ML20039H169
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UNITED STATES
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A-ATOMIC ENERGY COMMISSION y
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I, R. C. DeYoung, Assistant Director for Light Water Reactors, Group 1,.L l
SUPPLEMENTAL SUINEILTECE OF 17x17 IUEL ASSDIBLIES Surveillance of the Park C 17x17 fuel assemblies has been tha subject of discussions anung Reactor Safety, Reactor Projects,
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Mmk and Wilcox, applicants and the ACRS. This letter clarifies our position for a surveillance comtitment frc.n the first two licensees to use the Babcock and Wilcox Mark C 17x17 design.
l The desired surveillance prcyram is described in the enclosure.
The program requires visual inspection (e.g., by undenster television viewing systcm) of all the peripheral rods in the initial core fuel t
asscrrblies once they are noved into the spent fuel pool. At the time of refueling, the staff nust ba afforded 10 days advanca notice of the start of inspection so that it reay observe the inspections and the i
resultant evaluatiene of the fuel accciblics' performance.
The conclusions of the inspection are to be provided to the staff prior to Ixuor ascendency.
If ano:ralies are detectcd during the 1004 visual inspaction, then the applicant raust conduct a follca-on investigation of a representative sample of individual fuel rods.
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. The B&W Mark C fuel design is schedulcd for operation in tlk fol3csing plants:
Bellefonte 1&2 (1979/1980); WPPSS-1 (1980), Pebble Springs (1980); Greertaood 2&3 (1981/1984); and Davis-Bosse 2&3 (1932/1983).
i Please assure that the listad applicants are responsible for the i
supplerental surveillance prcgrcm as outlined in the enclosure.
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VictorStello)Jr.
sistant Director
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for Reactor Safety Directorate of Licensing
Enclosure:
As stated cc:
S. Ihnaucr 1;'. Schroader D. Ibss L. Rubenstein i
A. Schwcacer D. I!ouston l
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8201190680 810403 1
PDR FOIA i-MADDEN 80-515 PDR l
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,J SUPPIDENTM, FUEL SURVEILIANCE PROG 1VM gr r, ', /
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To provide added verification of the reliable perfonnance of the
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Park C 17x17 fuel assemblies, a supplenental fuel surveillance program will be conducted at Reactor A.
The program will consist of a visual inspection (e.g., by an undentater television viewing systen) of all of the peripheral rods in 100% of the initial core fuel assemblies once they are novcd into the spent fuel pool.
The inspections will be conducted during normal refueling shutdowns and upon final renoval of the initial core fuel asse:Tblies. Any condition observed by this inspection that could lead to unacceptable fuel perfonnance shall be the subject I
of a follow-on effort. The Reactor Safety staff must be affordcd a reasonable option to observe the inspections. The follow-on effort, if required, will consist of a detailed examination of a representative I
sample of individual fuel rods.
The renoved rods will be inspected
. visually, dimensionally, and for gamma activity (e.g., for fretting,
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cladding integrity, rod bcwing, corrosion and crud deposition, and i
l axial and radial dinensions). Subsequent destructive examination of these fuel rods may be deemed necessary by the Nuclear.R y latory Ca mission.
The conclusions of the inspection are to be provided to the staff prior i
i to p:n.nr ascendency.
The Supplcnontal Fuel Surveillance Program with its associated follcu--
i on effort, if required, will b2 conducted in addition to that which may be performed at other reactors.
If two other domestic _ plants i
which contain a full core of 17x17 fuel asscablics of a similar design reach the second and third refueling stage prior to Reactor A, and if y
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a supplerental surveillance, program has been performxi there, then
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I the program my nof have to be performed at Reactor A.
However, such action requires approval of the Ibclear Regulatory Ck2mtission. The results of these inspections shall be reported to the Naclear Regulatory Ccmnission.
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