ML052450426

License Amendment No. 196, Extension of the Reactor Coolant System Pressure/Temperature Curve Limits

ML052450426
Person / Time
Site:	Saint Lucie
Issue date:	09/21/2005
From:	Moroney B NRC/NRR/DLPM/LPD2
To:	Stall J Florida Power & Light Co
Moroney B, NRR/DLPM, 415-3974
Shared Package
ML052450454	List: ML052450426 ML052660321
References
TAC MC5580
Download: ML052450426 (9)

Text

September 21, 2005 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE UNIT 1 - ISSUANCE OF AMENDMENT REGARDING EXTENSION OF THE REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE CURVE LIMITS TO 35 EFPY (TAC NO. MC5580)

Dear Mr. Stall:

The Commission has issued the enclosed Amendment No. 196 to Renewed Facility Operating License No. DPR-67 for the St. Lucie Plant, Unit No. 1. This amendment consist of changes to the Technical Specifications in response to your application dated December 20, 2004.

This amendment revises Technical Specifications Figures 3.1-1b, 3.4-2a, 3.4-2b and 3.4-3 to reflect an extension in the effectiveness of the pressure and temperature (P/T) limit curves from 23.6 to 35 effective full-power years (EFPY). The low temperature overpressure protection requirements, which are based on the P/T limits, are also extended to 35 EFPY.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-335

Enclosures:

1. Amendment No. 196 to DPR-67

2. Safety Evaluation cc w/enclosures: See next page

ML052450426 NRR-058 OFFICE PDII-2/PM PDII-2/LA SRXB/SC EMCB/SC OGC PDII-2/SC NAME BMoroney BClayton JNakoski MMitchell MBupp DPickett for MMarshall DATE 09/ 12 /05 09/ 12 /05 09/ 13 /05 09/ 13 /05 09/ 20 /05 09/ 21 /05 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 196 Renewed License No. DPR-67

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power & Light Company (the licensee), dated December 20, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, Renewed Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 196, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Michael L. Marshall, Jr., Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 21, 2005

ATTACHMENT TO LICENSE AMENDMENT NO. 196 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 3/4 1-9a 3/4 1-9a 3/4 4-23a 3/4 4-23a 3/4 4-23b 3/4 4-23b 3/4 4-23c 3/4 4-23c

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 196 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT, UNIT NO. 1 DOCKET NO. 50-335

1.0 INTRODUCTION

By letter dated December 20, 2004, Florida Power and Light Company (the licensee) requested to amend Renewed Operating License DPR-67 for St. Lucie Unit 1, by revising the Technical Specifications (TSs). The proposed amendment would extend the effectiveness of the reactor coolant system (RCS) pressure and temperature (P/T) limit curves from 23.6 to 35 effective full-power years (EFPY). The low temperature overpressure protection (LTOP) requirements, which are based on the P/T limits, are also extended to 35 EFPY.

The P/T limit curves and LTOP analyses were approved for 15 EFPY by the U.S. Nuclear Regulatory Commission (NRC) in Amendment No. 104 to the St. Lucie Unit 1 TSs, dated June 11, 1990. The period of applicability of the curves was extended to 23.6 EFPY in Amendment 141, dated October 27, 1995.

However, in the original calculations, the fluence was overestimated. In addition, following the initial plant operating cycles, low-leakage fuel loading patterns widened the fluence conservatism. The licensee has also identified conservatism in the reactor vessel material properties. Finally, since the original calculations, two additional surveillance capsules were removed from the reactor vessel and testing indicated that actual accumulated fluence and benchmarked fluence projections are significantly less than previously projected. Based on the conservatism in the projections and results of the surveillance capsule testing, the licensee concludes that the material properties are valid for irradiation to 35 EFPY.

2.0 REGULATORY EVALUATION

The P/T limits satisfy Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, General Design Criteria (GDC) 14, 30 and 31. These design criteria require that the reactor coolant pressure boundary be designed, fabricated, erected, and tested in order to have an extremely low probability of abnormal leakage, and of rapid or gross failure. The criteria also require that the reactor coolant pressure boundary be designed with sufficient margin to assure that when stressed, the boundary behaves in a nonbrittle manner and the probability of rapidly propagating fracture is minimized.

The method to predict the reactor vessel material irradiation damage is provided in Regulatory Guide (RG) 1.99, Rev. 2, Radiation Embrittlement of Reactor Vessel Materials.

RG 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, describes methods and assumptions acceptable to the NRC staff for determining the pressure vessel neutron fluence, and is intended to ensure the accuracy and reliability of the fluence determination required by GDC 14, 30, and 31.

3.0 TECHNICAL EVALUATION

The purpose of this review and the following evaluation is to establish the validity of the fluence value and the correctness of the 35 EFPY estimate.

Westinghouse Commercial Atomic Power report, WCAP-15446, Revision 1, Analysis of Capsule 284° from the Florida Power and Light St. Lucie Unit 1 Reactor Vessel Radiation Surveillance Program, dated January 2002, includes updates that reflect data from two additional surveillance capsules that were removed since the original fluence evaluation.

Review of WCAP-15446, Revision 1, by the NRC staff indicated that the calculations were carried out using the correct methodology, correct approximations and correct cross sections.

