ML20028H746

Submits Addl Info Re 901217 Tech Spec Change Request 90-11 on MCPR Safety Limit Changes Required for Cycle 9 Operation Per 910117 Telcon W/Nrc.Corrected Tech Spec Pages Encl

ML20028H746
Person / Time
Site:	Peach Bottom
Issue date:	01/22/1991
From:	Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20028H747	List: ML20028H746 ML20028H748
References
NUDOCS 9101290354
Download: ML20028H746 (4)

Text

. _-...._._ _,_ ___.____ . _ __._ _____ _ _ _ _ . _ _ . _ _ . , _ . _ _

10 CFR 50.90 PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADGi>ARTERS 965 65 CHFSTERBROOK BLVD.

WAYNE. PA 19087 5691 (sis)e40sooo ,

January 22, 1991 Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 10555 Washington,-DC

SUBJECT:

Peach Bottom Atomic-Power Station, Units 2 & 3 Technical Specifications Change Request (TSCR)

Submitted December 17, 1990 (No. 90-11)

Dear Sir:

The subject Peach Bottom Atomic Power Station TSCR involved Minimum Critical Power Ratio (MCPR) Safety Limit changes required for Unit 2 and Unit 3 Cycle 9 operation and miscellaneous administrative changes. In a telephone conversation on January 17, 1991, the NRC Project Manager requested additional information~ about the Unit 2 and Unit 3 Cycle 9 reactor fuel. Accordingly, the tables below show the number of bundles of each fuel type that will be used in Unit 2 and Unit 3 Cycle 9. Also shown is the corresponding MCPR Safety Limit for each

, fuel type as specified .in Table . 4-2 of " General Electric Standard Application for Reactor Fuel," (0 ESTAR) NEDE-24011-P-A, with the exception of.the lead test-assemblies (LTAs) from the Unit 2 Cycle j reload (LTA 310)- and qualification fuel bundles (QFBs) that will bc L included-in~the Unit'2 Cycle 9 reload'(SVEA-96 and 9x9-9X+). .The LTAs

j. and QFBs were designed to.be compatible with'the standard reload bundles and have been demonstrated by analysis to be bounded by the thermal limits of the standard reload bundles with considerable margin. 'PECo has also committed to operate these bundles in non-limiting core positions to L provide even greater margin. Therefore, tho'LTAs and QFBs have no

-bearing on the determination of the appropriate core-wide MCPR Safety Limit.

9101290354 910122

- --- p

,P PDR i.

j.

. - , - . . - , _ - - - . _ . ~ - . - . . . - - . -

- PBAPS. Units 2 & 3 January 22, 1991 TSCR SC-11 Page 2

_ Uni _t_2__Cyg_1 e __9 EUEL_ TYPE CYCLE _ LOADED QUANTITY MCPR_ SAFETY LIMIT High Bundle R-factor 6 16 1.04 P8x8R (P8DRB285)

High Bundle R-factor 6 25 1.04 P8x8R (P8DRB299)

Iligh Bundle R-factor 7 136 1.04 BP8x8R (BP8DRB299)

High Bundle R-factor 7 155 1.04 BP8x8R (BP8DRB299H)

LTA310 (CE9B LTA) 8 4 (note 1)

High Bundle R-factor 8 64 1.04 GE8x8EB (BD319A)

High Bundle R-factor 8 204 1.04 GE8x8EB (BD321A)

GE8x8NB 9 148 1.06 (GE9B-P8DWB320-10GZ-80M-150-T)

LUA307 (GE21 QFB) 9 4 (note 2)

SVEA-96 (ABB Atom. Inc. QFB) 9 4 (note 2) 9x9-9X+ (ANF Corp. QFB) 9 4 (note 2) 764 total Ngtesi

1) See NRC Safety Evaluation Report for Amendment 123 (Cycle 8 r31oad) to the Unit 2 Technical Specifications, dated Septenoer 11, 1987.

2) See PECo letter to NRC concerning QFBs, dated November 21, 1990.

Because one MCPR Safety Limit is applied to the entire core, the most limiting fuel type determines the MCPR Safety Limit value. For Unit 2 Cycle 9, therefors, the MCPR Safety Limit for GE8x8NB fuel, 1.06, was selected. It should be noted that the Unit 2 Cycle 8 MCPR Safety Limit was 1.07, rather than the less restrictive approved value of 1.04 which GESTAR specifies for the Cycle 8 fuel as shown in the above table.

The less restrictive value was approved after Cycle 8 commenced.

4 POAPS, Units 2 & 3 January 22, 1991 TSCR 90-11 Page 3 U ni t_3_Cyc 1 e_9

, FUEL TYPE CYCLE _ LOADED Q'JANTI TY

• MCPR SAFETY LIMIT High Bundle R-factor 6 32 1.04 P8x8R (P8DRB299)

High Bundle R-factor 7 144 1.04 BP8x8R (BP8DRB299)

High Bundle R-f..ctor 7 140 1.04 BP8x8R (BP9DRB299H)

High Bundle R-factor 8 48 1.04 GE8x8EB (BD319A)

High Bundle R-factor 8 144 1.04 GE8xBEB (BD321A)

GE8x8NB 9 168 1.06 GE98-P8DWB324-10GZ1-80M-150-T GE8x8NB 9 88 1.06 GE9B-P8DWB328-110Z-80M-lbO-T 764 Total

• Preliminary core inventory It has also come to our attention that Unit 2 Technical Specifications page 256a and Unit 3 Technical Spamifications pages 17 and 256a enclosed with TSCR No. 90-11 contained editorial errors. Corrected pages are attached, and we hereby incorporate these corrected pages into the TSCR. We regret our error and any inconvenience it may have caused you.

If you have any questions or require additional information, please do not hesitate to contact us.

Very truly yours.

W b/

G. J. Beck Manager Licensing Section Nuclear Engineering & Services Attachments cc: T. T. Martin, Administrator, Region I, USNRC J. J. Lyash, USNRC Senior Resident Inspector, PBAPS T, M. Gerusky, Commonwealth of Penns."lvania

COMMONWEALTil 0F PEN!iSYLVANI A:

ss.

COUNTY OF CilESTER  :

D. R. Helwig, being first duly sworn, deposes and says:

That he is Vice President of Philadelphia Electric Company; that he has read the foregoing supplement to TSCR No. 90-11 for Peach Bottom Atomic Power Station, and knows the contents thoroof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

C ") f, .

.d D h Td^ __

Vice President [

V Subscribed and sworn to before me this J 3^/ day of January 1991.

?

Lt!bw*Lb01Q . d Notary Public _ _ _

NOTARAL CEAL CATKn'Nt! A MENCE2 tway petic TQ n + Ts0,CwOce Cxm; My C g r3g g .nres s et 4 1993 l

l AJ -_ _ - _ _ _ _ _ _ . _ - _ _ - _ _ _ - - - . - -