ML19263E381
| ML19263E381 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/30/1979 |
| From: | Wetmore J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906130512 | |
| Download: ML19263E381 (11) | |
Text
{{#Wiki_filter:' /pR Rto ugb UNITED STATES g* NUCLEAR REGULATORY COMMisslON g j WASHINGTON, D. C. 20555 a 8 April 30,1979 j
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Docket No. 50-409 LICENSEE: Dairyland Power Cooperative FACILITY: La Crosse Boiling Water Reactor (LACBWR)
SUBJECT:
Summary of April 26, 1979 Meeting Regarding Fuel Cycle 5 Fuel Performance Representatives of Dairyland Power Cooperative (DPC) and their consultants met with members of the NRC staff in Silver Spring, Maryland, on April 26, 1979. A list of meeting attendees is attached. The purpose of the meeting was to allow DpC to present the results of their end of Cycle 5 fuel examinations which were performed during the current refueling outage. LACBWR utilizes stainless steel clad fuel rods which have exhibited various numbers of defects in past cycles. A summary of important points follows: 1. DPC stated that at the end of Cycle 5 (March 25,1979), all fuel assemblies were examined with an underwater TV camera. During handling of two of the assemblies (2-13 and 2-33) a small section of one fuel rod from each assembly separated and fell on top of adjacent fuel assemblies. Figures 2 and 3 (attached) depict the locations of these sections within the fuel assemblies. DPC believes that no significant amount of fuel was displaced from these rods during Cycle 5 operation. A total of about 12 inches of fuel rod was displaced during handling of which about 9.2 inches has been recovered. About 2.8 inches of fuel (40.5 grams of uranium) is still in unknown locations in the system. This contrasts with about 352 grams that were left in the system at the end of Cycle 4 (26 assemblies were found to be defective in Cycle 4). 2. Five other assemblies had visual defects. These were primarily in the form of circumferential cracks in fuel rods. The location of visibly defective fuel rods in each assembly is shown in Figure 6 (attached). 2357 109 790613 0fl2-
s _2_ 3. All other fuel without visual defects was examined for fission gas release by dry sipping. Five assemblies were found to be definite leakers and five gave low level sipping indications. A total of 17 fuel assemblies are considered to have been defective. A summary of the examination findings is tabulated in Table II (attached). All defective assemblies were Type II Allis-Chalmers fuel. 4. The number of defective fuel assemblies (17) is within the rarge predicted for Cycle 5 in the March 3,1978 Safety Evaluation Report for Amendment No. 11 to Provisional Operating License No. DPR-45 for LACBWR, and is substantially less than that experienced in Cycle 4. 5. The core locations and exposures of each defective assembly is indicated in Figure 5 (attached). The exposure of the 17 defective assemblies ranged from 11,920 to 14,890 MWD /MTU. An exposure limit of 15,000 MWD /MTV on the lead assembly is currently contained in the LACBWR Technical Specifications. 6. DPC presented data (attached) on off-gas activity, primary system gross beta-gamma and alpha activity for Cycle 5. DPC believes that the gradual removal of fissionable material (left in the system from Cycle 4) during the early part of Cycle 5 tended to mask the development of fuel defects as indicated by off-gas activity. Because of the iodine spikes observed after scrams, DPC indicated that one or more leaking fuel rods may have developed as early as six weeks into Cycle 5. 7. DPC believes that with a much cleaner reactor coolant system at the beginning of Cycle 6, off-gas and primary coolant activity levels will be substantially less than at the beginning of Cycle 5, and thus will be more sensitve indicators of fuel condition during Cycle 6. The staff asked, and DPC agreed, to consider the need for modifying the current Technical Specification off-gas activity limits to account for the removal of fissionable material from the system as the cycle progresses. 2357 110
. I n 8. DPC plans to submit a full report on the' fuel examination results and any needed changes to their Cycle 6' reload plan in the near future. J -k S. Wetmore, Project Manager erating Reactors Branch #2 Division of Operating Reactors Attachments: As stated cc w/ attachments: See next page 2357 111 6
. cc w/ attachments: Fritz Schubert, Esquire Staff Attorney Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601
- 0. S. Heistand, Jr., Esquire Morgan, Lewis & Bockius 1800 M Street, N. W.
