ML20155F955

Proposed Tech Specs Pages to LAR #245,changing Methodology for Sf Pool B Criticality Analysis

ML20155F955
Person / Time
Site:	Crystal River
Issue date:	10/30/1998
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20155F952	List: 3F1098-15, Rev 0 to LAR 245 to License DPR-72,to Change Methodology for Sf Pool B Criticality Analysis.Change Is Necessary Due to Boraflex Degradation in Sf Pool B.Proposed Revs to USAR, TS & Holtec Rept,Encl ML20155F955 ML20155F977
References
NUDOCS 9811060163
Download: ML20155F955 (3)

Text

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Spent Fuel Pool Boron Concentration B 3.7.14 BASES l

SURVEILLANCE SR 3.7.14d (continued)

REQUIREMENTS Operating experience has shown significant differences between boron measured near the top of the pool and that measured elsewhere. As long as this SR is met, the analyzed events are fully bounded. The 7 day Frequency is acceptable because no major replenishment of pool water is expected to take place over this period of time.

REFERENCES 1. Criticality Safety Analysis of the Crystal River Unit 3 Pool A Spent Fuel Storage Rack, S. E. Turner, Southern Science, SS-162.

2.

Riihilisis?^6fithi!CFii StoragelRacksiWith.1 Bo ra fl ex7 tal? DegRWsE radat ion P6617BISpistRusl_.

1. S H ERTu rne r _i Hol tec41ntevnati onal y HI-982056g10ctobeN l998F^~

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TEdhhTE3 FSfEEi f i^65ti BE~C hshie',,c? deb t~ 1757 October 31, 1000.

3. NRC Safety Evaluation Report for Amendment 134 to CR-3 Operating License, dated April 16, 1991.

l l

l Crystal River Unit 3 B 3.7-71 .

RiV}ii65.^,mendmentNo.449 9811060163 981030 F PDR ADOCK 06000302P P PDR jj

l Spent Fuel Assembly Storage B 3.7.15 BASES (ccatinued) l SURVEILLANCE SR 3.7.15.1 REQUIREMENTS l Verification by administrative means that initial enrichment and burnup of fuel assemblies in accordance with Figure 3.7.15-1 and Figure 3.7.15-2, and Figure 3.7.15-3 is required prior to storage of spent fuel in storage pool A or pool B (as applicable). This surveillance ensures that fuel enrichment limits, as specified in the criticality safety analysis (Ref. 2), are not exceeded. The surveillance Frequency (prior to storage in high density region of the fuel storage pool) is appropriate since the initial fuel I enrichment and burnup cannot change after removal from the Core.

REFERENCES 1. Criticality Safety Evaluation of the Pool A Spent Fuel Storage Racks in Crystal River Unit 3-with Fuel of 5.0% Lnrichment, S. E. Turner, Holtec Report HI 931111, December 1993.

2. Rsshsl S to rag' iiffi'b fIthh?CFistilI RiiiiR P6bli BISiisht? FUsle (

1998;E "

Hol CFysttectInternationalif HI k982056 F Ri EF Udit~3 ShE5t~Fde' p 0ctobsN20p'[B ' ~

SteF556~P55.

Criticality Analysis, W. A. Mittkopf, L. A. H;;sler, B&W Fuci Company, BAW 2209P, Octcber 1993.

3. NUREG 0800, Standard Review Plan, Section 9.1.1 and 9.1.2, Rev.2, July 1981. l

4. 10 CFR 100.

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5. CR-3 FSAR, Section 9.6. l l

l l

Crystal River Unit 3 8 3.7-76 Revision No. -14 l

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 ATTACHMENT C LICENSE AMENDMENT REQUEST #245, REVISION 0 Revision to Licensing Basis - Methodology Change for Boraflex Degradation IIoltec Report, III-982056, " Reanalysis of The Crystal River Pool B Spent

Fuel Storage Racks with Boraflex Degradation," October 20,1998 J

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