The original Adjusted Reference Temperature (ART) is 191°F at 1/4T (reactor vessel wall thickness) and 137°F at 3/4T for the lower shell axial welds. The licensee calculated projected values of vessel fluence for the lower shell axial welds utilizing the maximum fluence value for Operating Cycle 15 as the benchmark, a conservative assumption for future fuel loadings, and a 10 percent increase to cover unforseen variations. These calculations are conservative with respect to the guidance in RG 1.190 and are acceptable. The new critical weld fluence for 35 EFPY is 1.88x1019 neutrons per square centimeter (n/cm2), which was reduced from the maximum value of 2.85x1019 n/cm2 in the original assessment.

WCAP-15446, Revision 1, provides materials information regarding the critical lower shell axial weld based on limiting weld heat No. 305424, which is part of the Beaver Valley surveillance capsule test program. The licensee examined all of the materials in the belt zone and concluded that the lower shell axial weld remains the critical element.

This material was then used to back-calculate the fluence for which the 1/4T ART is 191°F and this resulted in the proposed value of 35 EFPY. The maximum value of 2.85x1019 n/cm2 was applied to all circumferential welds to assure that the lower shell axial weld is the critical element. The calculation is straight forward and the equations used are in accordance with RG 1.99. The NRC staff verified that the calculations were performed correctly. Therefore, the proposed extension of applicability of the P/T limit curves to 35 EFPY is acceptable. The limiting values in the P/T limit curves, which include the lowest service temperature, minimum boltup temperature, and minimum pressure limits, do not change from the previously approved values, since these limits are not based on fluence.

St. Lucie Unit 1 TS 3.4.9.1 establishes a limiting condition for operation based on the RCS P/T limits, as shown in Figures 3.4-2a, 3.4-2b and 3.4-3. The proposed amendment revises the title of each figure to indicate a change in applicability from 23.6 EFPY to 35 EFPY. The curves are not changed. This is acceptable based on the preceding evaluation. Figures 3.4-2a and 3.4-2b also have a note added to indicate the limiting material and limiting ART value used in the

analysis. The information is consistent with the analysis and has no operational impact and, therefore, the change is acceptable.

The LTOP setpoints are also based on the existing P/T limit analysis and, therefore, do not change. TS Figure 3.1-1b provides limits on maximum allowable RCS heatup and cooldown rates for a single high head safety injection pump in operation during LTOP conditions, The proposed amendment revises the title of Figure 3.1-1b to indicate a change in applicability from 23.6 EFPY to 35 EFPY. Since the curve is not changed and is based on the P/T curves, the proposed change is acceptable.

The licensee proposes to continue the practice of not applying instrument uncertainties to the P/T limit curves. However, as indicated on page 10 of Attachment 1 of the submittal, the licensee accounts for instrument uncertainties in the LTOP analysis for the relief valve enable and pressure lift setpoints. Therefore, they do not need to be accounted for in the P/T limit curves.

In summary, the NRC staff reviewed the submitted information and the request to extend the applicability of the P/T limit curves and the LTOP setpoints for St. Lucie Unit 1. The request is based on vessel fluence conservatism in the existing P/T curves. This was demonstrated by recalculation of the fluence with methods that adhere to the guidance in RG 1.190, and therefore, are acceptable. The ART value for 35 EFPY was calculated to match the existing 1/4T value of 191°F of the current P/T curves. The staff finds this acceptable, because it assures that the proposed extension of the P/T curves is valid. The LTOP setpoints remain unchanged because they are based on the P/T curves.

4.0 STATE CONSULTATION

Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.

5.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (70 FR 9993, dated March 1, 2005). Accordingly, this amendment meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: Lambros Lois James Medoff Date: September 21, 2005

Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:

Senior Resident Inspector Licensing Manager St. Lucie Plant St. Lucie Nuclear Plant U.S. Nuclear Regulatory Commission 6351 South Ocean Drive P.O. Box 6090 Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Mr. Mark Warner, Vice President Craig Fugate, Director Nuclear Operations Support Division of Emergency Preparedness Florida Power and Light Company Department of Community Affairs P.O. Box 14000 2740 Centerview Drive Juno Beach, FL 33408-0420 Tallahassee, Florida 32399-2100 Mr. Rajiv S. Kundalkar M. S. Ross, Managing Attorney Vice President - Nuclear Engineering Florida Power & Light Company Florida Power & Light Company P.O. Box 14000 P.O. Box 14000 Juno Beach, FL 33408-0420 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Mr. J. Kammel Florida Power & Light Company Radiological Emergency 801 Pennsylvania Avenue, NW. Planning Administrator Suite 220 Department of Public Safety Washington, DC 20004 6000 Southeast Tower Drive Stuart, Florida 34997 Mr. Douglas Anderson County Administrator Mr. William Jefferson, Jr.

St. Lucie County Site Vice President 2300 Virginia Avenue St. Lucie Nuclear Plant Fort Pierce, Florida 34982 6351 South Ocean Drive Jensen Beach, Florida 34957-2000 Mr. William A. Passetti, Chief Department of Health Mr. G. L. Johnston Bureau of Radiation Control Plant General Manager 2020 Capital Circle, SE, Bin #C21 St. Lucie Nuclear Plant Tallahassee, Florida 32399-1741 6351 South Ocean Drive Jensen Beach, Florida 34957 Mr. Terry Patterson