ML20217H293

Forwards Safety Evaluation Re Review of Pressure Temp Limits Rept & Methodology for Relocation of Reactor Coolant Sys Pressure Temp Limits.Methodology Acceptable for Ref Administrative Controls Section of TS

ML20217H293
Person / Time
Site:	Farley
Issue date:	03/31/1998
From:	Berkow H NRC (Affiliation Not Assigned)
To:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
Shared Package
ML20217H297	List: ML20217H293 ML20217H319
References
TAC-M99338, TAC-M99339, NUDOCS 9804030262
Download: ML20217H293 (5)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20006-4001 g

'+ , + March 31, 1998 Mr. D. N. Morey, Vice President Farley Project Southem Nuclear Operating Company, Inc.

. Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, ACCEPTANCE FOR REFERENCING OF PRESSURE TEMPERATURE LIMITS REPORT (TAC NOS. M99338 AND M99339)

REFERENCES:

1. Letter from A. Schwencer, NRC, " Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment No.13 to Facility Operating License No. NPF 2, Alabama Power Company, Joseph M.

Farley Nuclear Plant, Unit No.1 Docket No. 50-348," July 31,1979.

2. WCAP-12471, Westinghouse Electric Corporation, " Analysis of Capsule X from the Alabama Power Company, Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program," December 1989.

3. WCAP-14196, Westinghouse Electric Corporation, " Analysis of Capsule W from the Alabama Power Company, Farley Unit 1 Reactor Vessel Radiation Surveillance Program," February 1995.

4. Letter from C.1. Grimes, NRC, to R. A. Newton, Westinghouse Electric Corporation, " Acceptance for Referencing of Topical Report '

WCAP-14040, Revision 1, Methodology Used to Develop Cold Overpressure Mitigating System Setpohts and RCS Heatup and Cooldown Limit Curves," October 16,1995.

5. WCAP-14040-NP-A, Revision 2, Westinghouse Electric Corporation,

• Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Hestup and Cooldown Limit Curves," January 16, 1996.

6. NRC Generic Letter 96-03, " Relocation of the Pressure Temperature Limit Curves end Low Temperature Overpressure Protection System Limits," January 31,1996.

7. WCAP-14687, Westinghouse Electric Corporation, " Joseph M. Farley, Units 1 and 2, Radiation Analysis and Neutron Dosimetry Evaluation,"

June 1996.

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8. WCAP-14689, Revision 1, Westinghouse Electric Corporation,

" Joseph M. Farley Units 1 and 2 Heatup and Cooldown Limit Curves for Normal Operation and PTLR," June 1996.

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D. N. Morey 9. CE NPSD-1039, Revision 2, A. B. Combustion Engineering, "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Welds, CEO Task 902," June 1997.

10. Letter from D. Morey, Southem Nuclear Operating Company, to NRC Document Control Desk, " Joseph M. Farley Nuclear Plant Technical Specification Change Request, Pressure Temperature Limits Report,"

July 23,1997,

11. Letter from D. Morey, Southem Nuclear Operating Company, to NRC Document Control Desk, " Joseph M. Farley Nuclear Plant Technical Specification Change Request Correction to Pressure Temperature Limits Report," September 30,1997.

12. Letter from D. Morey, Southem Nuclear Operating Company, to NRC

' Document Control Desk, " Joseph M. Farley Nuclear Plant Pressure Temperature Limits Report," October 27,1997.

13. Letter from J. Zimmerman, NRC, to D. Morey, Southem Nuclear Operating Company, " Request for Additional Information Related to Proposed Amendments Regarding Pressure Temperature Limits Report, Farley Units 1 and 2," November 14,1997.

14. Letter from D. Morey, Southem I, . . lear Operating Company, to NRC Document Control Desk, " Joseph M. Farley Nuclear Plant Technical Specification Change Request, Pressure Temperature Limits Report,"

December 18,1997.

15. Letter from D. Morey, Southem Nuclear Operating Company, to NRC Document Control Desk, " Joseph M. Farley Nuclear Plant Technical Speification Change Request, Pressur6 Temperature Limits Report,"

February 12,1998.-

The NRC staff has completed its review of the methodology associated with the pressure temperature (P/T) limit curves, the residual heat removal (RHR) system relief valves used for overpressure mitigation, and the P/T limits report (PTLR), submitted by the Southem Nucear Operating Company, Inc. (SNC). The staff finds the methodology to be acceptable for referencing in the administrative controls section of the Farley Nuclear Plant, Units 1 and 2, Technical Specifications e tt e extetspecified and under the limitations delineated in your submittals and the asso*eted NRC C+afety Evaluation, which is enclosed. The Safety Evaluation defines the basis for acceptance of the submittals. Our acceptance applies only to the matters desenbod in the submittals.

