ML19289E765
| ML19289E765 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/23/1979 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| LAC-6312, NUDOCS 7905290086 | |
| Download: ML19289E765 (6) | |
Text
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DAIItYLAND I*0 Welt CODI*EftATIVE Ba Groue, Olko,ua,a 54601 May 23, 1979 In reply, please refer to LAC-6312 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 APPLICATION FOR AMENDMENT TO LICENSE
Reference:
(1)
NRC Letter, Wetmore to DPC (Licensee),
dated April 30, 1979.
(2)
DPC Letter, LAC-6130, Linder to Ziemann, dated February 26, 1979.
(3)
DPC Letter, LAC-6274, Linder to Ziemann, dated May 9, 1979.
(4)
NRC Letter, Reid to Madgett, dated March 3, 1978.
Gentlemen:
Your letter (Reference l' summarized points discussed during our meeting on April 26, 1979 regarding Fuel Cycle 5 fuel performance.
In response to your request to consider the need to modify the current Technical Specification off-gas activity limits to account for the removal of fissionable material from the primary coolant system as Cycle 6 progresses.
We are submitting an application to amend Provisional Operating License No. DPR-45 by proposing changes to Technical Specifications for the La Crosse Boiling Water Reactor (LACBWR) which deal with off-gas activity.
Our letter (Reference 2) forwarded the refueling plan for LACBWR Fuel Cycle 6 (LAC-TR-067) and included proposed changes to the Technical Specifications necessary to include Type I fuel for the proposed operation during LACBWR Fuel Cycle 6.
In addition, our letter (Reference 3) responded to NRC questions concerning the sub-mittal of Reference 2 and included report LAC-TR-068, "LACBWR Cycle 5 Fuel Performance - Finalized Refueling Plan for Cycle 6".
The proposed changes to Technical Specifications are as follows: 7905290086 d
Mr. Dennis L.
Ziemann, Chief LAC-6312 Operating Reactors Branch #2 May 23, 1979 Referring to Reference 4 (Amendment 11 to Provisional Operating License No. DPR-45) page 32, Section 4.2.2.22 ACTIVITY, Limiting condition for Operation, paragraph b - change to read:
" REACTOR COOLANT SYSTEM 4.2.2.22 ACTIVITY LIMITING CONDITION FOR OPERATION 4.2.2.22 The activity of the:
a.
Reactor coolant shall be limited to:
1.
< 0.2 pCi/ gram DOSE EQUIVALENT I-131, 2.
j 100/E pCi/ gram, and 3.
j 5.0 x 10-6 pCi/ gram gross alpha activity.
b.
Off-gas emission, measured at the 150 cu. ft. off-gas holdup tank effluent monitor, shall be limited to j 750 Ci/ day (P/Pp) +AT (1. 018 t) (P/Pp), where:
1.
(P/PF) = fraction of RATED THERMAL POWER between 33 MWt and 165 MWt, 2.
AT = tramp activity, Ci/ day, not to exceed 1500, at THERMAL POWER (PF) as determined upon initial power escalation after each refueling.
3.
t = days after the determination of AT with the limitation that t j 50, 4.
Activity values shall be normalized for correlation with previous cycles due to changes in monitoring, sampling and/or analysis methods.
APPLICABILITY:
OPERATIONAL CONDITIONS 1 2,
3 and 4."
Referring to Reference 4, page 32b, as corrected by NRC Letter, Ziemann to Madgett, dated April 18, 1978, Section 4.2.2.22 ACTIVITY -
Action paragraphs b and f - change to read:
2048 JS1 s
Mr. Dennis L.
Ziemann, Chief LAC-6312 Operating Reactors Branch a2 May 23, 1979 "b.
In OPERATIONAL CONDITION 1, with off-gas activity:
750 Ci/ day (P/Pp) +AT (1. 018 t) (P/Pp) but < 10 0 0 1.
Ci/ day, POWER OPERATION may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these conditions shall not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12-month period.
Should the total operating time at an off gas activity > 750 Ci/ day (P/Pp) +AT (1. 018 t) (P/Pp) exceed 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s-in any conseettive six-month period, the licensee shall report the number of hours of oper-ation above this limit to the NRC within 30 days.
750 Ci/ day (P/PF) + AT (1. 018 t) (P/PF) for more than 2.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or > 1000 Ci/ day, be in at least HOT SHUTDOWN with the main steam line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."
"f.
In OPERATIONAL CONDITION 1, 2,
3 or 4 with the activity of the primary coolant > 0.2 pCi/ gram DOSE EQUIVALENT I-131, or > 100/E uCi/ gram, or > 5.0 x 10 6 uCi/ gram gross alpha activity, or with the off-gas activity > 750 Ci/ day (P/Pp) +
AT (1. 018 t) (P/PF), perform the saritpling and analysis require-ments of Items Ib, 4b and 6b of Table 4.2.2.22-1."
