ML20024G373
| ML20024G373 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/21/1978 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20024G372 | List: |
| References | |
| A00L-780321, AL-780321, NUDOCS 9102110388 | |
| Download: ML20024G373 (3) | |
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4 l'NITED STATES NUCLEAR PIGULATORY C0FMISSION NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLA?U Docket No. 50- 263 REQUEST FOR AMENDiENT TO OPERATING LICDiSE NO. DPR.22 1
(License Amendment Request Dated March 21, 1978)
Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Technical Specifications as shown on the attachments labeled Exhibit A and Exhibit B.
Exhibit A describes the proposed changes along with reasons for the change. Exhibit B is a set of Technical Specification pares incorporating the proposed changes.
This request contains no restricted or other defense infomation.
NORTHERN STATES POW'ER COMPANY By
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"'i.J Wachter Vice President, Power Production 6 System Operation On this 21st day of Ma rch 1978, before me a notary public in and for said County, personally appeared L J Wachter. Vice President, Power Production & System Operation, and first being duly sworn acknowledged that he is authorized to execute this document in behalf of Northern States Power Company, that he knows the contence thereof and that to the best of his knowledge, infomation and belief, the statemente ende in it are true and that it is not interposed for delay.
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MONIICELLO NUCLEAR GENERATING PLANI Docket No. 50-263 License No. DPR-22 LICENSE MIENDMENT REQlIEST DATED MARCH 21, 1978 PROPOSED CHANCES TO TECICiICAL SPECIFICATIONS Pursuant to 10C FR50, the holders of Provisional Operating License DPR-22 hereby propose the following change to the Appendix A Technical Specifi-cations.
PROPOSED CHANGES Page vii Modify the title of Figure 3.11.1-B and add a new Figure 3.11.1-Ea as shown in Exhibit B.
Pages 189H, 1891, 189Ia, 1893 and 189K.
Page 189In is a newly created pa v.
All pages listed here are intended for the documentation of MAPIllGR limits as determined using the partial drill ECCS model dir, cur-seu in the Safety Evaluation. The calculational results will be provided c: a later date.
Page 190.
In Specification 3.2.A delete the words "of 49 or 63 fuel rods each" REASON roi; CHANGEE In the Fall, 1978 refueling outage, two fuel types not currently in use at Monticello are scheduled to be loaded into the reactor.
i The new fuel types have pre-drilled lower tie plates to provide control-led fuel assembly bypass flow during normal operation.
These holes improve the reflood time in the postulated loss of coolant accident, re-sulting in new MAPLEGR limits for all fuel types in the reactor.
Tne Technical Specifications presently include a MAPLHGR limit for 7D230 fuel, a fuel type that is not expected to be used at Monticello in the future.
MAPLEGR limits are the refore eliminated for 7D230 fuel.
That page is replaced with limitr for a new fuel type, 8DR 264.
Limity for the other new fuel type, SDR 282, are on a newly created page.
The two new fuel types are of the same Sxb array as existing fuel, but with two water rods rather than one.
The second non-fueled rod within the assembly improves the power distribution and therefore the overall performance of the assembly. The proposed change broadens the descrip-tio ei reactor design features to encompass the new fuel type.
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9 SATETY EVAtlMTION The 8DR 264 and BDR 282 are improved fuel element designs developed as the current General Electric Company product line fuel.
The safety evaluation is topical report NEDO-24011, " Licensing Topical Report, General Electric Boiling Water Reactor, Generic Reload Fuel Application",
dated May 1977.
This document describes the fuel and its performance.
We understand that it has been under review by the Nuclear Regulatory Ccamission for some tirae. We request that the review be expcnded to en-compass the application of this retrofit fuel in the Monticello reactor.
The new MAPLHGR limits will be based on the partial drilled ECCS model which has already been accepted for BWR 4 plants.
The safety evaluation for appliention of the partial drilled model to BWR 3 plants such as Monticello, has 'already been submitted along with a January 17, 1978 1ctter f rom Mr R E Engel of General Electric to Mr D G Eisenhut of the
- Nuclear Regulatory Commission.
It is our understanding that your re-view of this license amendment request can proceed on the basis of the described modek even though the calculated results may not be available for some time. ~ Those results will be provided in writing as they become availaule.
The design features section of the technical specifications presently states the number of fuel assemblies in the reactor core and the number of fuel rods per assembly.
The proposed change will eliminate reference to the number of fuel rods per assembly which is consistent with techni-cal specifications of other plants.
The significant factor in describing the reactor design is the number of fuel assemblies in the reactor core; the number of fuel pins in an assembly is one of a number of fuel design parameters having only secondary importance.
Such details can be found by referencing the specific description of each fuel assembly type which is identified in Section 3.11 when defining the MAPLHGR limit per fuel type.
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