ML20006A633

Application for Amend to License DPR-30,reflecting Use of Generically Approved Fuel Type GE8x8NB in Reload Cycle 11 & Changing MCPR Safety Limits from 1.04 to 1.06

ML20006A633
Person / Time
Site:	Quad Cities
Issue date:	01/15/1990
From:	Silady J COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
Shared Package
ML20006A634	List: ML20006A633 ML20006A638
References
0493T, 493T, NUDOCS 9001290239
Download: ML20006A633 (4)

Text

-- -

7-~  !

4 ./

. ( ._

} Commonwealth Edison One Fast National Plaza. Chicago Illinois  ;

'\ 2 KBfesskply to: Post Office Bb7767~ l C Nd Chcago, lihnois 60690 - 0767 l

)

January 15, 1990 i I

d Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission i Washington, DC 20555 )

?

Subject:

Quad Cities Nuclear Power Station Unit 2 '

Proposed Amendment to Technical Specification Minimum Critical Power Ratio Limit  !

License No. DPR-30 1 NRC Docket No. 50-265 I

l Dr. Murley:

Pursuant to the provisions of 10 CFR 50.90, Commonwealth Edison Company (CECO) proposes to amend Facility Operating License No. DPR-30, Appendix A, Technical Specifications to reflect the use of generically approved fuel type GE8x8NB in the reload. Unit 2 Cycle 11 and the resultant change in j the Minimum Critical Power Ratio (MCPR) safety limits from 1.04 to 1.06.

i Attachment 1 provides a description of the proposed Technical Specification change. Attachment 2 summarises the proposed change. The  ;

proposed Technical Specification page change is provided in Attachment 3. j Attaclunent 4 documents the CECO determination of No Significant Hazards Consideration (NSHC) based on the criteria in 10 CFR 50.92. The proposed amendment has been reviewed and approved by Ceco On-Site and Off-Site Review in accordance with Company procedures. '

i CECO is notifying the State of Illinois of our request and our deter-mination of NSHC by providing a copy of this letter and the attachments to the Illinois Department of Nuclear Safety.

l 1

0526T 1 l

I f 9001290239 900115 [N' PDR ADOCK 05000265 t ,

p PDC ij

c .

F n  ;

s , t

Dr. T.E. Murley January 15, 1990 i E j

, i L-I r t

If you have any questions regarding this matter, please contact this ,

office.

I i- Very truly yours, i ,

g hhib_u J.A. Silady i Nuclear Licensing Administrator 1m Attachments la Description of Proposed Amendment Request 2: Summary of Proposed Change l 3: Proposed Technical Specification Change 4: Evaluation of Significant Hazards Consideration '

cc: T.M. Ross - Project Manager, NRR A.B. Davis - Regional Administrator, RIII R.L.'Higgins - Senior Resident Inspector, Quad Cities ,

' Office of Facility Safety - IDNS L

SUB RIBED AND } to [=====:=: ^:=::=:,

befremethisJJgW day 4 l "0FFICIAL SEAL" <

^'

of flA1A4.Ap 1990 ll LEL1A F. MAYO l d' l Notary Public. State of Illinois l '

/ _ D/ * .. b 8._ l Hy Commission Espires 4/25/93 ' '

Notary Pub 1ic { '=:======:====

0493T:2

i n .

f AT11CIEEENI_1 3

DESCRIPTION OF TE.CENICAL SPECIFICATION CHAltGE ,

Quad Cities Unit 2 vill be using its first reload of GE8x8NB fuel during Cycle 11. General Electric has been continuously refining and improving the fuel design used in BWRs. Their continuous interest in advancing their fuel design has, in the past, led to safety limit MCPR values unique to particular fuel types. For a given plant, the value of the safety limit MCPR in the Technical Specifications may change as new fuel types are licensed. The major differences between the GE8x8EB and the GE 8x8NB designs  !

are the utilization of a large central water rod (LCWR), a high performance spacer and U-235 axial enrichment variation for the GE8x8NB fuel. From a thermal-mechanical standpoint, the GE8x8NB design is the same as that of the GE8x8EB. However, the hydraulic design change of using one LCWR and a high performance spacer has resulted in changes to the bundle flow area, hydraulic diameter, heated perimeter and spacer loss coefficients. The analysis of the thermal-mechanical and hydraulic portion of the GE8x8NB design has been performed using approved codes and methodology and the analysis and results have been accepted by the NRC. A new critical power correlation has also been

. developed and approved for use on GE8x8NB fuel.

L I l A safety limit MCPR of 1.06 for GE8x8NB fuel was determined using NRC approved methodology discussed in Section 4.3 of NEDE-24011-P-A-9, " General Electric Standard Application for Reactor Fuel". This is the same methodology used in determining the safety limit MCPR for previous GE fuel designs. This value ensures that 99.9% of the fuel rods would be expected to avoid boiling l l transition during steady-state or transient conditions with a 95% confidence level. For these reasons, a Technical Specification change reflective of the 1.06 safety limit MCPR for GE8x8NB is required prior to the beginning of Cycle 11 operations.

0526T:3 014 Suo.

l

yp , ,,- ,

3,,

~-

n.

ATTACE WIT 1 IECHNICAL_$21QIFICATION CHAl(GE...SUff1AkY s

t PAGE AFFECTED CHANGE DESCRIPTION 1.1/2.1-1 Under Section 1.1/2.1-1 Fuel Cladding Integrity, there is a listing of Specifications which have been established to preserve the integrity of the cladding.

Among the list-is the safety limit MCPR. .The current value of 1.04, established through the use of GE8 and high R-factor fuel, must be raised to 1.06 to account, for the use of GE8x8NB' fuel. ,

r

~

l l

I l

l 4

?

+

< t

, 0526T 4

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