ML19257C787

Requests Interim Relief from Tech Spec 4.2.4.2.5 Which Limits Max Average Exposure of Fuel Assembly to 15,000 Mwd/Mtu.Limiting Exposure Will Be Reached by 800204. Incremental Increase Should Be Granted.W/Oversize Diagrams

ML19257C787
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	01/17/1980
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	Ziemann D Office of Nuclear Reactor Regulation
References
LAC-6739, NUDOCS 8001300425
Download: ML19257C787 (9)

Text

{{#Wiki_filter:. 4 DAIRYLAND POWER COOPERATIVE Sa Groue, 01' comin h 54601 January 17, 1980 In reply, please refer to LAC-6739 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation ATTN: Mr. Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR) PROVISIONAL OPERATING LICENSE NO. DPR-45 REQUEST FOR INTERIM RELIEF FROM TECHNICAL SPECIFICATION LIMIT

Reference:

(1) DPC Letter, LAC-6274, Linder to Ziemann, dated May 9, 1979. (2) DPC Letter, LAC-4771, Madgett to Reid, dated July 7, 1977. Gentlemen: Dairyland Power Cooperative (DPC) hereby requests interim relief from LACBWR Technical Specification 4.2.4.2.5 which limits the maximum average exposure of any fuel assembly to not more than 15,000 MWD /MTU. It is presently estimated that the most exposed fuel assembly in the LACBWR will reach this limiting exposure on February 4, 1980. DPC requests that an incremental increase of 350 MWD /MTU be granted initially and that one or more additional incremental increases of approximately 300 MWD /NTU be considered in a timely manner as each interim limit is approached. DPC will furnish in a timely manner such additional reporting of monitored reactor conditions, etc., as deemed necessary for the consideration of each incremental increase in the fuel exposure limit. Detailed justification for the request for interim relief from LACBWR Technical Specification 4.2.4.2.5 follows. (1) When the most exposed fuel assembly in the LACBWR, Assembly 2-58 in Core Position F-1 (see Figure 1), reaches an average exposure of 15,000 MWD /MTU, the core average exposure will be only 8,000 MWD /MTU. A total of only five Type-II fuel assemblies will have an average exposur'e greater than 14,600 MWD /MTU and the remaining seven A-C Type II fue,1 assembl,ies l838 247 ~ _1_ 80013 00 Y 2 F o 1

