ML20128D698

Forwards Response to Plant Interrogatories Which Was Transmitted to J Shea by SB Kim on 740815

ML20128D698
Person / Time
Site:	Monticello
Issue date:	08/20/1974
From:	Rubenstein L US ATOMIC ENERGY COMMISSION (AEC)
To:	Stello V US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212070353
Download: ML20128D698 (5)

Text

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.  ; Victor Stello, Jr., Assistant Director for Reactor Safety, L-1

: TAR REQtlEST NO. ORB-2-115 " WRITTEN RESPONSE TO MONTICE 1

Enclosed is a copy 6f the response to the subject request which was

" transmitted to Mr. J.- Shea by S. B. Kim on August 15, 1974. Both Mr. Shea and Mr. Kim will be working with the OGC to obtain a final-

answer to the interrogatory, at which time it will again be available

< ' for Reactor Safety review. Mr. Kim suggested to J. Shea and Mr. Shea agreed that the interrogatory No.13 may be best prepared by the operating reactors branch since it concerns specific plant experience.

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L. S. Rubenstein 1

, Core Performance Branch

i Directorate of Licensing cc

D. F.-Ross S. B. Kim

, J. Shea

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$$M9 sin 0 0 W Victor Stello, Jr., Assistant Director.for React'or Safety, L TAR REQUEST t10. ORB-2-ll5 " WRITTEN RESPONSE TO I40!iTICELLO IflTERR0GATORIES Enclosed is a copy of the iesponse to the subject request which was transtaitted to Mr. J. Shea by S. B. Kim on August 15, 1974. Both fir. Shea and Mr. Kim will be working with the OGC to obtain a final answer to the interrogatory, at which time it will again be available .

for Reactor Safety review. lir. Kim suggested to J. Shea and fir. Shea egreed that the interrogatory No. 13 may be best prepared by the operating reactors branch since it concerns specific plant experience.

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, Core Performance Branch Directorate of L1 censing cc: D. F. Ross 4 S. B. Kim J. Shea l .'

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12. EVALVA110M OF OPERATIUr, EXPERIENCES PROPOSED JT'STlHG AND CRITLRIA In response to AEC request, the General Electric Co. (GE) agreed to a surveillance program on 8x8 fuel bundle behavior as described in the letter froa J. Hinds of GE to V. Stello of ACC dated February 4,1974.

They include' measurements of some key geometric dimensions as well as routine sipping, visual inspections and non distructive tests. About j ten fuel rods are pre-characterized before irradiation. - This fuel bundle has been inservice since last spring refueling operation. At the time of next refueling outage a complete inspection will_ be performsd on these removabic rods. 'under the stcrage pool. They will look for j the unusual features such as fretting hydriding blisters, and dimensional 1

changes. The program is flexible such that any.abi.ormal rods can be further examined in detail. Northern St. ate Powr Company has agreed -

i to.' participate with GE in the above surveillance progr6m. GE will also obtain operating power history such that a real'istic evaluation can be made-.

The data and evaluation of the 8x8 lead bundle will be subnitted to the staff of AEC for a review.

At the time of inspection three criterias will be used as a measure of satisfactory fuel assembly performance and. continuiniservice of the 8x8 fuel . They are 1.0% cladding strain measured in terms of diameter change, 0.030 inches of;the ro'd deflection between two spacer grids and fretting wear of 10.'; of thickness. ,

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15. Quality Assurance .

2 I!cw 0<.8 fuel azwblies undcrgo rigorous Q.selity Im.uri.nte proten haginning with GE plant, IdC' healetory Op uiion regional of fice aid utility, a .

! In CE plcnt, OA concerns ciaterial' acceptcbility'pi:ocess c;onfonaance and product confortcnce, as well as shipping test perf or.nnce. Close to 190 ley quality manuf acturing activitics are nonitored and evaluated.

2 further details my be found in the af fidavit of Mr. J. E. Dergman of GE dated l' arch 29. 1974 at the time of the pilgrim hx ring.

i ln addition, as an independent action, wo. Technical Review, requested Regulatory Operation headquarters for GE audit on fuel and cladding j characteristics. P.0 inspectors spent several days at CE. Uilmington,

! 11ofth Carolina plant m e. Tha follcwing are the itens inrpected. .

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Fill Gas Composition and Pressure .

Fuel Stack' Length ,

Plenum Volume Fuel Rod Enrichment Verfification e i

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Pellet Diameter s

Surface Finish Pellet l'oisture 4

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Pellet Density ,

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Surface Defects Tuhiro 5trenJLh & Ch: :isi t y Ci.;rac teris t.ics l Youn9's l'odalu; Coef ficic nt of Thor.,al Expansion itegional Of fic e of f(epulatory Opert. tion of the AEC performei l tuo audits on GL fuel uanufacturiruj process. As a result of first audit eight corrective actions utre taken. The second, rccent audit has been completed and is being evaluated at this time. They also revie, cd the QA program on receiving 3x3 i

fuel assemblies and worn present t t the ti!nc of refueling.

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