Referring to Reference 4, page 32f, Section 4.2.2.22 and 5.2.16 ACTIVITY bases - change to read:
"The limitation on off-gas emission and the limitation on gross alpha activity are established to ensure fuel integrity.
The numerical limits were selected using extensive data collected during fuel cycles 4 and 5.
The off-gas activity limitation formula has been derived to relate off-gas production and power level and,onservatively precludes reduced power operation with-out also reducing the limiting condition for operation off-gas activity.
The formula contains a factor AT(1.018t) (P/PF) which accounts for base level tramp Uranium activity in the coolant and on the core surfaces at the beginning of the cycle.
This tramp activity term is reduced to 0.1 of the BOC value within 50 days to account for clean-up of the system during operation."
We have determined that a fee is not necessary for this license amendment since it changes paragraphs to Technical Specifications as a result of verbal and written Commission requests (Reference 1).
/Q48
] 3-
Mr. Dennis L. Ziemann, Chief LAC-6312 Operating Eeactors Branc #2 May 23, 1979 The information submitted in this.pplication for license amendment has been reviewed by LACBWR Committees as prescribed in Technicil Specifications. We are also including with this submittal, as Enclosure 1, DPC's reply to a question from the NRC Staff (May 22, 1979) concerning verification of the LACBWR core configuration for Cycle 6 operation. If there are any questions concerning this submittal, please con-tact us. Very truly yours, DAIRYLAND POWER COOPERATIVE (Tm ) su[ L db Frank Linder, General Manager FL:SJR:af Enclosure cc: J. Keppler, Reg. Dir., NRC-DRO III STATE OF WISCONSIN ) ) COUNTY OF LA CROSSE) day of May, 1979, Personally came before me this a the above named Frank Linder, to me known to be the person who executed the foregoing instrument and acknowledged the same. f7 v Notary Public, La Crosse County Wisconsin. My Commission Expires March 2, 1980. 2048 053 ENCLOSURE 1 TO LAC-6312 Reply to Verbal Question from NRC Staff (May 22, 1979) Concerning Verification of the LACBWR Core Configuration for Cycle-6 Operation. The 26 fresh (unirradiated) Type III fuel assemblies and 2 fresh Type I fuel assemblies included in the design core loading for Fuel Cycle-6 were loaded according to procedures in Addendum No. 1 of Operations Procedure OP-35-02. Prerequisite 2.3 of this procedure required that "Before new fuel is loaded, the Fuel Accountability Representative shall visually examine the existing core loac; 7 to verify that an irradiated fuel assembly of the proper type is in each location designated for a previously ex-posed fuel assembly in the attached Figure 1 and that only locations designated for new fuel are still empty." This examination was done and the required condition verified by Dr. Seymour Raffety, the LACBWR Reactor Engineer and Fuel Accountability Representative, at 0635 hours on May 7, 1979. The visibility during the examination was excellent and there was no problem in identifying the Type II and Type III assemblies by the difference in upper end fittings. There was no fresh fuel in the core and the only empty locations were those designated for fresh fuel in the design loading for Cycle-6. This examination was documented on the "LACBWR Fuel Element Transfer Record" form. The original of this document is filed in the SNM Accounting files and copies with procedure Addendum No. 1 of Operations Procedure OP-35-02. At 1440 hours on May 7, 1979, the loading of fresh fuel into the LACBWR core commenced with the insertion of assembly 1-8 in core position B-5. Assembly 1-24 was inserted in core position B-6 at 1500 hours on May 7th. These assemblies were identified and their positioning in the core witnessed and documented by a LACBWR Fuel Accountability Delegate (Paul Sampson) acting independently of the fuel handling crew. After the two fresh Type I assemblies were loaded, the fresh Type III fuel was loaded with the Fuel Accountability Delegate (Paul Sampson) or the Alternate to the Fuel Accountability Representative (Lynn Papworth) witnessing and documenting each move. This docu-mentation is filed in the SNM Accounting files with copies filed with the fuel loading procedure. After the refueling was completed according to the design LACBWR reload configuration for Cycle-6 as shown in Figure 7 of LAC-TR-068, a new small high resolution TV camera was used to read the serial number on the handle of each fuel assembly in place in the core. (This had not been possible with the equipment available during previous reloads). The numbers were easily distinguished with the new TV equipment and as the number of each assembly was read, its location was checked against the design reload configuration and 2048 054 documented. (No TV tape record was made). The configuration of the fully loaded core was thus verified to be in agreement with the design loading and the documentation was signed by L. Papworth at 0330 hours on May 8, 1979. This documentation is filed with the fuel loading procedure. 2048 J)SS }}