ML19332A593

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Responds to NRC 800911 Request for Addl Info Re Spent Fuel Pool Mods.Poison Matl Is B4C Powder in Fiberglass Matrix. Irradiation Data Submitted to NRC on Haddam Neck & Millstone Dockets in Form of CBO-N-78-299 Dtd 781031
ML19332A593
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/12/1980
From: Ash R
BALTIMORE GAS & ELECTRIC CO.
To: Clark R
Office of Nuclear Reactor Regulation
References
NUDOCS 8009160453
Download: ML19332A593 (2)


Text

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V BALTIMORE GAS AND ELECTRIC y

CHARLES CENTER . P.O. BOX 1475 BALTIMORE, MARYLAND 21203 ELECTRIC ENGINEERING oEPARTMENT September 12, 1980 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attn: Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Subject:

Calvert Cliffs Nuclear Pover Plant Units Nos. 1 & 2, Dockets Nos. 50-317 & 50-318 Spent Fuel Pool Modification Sunnlementary Information

References:

(a) BG&E letters dated 8/5/77 and 9/7/77 from A. E. Lundvall, Jr. , to E. G. Case , same subj ect.

(b) NRC letter dated 1/h/78 from D. K. Davis to A. E. Lundvall, Jr., Amendments 27 and 12 to operating Licenses DPR-53 and 69 (c) BG&E letter dated 7/3/79 from J. W. Gore, Jr. to H. R. Denton, Request for Amendment.

(d) BG&E letter dated 1/15/80 from A. E. Lundvall, Jr.

to R. W. Reid, same subject.

Gentlemen:

The following are BGLE's responses to the NRC request for additional in-formation which was telecopied to us September 11, 1980.

a. What is the composition of the Bhc composite material?

The poison t:aterial is a BhC powder in a fiberglass matrix.

b. Has this composite material been corrosion tested in borated water at the condition of the SFP? What were the results?

The material has been corrosion tested in an environment of boric acid greater than 1720 ppm boron maximum in the Calvert Cliff-Spent Fuel Pool.

No significant corrosion occurred.

c. Is the B hc composite subject to off-gasing under irradiation? What provisions have been made to prevent swelling of the sandwich by off-gasing?.

The material does off-gas under irradiation. The racks are of a vented design, however, which prevent swelling of the can.

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d. Has the referenced irradiation data been submitted to and approved by O NRC on another docket? If not, please submit three (3) copies for our 9 t review.

8009160458

m R. A. Clark September 12, 1930

~i The irradiation data has been submitted to the NRC on the Haddam Neck &

Millstone Dockets -Nos. 50-218 and 50-2h5 respectively in the form of CEO-N-78-299 dated October 1978. The NRC has also previously licensed this poison for use in the Lacrosse Spent Fuel 2acks.

e. If the binder material in the B c composite h decomposes or breaks down under irradiation, what prevents shifting of the 3 c hparticles?

The binder material does not decompose sufficiently for the danger of shifting of 3 hc particles to be significant.

\ m Mr. R. F. Adh Chief Nuclear Engineer ec: J. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. 3. L. Conner, Jr. - NRC Mr. R. A. Milos - NES m