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D.N.Momy The NRC notes that SNC should address the method for assessing the credibility of the reactor pressure vessel surveillance capsule data consistent with the criteria provided in the revised rule (10 CFR 50.61) or in Regulatory Guide 1.gg, Revision 2, in future revisions to the PTLR.

With respect to these methods, SNC should apply the ratio procedure when it is determined that the chemical composition of the surveillance capsule weld material is dl#erent from that of its corresponding beltline weld material.

The methodology for review relating to the P/T limit curves and the RHR system relief valves setpoint is provided in the listed references. WCAP-14040-NP-A provided parts of the methodology used for determining the acceptance of the Fariey methodology.

The methodology in WCAP-14040-NP-A, along with supplements provided by SNC, will be used to calculate future changes to the P/T limit curves. SNC may generate new P/T limit

" curves in accordance with this methodology without prior approval of the staff. However, changes to the methodology must first be reviewed and approved by the staff. System limits may be subject to audit by the staff through inspections as necessary.

We do not intend to repeat our review of the matters described in the submittais if the submittals appear as references in other license applications relating to your plants, except to  !

ensure that the material in the submittals is still applicable to your plants as indicated in the conclusion section of our Safety Evaluation.

Should our criteria or regulations change so that our conclusions as to the acceptability of the methodology is invalidated, licensees referencing these documents will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.

Sincerely, Herbert N. Berkow, Director Project Directorate ll-2 Division of Reactor Projects - 1/11 ONice of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

Safety Evaluation 3 cc w/ encl: See next page' L'

D. N. Mor:y March 31,1998

,t ,

The NRC notes that SNC should address the method for assessing the credibility of the reactor pressure vessel surveillance capsule data consistent with the criteria provided in the revised l

rule (10 CFR 50.61) or in Regulatory Guide 1.99, Revision 2, in future revisions to the PTLR.

With respect to these methods, SNC should apply the ratio procedure when it is determined I l

that the chemical composition of the surveillance capsule weld materialis different from that of its corresponding beltline weld material.

l The methodology for review relating to the P/T limit curves and the RHR system relief valves )

setpoint is provided in the listed references. WCAP-14040-NP-A provided parts of the i methodology used for determining the acceptance of the Farley methodology.

The methodology in WCAP-14040-NP-A, along with supplements provided by SNC, will be used to calculate future changes to the P/T limit curves. SNC may generate new P/T limit curves in accordance with this methodology without prior approval of the staff. However, changes to the methodology must first be reviewed and approved by the staff. System limits may be subject to audit by the staff through inspections as necessary.

We do not intend to repeat our review of the matters described in the submittals if the submittals appear as references in other license applications relating to your plants, except to ensure that the material in the submittals is still applicable to your plants as indicated in the conclusion section of our Safety Evaluation.

Should our criteria or regulations change so that our conclusions as to the acceptability of the methodology is invalidated, licensees referencing these documents will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.

Sincerely, Original signed by:

Herbert N. Berkow, Director

((k hme Ghdi M fY3Wi Project Directorate ll-2 Division of Reactor Projects -l/ll Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 DISTRIBUTION Docket File BSheron JStrosnider

Enclosure:

Safety Evaluation PUBLIC GHolahan ESullivan PDll-2 RF TCollins KWichman cc w/ encl: See next page OGC EWeiss BElliott ACRS RCaruso JMedoff LPlisco,Rll LLois WBeckner PSkinner,Rll CJackson MWeston BBoger JZwolinski HBerkow DOCUMENT NAME: G:\FARLEY\FARLEY.LTR

• see previous concurrences Indicate in the box: "C" = Copy w/o enci "E" = Copy w/enci "N" = No copy OFFICE TSB:ADP

• l PM:PDll 2 (L l Pf/jf)Dil-2 l6

,X(. '

NAME MWWeston LBerry Atmrherman DATE 3/19/98 73 /b)/98 J/3!//98 OFFICE C/SRXB:DSSA* C/EMCB:DE* C7TSB:ADP* PD:PDil-2*

NAME TCollins ESullivan WDBeckner HBerkow DATE 3/27/98 3/23/08 3/20/98 3/30/98 OFFICIAL RECORD COPY

Joseph M. Farley Nuclear Plant

- cc:

Mr.' R. D. Hill, Jr.

General Manager-Southem Nuclear Operating Company Post Office Box 470 Ashford, Alabama 36312 Mr. Mark Ajiuni, Licensing Manager Southem Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201-12g5 Mr. M. Stanford Blanton Balch and Bingham Law Firm -

Post Office Box 306

. 1710 Sixth Avenue North

- Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southem Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health I 434 Monroe Street f Montgomery, Alabama 36130-1701 i Chairman Houston County Commission Post Office Box 6406.

Dothan, Alabama 36302 Regional Administrator, Region 11 U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Resident inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway g5 Columbia, Alabama 3631g-e 4

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