ML20205F263

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Proposed Tech Spec Changes,Deleting MAPLHGR Limit Curves for Fuel Types 8D250 & 8D262,adding MAPLHGR Limit Curves for GE Fuel Types BP8DRB282 & BP8DRB299 & Extending MAPLHGR Limits for Fuel Type Barrier Lta. All MAPLHGR Curves Replotted
ML20205F263
Person / Time
Site: Quad Cities, 05000000
Issue date: 10/29/1985
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20205F242 List:
References
0819K, 819K, NUDOCS 8511050272
Download: ML20205F263 (8)


Text

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l l l ATTACHMENT 1 i

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i (ESCRIPTION OF PROPOSED CHANGES J.0 TECHNICAL SPECIFICATION FIGURE 3.5-1 i

1) MAPLHGR limit curves for fuel types 80250 and 8D262 have been celeted as these fuel types are no longer utilized.

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2) MAPLHCR limit curves have been added for CE fuel types 8P8DRB282 and '

BP80R8299 based on E and A Sheet No.14 to NEDO-24146A, Tables 4R and 45, respectively. Refer to Figure 3.5-1 Sheets 2 and 4 in Attachment 2.

( 3) MAPLHGR limits for fuel type " Barrier LTA" (Lead Test Assemblies) have l been extended out to 55,000 mwd /t planar average exposure based on E and l

A Sheet No. 14, Table 4H. Refer to Figure 3.5-1 Sheet 1 in Attachment 2.

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l 4) All MAPLHGR curves have been replotted for clarity with page numbers and i

sheet numbers adjusted as requited to reflect the above additions and deletions. ,

All MAPLHCR curves contain revision bars to indicate changes from l values currently in the Quad Cities Technical Specifications.

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I ATTACHMENT 2 Proposed Change to Appendix A Technical Specifications to Operating License DPR-29 Revised pages: Figure 3.5-1 (Sheets 1 through 4 of 4) 0819K

. GUAD CITIES DPR- 29 1

MAPLHGR Vs. Average Planer Exposure 1 Fuel Type Bdtrier LTA 12.5- , I I I I I I I I 12.0- _. ...  ; I m .

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I I I I I I 0 10,DOO 20,000 30.d00 50.D00 60'000 I ' 49000 Average Planer Exposure (WW3/St)

MAPLHGRVs.AveragePla/nerExposure Fuel Types P80RB265L P80G8265L 1

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o nswutu DPR- 29 MAPLHGR Vs. Average R!aner Exposure Fuel Type BP80RB299 12.5- , ,, ,

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MAPLHGR Vs. Average Pl.aner Exposure fuel Type P80RB282 ,

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( Figure 3.5-1 (5heet 2 of 4)

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... . GUAD CITIES

, orn- as MAPLHGR Vs. Average flaner Exposure Fuel Type P8DRB239 h

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MAPLHGR Vs. Average Plaper Exposure fue! Types P80RB265H/BP80RB265H 12.5_

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0 10,000 20,000 30.000 40,000 50,000 Average Planet Esposure (WWd/St) rigure 3.5-1 Isheet 3 of Al J 2___ _ - - _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

. . . . GUA0 CITIES DPR- 29 MAPLHGR Vs. Average Planer Exposure fue1 Type BP80RB282 12.5 12.0 N ,.

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AserogePlanetExposure(wad /St)

MAPLHGR Vs, Average Planer Exposure 1'

Fuel Type BP8DRB283H 12.5 , 1

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) 10,D00 20.D00 33.b00 40,600 50,D00 AveragePlanerCaposure(W43/St) l Figure 3.5-1 tsheet 4 of 4)

ATTACHMENT 3 Evaluation of Significant Hazaros Consideration Oescription of Amenoment Request The proposed Technical Specification amendment includes the following (also see Attachment 1):

- Deletion of MAPLHCR limit curves for fuel types no longer in use

- Addition of MAPLHCR limit curves for new fuel types

- Extension of a MAPLHCR limit curve to higher fuel exposures.

The new and extended HAPLHCR limits are based on values provided in Erratta and Addenda Sheet No.14 to NE00-24156A, the Dresden and Quad Cities Loss of Coolant Accident Analysis.

! Dasis for Proposed No Significant Hazards Consideration Determination Commonwealth Edison has evaluated the proposed Technical Specifi-cation amendnent ono determined that it does not represent a s10nificant hazaros consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92(c), (;peration of Quad Cities Unit 1 in accordance with the proposed amendmen',s will not:

1) involve a significant increase in the probability or consequences of an accident previously evaluated because u) the amendments involve restrictions on the reactor power distribution during normal operation which of itself cannot initiate an accicont and therefore does not increase the probability of an accident and b) these restrictions on power distribution are based on a reunalysis

! or re-evaluation of accidents in uccordant.u with NRC approved l methods and are specifically provided to ensure that the l consequences of accidents (LOCA) remain within thu existing l accident criteria established for Quad C.tles.

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l 2) create the possibility of a new or different kind of accident from any accident previously evaluated for the same ruason as 1)a above and i

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3) involve a significant reductiL1 in the margin of safety since the amendments are specifically intended to ensure that the 10 CFR 50.46 ECCS criteria continue to be protected during future operation.

In consideration of the above, Commonwealth Edison expects that NRC approval of these amendments should not be predicated on satisfactory resolution of public comments or intervention as provided for by 10 CFR 1

50.91(a)(4).

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  • A ATTACHWNT 4 Errata and Addenda No.14 to NE00-24146A " Loss-of-Coolant Accident Analysis Reptsrt for Dresden Units 2,3 and Quac Cities Units 1, 2 Nuclear Power Stations".

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