Mr. Dennis L. Ziemann, Chief LAC-6739 Operating Reactors Branch #2 January 17, 1980 will have average exposures of less than 14,000 MWD /MTU. All of the Type II fuel assemblies in t'3 present LACBWR core loading are located on the periphery of the core. The lead assembly 2-58 is presently operating at only 0.539 times core average assembly power, and none of the Type II assemblies are greater than 0.6 average assembly The reactor has been operated at approximatoly 85% power. of rated power for the majority of the time during fuel cycle 5. See Figure 2. (2) All fuel assemblies located in the higher powered inner regions of the LACBWR core are Type III (Exxon) assemblies except for two Type I (A-C) assemblics in core positions B-5 and B-6. When the 15,000 MWD /MTU exposure limit is reached in the lead assembly, 2-58, the maximum exposure in a Type III assembly will be only 9,950 MWD /MTU. These assemblies are designed for a batch average exposure of 16,800 MWD /MTU, which corresponds to a maximum assembly exposure of approximately 21,500 MWD /MTU. It is anticipated that the Type III fuel will operate without defects to exposures considerably greater than 10,000 MWD /MTU. Like-wise, the two Type I assemblies which will have experienced only approximately 4,240 MWD /MTU exposure are also expected to be trouble-free for many thousand additional MWD /MTU exposure. (3) During the 5 previous fuel cycles on the LACBWR, the incidence of significant fuel failures in peripheral fuel assemblies has been relatively low corupared to that in assaablies located in the interior of the core. See Reference (1). Most of the defects which did occur in peripheral assemblies were only evident from sipping indications. Visible clad defects have been observed in only six peripheral fuel assemblies, two at the end of cycle 4 and four at the end of cycle 5. (4) Since all the high exposure fuel in the LACBWR is in low power density peripheral core positions, any minor clad defects that may be present or may develop during continued operation would be expected to develop very slowly, and the consequences of such failures would be minimal. The probability of a fuel rod failure propagating a failure in an adjacent rod is essentially nil at the low power densities present in the peripheral core positions. Continued low = activity in the primary coolant will give adequate assurance that there are no gross fuel rod failures present. 2 I838 248 Mr. Dennis L. Ziemann, Chief LAC-6739 Operating Reactors Branch #2 January 17, 1980 (5) The a activity in the primary coolant decreased rapidly during the first few weeks of Cycle 6 and has continued to decrease gradually during the ensuing months. The average of six measurements obtained during the period from December 24, 1979, to January 10, 1980, yields a value of 0.040 x 10-6 pCi/g. The a activity in the LACBWR coolant is currently less than 5% of that present at the end of Cycle 5. See Figure 3. The a activity in the primary coolant at the present time is only 0.8% of the crrrent Technical Specification Ibnit. This low a activity in the primary coolant is a good indication that there are no fuel rods in the core with major clad defects exposing UO2 to the coolant. (6) At the present time, with the reactor at a steady 85% power, the Il31 activity in the primary coolant is approximately 0.0020 pCi/g. Near the end of fuel cycle 5, the Il31 activity in the primary coolant was approximately 0.0095 with the l31 activity in the reactor at 49% power. Assuming that the I coolant is directly proportional to reactor power, the present Il31 activity in the coolant is only approximately 12% of that at the EOC-5. l31 activity in the primary coolant is (7) The Dose Equivalent I presently approximately 0.017 pCi/g at 85% power compared to an activity of approximately 0.040 pCi/g at 49% power at the 131 EOC-5. Again assuming that Dose Equivalent I activity is directly proportional to power, the present Dose Equivalent I ldi activity would be only approximately 25% or tnat at the EOC-5 and is only approximately 8.5% of the current Technical Specification limit. (8) The gross 8/y activity in the primary coolant is currently approximately 1.54 pCi/g at 85% power compared to an activity of approximately 3.21 pCi/g at 49% power at the EOC-5. Assuming a directly proportional relationship with power, the present gross 8/y activity is approximately 28% of that at the EOC-5. (9) The off-gas activity measured at the 150 cu. ft. off-gas hold-up tank effluent monitor is presently approximately 246 Ci/ day at 85% power. This off-gas activity is 36% of the current Technical Specification limit at 85% power and, conservatively assuming that off-gas activity is directly proportional to reactor power, it is approximately 50% of that at the EOC-5. (10) All of the monitored parameters discussed in 5 through 9 above which indicate the condition of the fuel in'the LACBWR core exhibited a decreasing trend early in Cycle 6 as the system i838 249 Mr. Dennis L. Zicmann, Chief LAC-6739 Operating Reactors Branch #2 January 17, 1980 continued to -lean up the residues from previous fuel failures. All have been relatively constant for the last several months of operation at approximately 85% of rated power indicating that the fuel condition is very stable. All of the parameters indicate that the shutdowns and startups which have occurred have not produced any signifi-cant detrimental effects in the fuel. We believe that no precipitous deterioration of the fuel condition will occur during the limited additional operation that would be allowed under the requested interim relief from LhCBWR Technical Specification 4.2.4.2.5. Any deterioration that might possibly occur is expected to develop slowly and would be apparent at an early stage from increases in the monitored parameters discussed above. If the interim relief from LACBWR Technical Specification 4.2.4.2.5 is granted by an increase in the assembly exposure limit to 15,350 MWD /MTU, fuel cycle-6 can be extended by 31 full power days or 37 days at 85% of rated power. The core average exposure at that time would be approximately 8648 MWD /MTU and five control rods would still be partially inserted into the core. The full power all rods out end of life core average exposure is estimated to be at least 10,600 MWD /MTU. The information submitted with this request has been reviewed by LACBWR committees as prescribed in Technical Specifications. DPC respectfully asks that the review of this request be expedited so that a decision may be received before the present Technical Specification limit is reached on the 4th of February. If you have any questions, please feel free to call us at any time. Very truly yours, DAIRYLAND POWER COOPERATIVE { Nm Frank Linder, General Manager FL:SJR:af Attachments cc: J. Keppler, Reg. Dir., NRC-DRO III i838'250 4-

Mr. Dennis L. Ziemann, Chief LAC-6739 Operating Reactors Branch #2 January 17, 1980 STATE OF WISCONSIN ) ) COUNTY OF LA CROSSE) Personally came before me this N day of January, 1980, the above named Frank Linder, to me known to be the person who executed the foregoing instrument and acknowledged the same. y (,f4& ' L-4 Notary Public,vLa Crosse County Wisconsin. My Commission Expires March 2, 1980. ( i838~251 \\ A B C D E F G H K L 2-67 2-51 l'/. 61 ls;oo i 2(i 1 r 2-b/ 3-21 3-17 3-Y7 3-Y3 3-13 3-} 267 S 13.rs ry? 9.3/ V.12 92s T.vs F.01 13.7/ [u IR IF IT 3-2r 34s 1st 3-21 3-7 3-31 3-ar 3 5~ b 7 71 'I.47 ti.7/ 1.74 7 37 s;oo '/. 74 S.33 GT 7 @PB 3-J o 3-36 3-IV 3-yg 3-yy 3-/7 3-34 3 F.6/ Y. 72 9.37 3 77 1 02 g f.07 V.7/ @F3 /P L?S I 2

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