NRC-96-0126, Forwards Supplemental Info Re License Amend to Safety Limit Re Min Critical Power Ratio

Forwards Supplemental Info Re License Amend to Safety Limit Re Min Critical Power Ratio

ML20134F776
Person / Time
Site:	Fermi
Issue date:	10/29/1996
From:	Gipson D DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-96-0126, CON-NRC-96-126 NUDOCS 9611080034
Download: ML20134F776 (7)

Text

'. 8 Douglio fl Gipton I Senior Vke President Nuclear Generation Detroit ree E*

6400 North Dme Nghway Newport, Mictugan 48166 (313) 586-5249 October 29,1996 NRC-96-0126 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555

References:

1) Fermi 2 NRC Docket No. 50 341 NRC License No. NPF-43

2) Detroit Edison Letter to NRC," Proposed Technical Specification Change (License Amendment) - Safety Limit -

Minimum Critical Power Ratio (MCPR)," NRC-96-0075 dated September 5,1996

3) Detroit Edison Letter to NRC," Supplemental Information Regarding Proposed Technical Specification Change (License Amendment) - Safety Limit - Minimum Critical Power Ratio (MCPR)," NRC-96-0119 dated October 14,1996

Subject:

Supplemental Information Regarding Proposed Technical Specification Change (License Amendment) - Safety Limit - Minimum Critical Power Ratio (MCPR)

On September 5,1996 Detroit Edison proposed a License Amendment (Reference 2) to change the Minimum Critical Power Ratio (MCPR) Safety Limits in Technical Specification 2.1.2. The proposed changes result from a cycle specific calculation performed for Fermi 2 Operating Cycle 6, expected to commence in November of 1996. On October 14,1996 Detroit Edison provided supplemental information regarding this proposed License Amendment (Reference 3). Included with that j i submittal was a report from General Electric which provided an explanation of 1 i

differences between the Fermi 2 cycle specific calculation and the generic calculation  ;

for the Minimum Critical Power Ratio (MCPR) Safety Limits.  ;

/k00\ j 070082 l 9611000034 961029 PDR ADOCK 05000341 P PDR I

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. USNRC October 29,1996 NRC-96-0126 Page 2 The General Electric report provided in Reference 3 briefly described the method used to select the MCPR Safety Limit for single loop operation (SLO). Since that supplemental information was provided, General Electric has performed an analysis of the single loop operation (SLO) MCPR Safety Limit for Fermi Cycle 6. This analysis ,

confirms that the SLO MCPR Safety Limit value requested in Reference 2 is appropriate for Fermi Cycle 6. A description of this analysis and additional description of the initial method used to select the Cycle 6 SLO MCPR is included in ]

the attachment to this letter. I I

Detroit Edison has evaluated this supplemental information regarding the proposed i Technical Specification change and has determined the Significant Hazards evaluation l provided with the proposed amendment is not affected by this supplemental I information and that No Significant Hazards Consideration is involved.

If you have any questions, please contact Mr. Joseph Conen at (313) 586-1960.

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Sincerely, j

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Attachment ,

l cc: A. B. Beach l M. J. Jordan i A. J. Kugler A. Vegel Supervisor, Electric Operators, Michigan l Public Service Commission, J. R. Padgett l

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, jc . USNRC October 29,1996 NRC-96-0126 1 Page 3 -

l I, DOUGLAS R. GIPSON, do hereby affirm that the foregoing statements are based -

on facts and circumstances which are true and accurate to the best of my knowledge and belief.

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DOOGLAf R. GIPSON Senior Vice President ,

l On this M ' day of ,1996 before me personally appeared Douglas R. Gipson, being first duly sworn and says that he executed the foregoing as his free act and deed.

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H?AT -

Notary Public ROSAUE A. ARMETTA l' NOTARYPUBUC-HONROE COUNTY,M1 MYCOMMISS10N EXPHES10/11/09

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. Attachment to NRC-96-0126 Page1

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ATTACHMENT 1

DESCRIPTION OF FERMI 2 i

CYCLE SPECIFIC ANALYSIS SINGLE LOOP OPERATION l MCPR SAFETY LIMIT I

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GENuclearEnergy R. . lack Bragg fuelProtea Manager Nuclear ruel- Amercas GeneralElectnc Company P O % 780. M:CA33. W;im.og'on. NC28401 910 C5 5751 R18:% - 22,rev. I Dal Comm. 8*292 5751 rr 910 675-5684 October 28,1996 cc: S. E. Kremer M. H. Lim S. T. Hsieh*

