

ENCLOSURE 1 TO NYN-97071 j

i i

i l

4 1

I i

l 1

SEABROOK STATION CYCLE 6 Nr&

sIgWret

- Atlantl3

- CORE RELOAD SAFETY EVALUATION JUNE 1997 e<

Figure 2-2 Control Rod Positions 180*

R.

P N

M L

K J

H G

F E

D C

B A

1 Loop 4 Loop 1 NI41 Ni43 2

SA CB CC C8 SA 3

SD SS SB SC 4

SA CD' SE CD SA 5

SC CA CA SD 6

C8' CC CA CC CB 7

SS S8 8

CC SE CA CD CA SE CC 270' 0

gg 33 10 CS CC CA CC CB 11 SD CA CA SC 18 SC 68 68 SD-14 SA C8 OC C8 SA W2 N144 NI42 15-O g

.g

.ap.

i:

4 i

Seabrook Station Cycle 6 Rodded Fuel Assemblies j

H G

F E

D C

B A

Region A Region A Region G Region G CD CA SE CC 8

30,482 29,208 49,635 46,859 j

Region G

]

SB 9

48,910 Region A Region G Region H CA CC CB 10 1

29,208 50,368 26,790 i

j Region G Region H CA SC 11 44,663 29,418 1

l Region G Region A Region G l

]

SE CD SA 12 49,635 28,200 39,120 Region G Region H SB SD 13 48,859 29,437 Region G Region H Region G CC CB SA 14 46,859 26,674 39,145 1

1 l

Fuel Batch Type Control Rod Bank 15 EOC6 Assembly Exposure 1

I EOC6 Core Average Exposure is 22,250 Mwd /Mtu NOTE: The other three quadrants are symmetrical to the depicted quadrant.