Washington, D. C. 20036 Mr. R. E. Shimshak La Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 135 Genoa, Wisconsin 54632 Coulee Region Energy Coalition ATTN: George R. Nygaard P. O. Box 1583 La Crosse, Wisconsin 54601 La Crosse Public Library 800 Main Street La Crosse, Wisconsin 54601 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601 2357 112 i
ATTENDANCE LIST APRIL 26,1979 DPC W. Angle
- 0. Hiestand J. Parkyn R. Shimshak E. Trenmel NRC J. Wetmore R. Lobel F. Coffman C. Woodhead M. Chatterton H. Vander-Molen R. Riggs Nuclear _ Energy Services T. Kenter P. Buck 2357 113
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FUEL /A/S PEC T/C' ^ ' R.E S. tJL. 7._S_ i; S_CEMBL y A/o_, y,1 ; OO e s 4 (!.a ~ fl 5) t }
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l i i l l s i l k ~ <k e sowrp --e BAWD i II i- _L LOWS 2 SAA/D --d - l / 2357 115 l ~ ~ J .~ \\___/ P/M ff - ~ MfB,0'T cY. ~5,M 03,02,0/, 60 FIG-3 NO ZLf i =i>. < . vin e
LAC-TR-068 A B C D E F G H K L / O(O Q 1-?] 14 V l T l( Ji' ~ 1-50 } QPB Gm 7 A C?hD [~ 2 &V'3 18 5 = ' ' '. 2" C @'_ i 9 QC@M dM I t 6 2-"' L_ 24 @k.S 4 Ic, 7 IP ll Q I( 8 L-n ? 9 z-w a ?! 10 IN CORE FLUX MONITORS Q PLANT NORTH Fuel Assembly Number xxx FIGURE 6 - Location of Visibly Defective Fuel Pods at EOC-5. 2357 ii6
LAC-TR-068* TABLE II LACBWR FUEL ASSEMBLIES DISCHARGED AT END OF CYCLE 5 FUEL ASSEMBLY NO. CORE POSITION EXPOSURE, MWD /MTU TYPE OF DEFECT
- 2-48 K-8 14,889 V
2-25 B-3 14,836 S 2-23 F-1 14,774 LS 2-2 L-6 14,713 NONE 2-41 B-8 14,689 LS 2-1 F-10 14,688 LS 2-32 K-3 14,663 NONE 2-40 H-9 14,614 V 2-13 A-5 14,608 V' 2-29 E-1 14,539 NONE 2-33 C-2 14,534 V' 2-24 L-5 14,479 NONE 2-9 A-6 14,437 NONE 2-36 H-2 14,424 NONE 2-49 C-9 14,358 NONE 2-47 E-10 14,337 NONE 2-70 F-8 13,708 S 2-51 E-3 13,670 V 2-69 E-8 13,387 NONE 2-52 F-3 13,351 S 2-62 D-4 13,306 LS 2-59 G-7 13,303 S 2-68 H-6 13,172 NONE 2-53 C-5 13,119 NONE 2-63 G-4 13,079 S 2-65 C-6 12,809 V 2-55 E-5 12,640 V 2-72 G-9 11,925 LS V' Vi sible Defects, Fuel Displaced During Ilandling V Visible Defect S liigh bipping Indication, 85 to 10,260 x Backg round LS Low Sipping Indication 7
A B C D E F G H K L 2-23 IV. 77 2(i 1 lZ-11 g l/4.s t_ @~~ 17 /4 l' R / 2n Y 2 {/ 2-S: b IV.31 /3.;,7 13M G 7 8 2-62. 2-M k 13 3 / !3.c? ?% __ _ 2 3 I@ 2-13 1-!J b 1%I n,y ~ ~G) / 9 @i-~ gr I Pn t n i
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/2.9 / 24 S 4 to 1-11 I3.30 '? ll 1@ IC (i 2 I ' 2 f? l'YI O ty.7/ l fy3 i u ty. t, / f ?? T~ v l ?> 2n 9 2-7: 2 -Yo ll.9Z ly.bj Pf 2-/ IV.a'f l IN CORE, FLUX MONITORS Q \\ \\ PLANT NORTH Fuel Assembly Number 'xxx! Average Exposure (GWD/MTU) yyy l FIGURE 5 - Locations and Exposure of t.he 17 Assemblies Failed During Cycle 5. Five of these Assemblies Gave Only l Low Sipping Indications. See Table II and Figure 6 for Type of Defects. 2357 118
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