J. M. Thorson W. M. Tucker

• with attachments Mr. B. L. Myers Principle Engineer, Nuclear Fuel Enrico Fermi Unit 2 Detroit Edison Company 6400 North Dixie Highway 290 TAC Newport, MI 48166 l

SUBJECT:

Fermi- 2 Cycle SLMCPR Licensing Clarification

Dear Mr. Myers:

Please find enclosed, for DECO's information and use a letter written by C. L. Heck of our Design Process Improvement team clarifying Fermi 2 Cycle 6 Safety Limit MCPR (S calculation.

1996. The letter has been modified to reflect our conversation today, Monday, If you have any questions, please call me or C. L. Heck at (910) 675 - 6134.

i Sincerel ,

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.. ra Fuel Projec Manager Fermi - 2

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, GENuclearEnergy Nudentfuel-Amertcrs Mall Code AD l

Fax 8*292-5684 1 cc: C.L Heck TO: J.L Rash R.J. Bragg R.H. Szilard LRf 262 96180 FROM: B.R. Fischer/C.L Heck DATE: October 28,1996 1

SUBJECF: Fermi 2 Cycle 6 SIJdCPR Single Imop Operation (SID) Ucensing Clarification l

REFERENCES 1. Genem! Electric Standard Applicationfor RmdorFud, NEDE-24011-P-A-1 S-US, i August 1996.

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2. Licensing Topical Report, Genen!Electnc B%R 7kennal Analysis Basis (GETAB): {

Data, Conelation and Design Application, NEDO-l0958-A, January I977.

3. GeneralElectricFud Bundle Designs, NEDE-SI 152-P, Revision 5, June 1996.

4. CE13 Compliance With Amendment 22 of MDE24011-P-A (GESTAR-II), NEDE. 32198P, Dece nber 1993. I i

5. Gell Compliance With Amendment 22 ofMDE-24011-P-A-10 (GESTAR-II), NEDE. 31917P, April 1991.

In order to assist in answering the NRC questions about the Fermi 2 Cycle 6 Safety Limit MCPR (SLMCPR) calculation the following additional information regarding the adder to the SLMCPR for single loop operation (SLO) is being provided:

1. What is the basis for the SIAICPR SID adder of 0.02?

l A number of plant-specific single loop operation (SID) SLMCPR calculations have been performed for i gel I and the other fuel product lines. Rese calculations use the same procedure as used for the plant-specific dual-loop SLMCPR calculations (Reference I ), and the methods described in Reference 2. The only difference is that the larger uncertainties associated with SID as specified in Table 3.3 of ]

2 Reference 3 are used. Reference 3 is incorporaed by reference from Reference 1. The uncertainties associated with SLO remain unchanged from those used previously in determining the SID adders to the generic dual. loop SIAiCPRs. The conclusion of these plant-specific SID calculations is that the l SLO adder is linearly correlated to the base value (dual-loop SLMCPR) and is not correlated to a j pardcular bundle design. For example, larger base dual-loop SIAICPR values have larger adders 1 independent of whether the bundle is GElI or GEIS. For a base calculated SLMCPR value of 1.09 the appropriate SLO SIAICPR adder is 0.02, which is the same value applied previously to the generic GEIS base dual-loop S13fCPR value of 1.09 documented in Reference 4. This result is contrasted to the 0.01 l SLMCPR adder which has previously been applied to the generic gel I base dual-loop SLMCPR value of 1.07 documented in Reference 5. The 0.02 SID SIAICPR adder is applicable for Fermi-2 Cycle 6, and results in a SID SIAICPR of 1.11. Based on the verified data accumulated to the present, the 0.02 adder is conservative for a 1.09 base S13f CPR since a best fit to the data yields an adder between 0.01 and 0.02. This fact has been confirmed by a specific analysis, performed in accordance with References I and 2, for Fermi-2 Cycle 6. This calctdation shows the specific adder to be between 0.01 and 0.02. j Thus the use of 0.02 is conservative.

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e-RJ. Bragg Fermi-2 Cycle 6 SLMCPR Single loop Operation (SLO) Licensing Clarification October 28,1996

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B.R Fischer CL Heck Technical Program Manager Principal Engineer Nuclear Fuel- Americas Design Processimprovement (910) 675-5838; 8'292-5838 (910) 675 6134,8*2924134 Page 2