ML20116A087

Responds to NRC Bulletin 96-001, Control Rod Insertion Problems

ML20116A087
Person / Time
Site:	Beaver Valley
Issue date:	07/18/1996
From:	Jain S DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-001, IEB-96-1, NUDOCS 9607250290
Download: ML20116A087 (5)

Text

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

[< l

, Beaver Vapey Power Station SNppingport, PA 15077 0004 a

e s July 18, 1996 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No.1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Response to NRC Bulletin 96-01:

Control Rod Insertion Problems The Duquesne Light Company (DLC) original response dated April 8,1996, to NRC Bulletin No. 96-01: " Control Rod Insertion Problems" notified you that an additional response would be required to fumish information regarding the projected burnup for rodded fuel assemblies for the next fuel cycle of Beaver Valley Power Station Unit No. 2. That information was not available at the time of the original response.

Attachment 1 of this letter provides the projected end-of-cycle burnup values for rodded assemblies for Beaver Valley Power Station Unit No. 2 Cycle 7. Cycle 7 is the next fuel cycle for Unit No. 2. The maximum projected bumup of rodded fuel assemblies is 41,108 MWD /MTU. Thus DLC does not expect any problems will be experienced with incomplete control rod insertions during Unit No. 2 Cycle 7 lifetime. All rodded assemblies in Unit No. 2 Cycle 7 are Westinghouse Vantage 5 Hybrid fuel assemblies. l The DLC original response to Bulletin 96-01 also provided a core map showing the projected end-of-life burnup for rodded fuel assemblies in Beaver Valley Power Station Unit No.1 Cycle 12. Due to cladding defects which were discovered in some fuel assemblies during the Cycle 11/12 refueling outage, the originally planned core loading scheme was modified so the fuel assemblies with leaking fuel rods would not be reloaded into the core. Fuel assemblies without known cladding defects previously discharged from Unit No. I and stored in the spent fuel pool were substituted for the identified leaking fuel assemblies. This required a revision in the location for loading various fuel assemblies in the Cycle 12 core to achieve proper core peakiny factors and other core operating parameters. The revised projected burnup values for the as-loaded Unit No.1 Cycle 12 core are shown on Attachment 2 to this letter. The maximum Dy DEllVEllNG 960725/X290 960718 0UAL4iY PDR ADOCK C5000334 \

G PDR \

ENERGY

Beaver Valley Power Station, Unit No. I and No. 2 Response to NRC Bulletin %-01

" Control Rod Insertion Problems" Page 2 projected burnup for any rodded fuel assembly increased by approximately 800 MWD /MTU from the values originally reported to the NRC (47,525 MWD /MTU versus 46,743 MWD /MTU). As stated in our June 10,1996, letter to you on this issue, there has been over 540 successful control rod insertions in fuel assemblies with burnup greater than 42,500 MWD /MTU. This includes 87 successful control rod insertions in fuel assemblies with burnup in the range of 47,500 to 52,500 MWD /MTU. Thus it is expected that full insertion of the control rods will occur should a reactor trip be required during BV-1 Cycle 12 lifetime. All rodded assemblies in Unit No.1 Cycle 12 are Westinghouse Vantage 5 Hybrid fuel assemblies.

If you have any questions concerning this response, please contact Mr. Roy K.

Brosi at (412) 393-5210.

Sincerely, j Sushil C. Jain  !

Attachments  !

c: Mr. L. W. Rossbach, Sr. Resident inspector Mr. T. T. Martin, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Manager

0 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA)

) SS: ,

COUNTY OF BEAVER )

l

Subject:

Beaver Valley Power Station, Unit No. I and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 ,

BV-2 Docket No. 50-412, License No. NPF-73 Before me, the undersigned notary public, in and for the County and Commonwealth aforesaid, this day personally appeared Sushil C. Jain, to me known, who being duly swom according to law, deposes and says that he is Division Vice  :

President, Nuclear Services of the Nuclear Power Division, Duquesne Light Company, a he is duly authorized to execute and file the foregoing submittal on behalf of said j Company, and the statements set forth in the submittal are true and correct to the best of his knowledge, information and belief.

Sushil C. Jain i

Subscribed and sworn to before me  !

on this/8 day of d ,/kkh ulww d a&A$ary' Pub'lic /

n My .

m _,

~~' W#N 80, tW/

--J,1 w s ,'Og g

1 Attachm:nt 1 R:sponso to NRC Bulletin 96-01  ;

Beaver Valley Unit 2 I Rodded Assembly Burnup (MWD /MTU)

Projected - End of Cycle 7 RPNM LK JHG F EDCB A  :

I 1

l 2 41072 20374 41072 3 2343e 23 .

4 2** 3= = 3= = 2**

5 == 3e'

• 6 4,s. 3m22 as . 3ss77 as4ee 3m22 4ss.

23337

[ 37083 37083 23337 h 20374 3ss77 3ss77 20374 h 23337 37083 37083 23337 10 4uo8 39322 as4ee 3ss77 as4ee 30322 4s20e 11 m se u se 12 2

• 95 saa 3== 25

• 13 23 . 2343e j4 41072 20374 41072 15

l l

s Attachm::nt 2 Response to NRC Bulletin 96-01 l

l Beaver Valley Unit 1 Rodded Assembly Burnup (MWD /MTU) l Projected - End of Cycle 12 (Revised) .

RPNM LK JHG F EDCB A 1

i 2 2ee97 47739 2ee97 3 ' *39 = 3a 4 296s1 43031 43031 29esi 5 20771 20772 6 2eee2 43se7 47s2s .ee4s 4752s 43se7 2eee2 190e2 198e2

[ 33120 33120 h 17739 de64s de64s 17739 9 4 82 33420 33420 = e2 10 2ese2 43se7 47s2s 4es s 47s2s 43se7 2s882 11 un un 12 24 43mi 43034 2=1 13 = 39 = 39 l

14 2a897 '7739 26S97 15 f

I