ML20085C305
| ML20085C305 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/29/1991 |
| From: | Vaughn G CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-91-213, TAC-66082, TAC-66083, NUDOCS 9109040266 | |
| Download: ML20085C305 (2) | |
Text
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e Caroina Power A Light Cornpany P o 00 mt e nwee N c tue SERIAL: NLS DI-213 G.EVAUGHN vice P,eneent Nsclear Services oepartment United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRZ PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50 325 & 50424/ LICENSE NOS DPR 71 & DPR 02 EXTENSION OF OPERATIND LICENSE (NRC TAC NOS,06082 AND 00033)
Gentlemen:
On August 17,1987 (Scrial: NLS 87111), Carolina Power & Light Company subrnitted a license amendment request to extend the expiration date for the operating licenses for the Brunswick Steam Electric Plant, Units 1 and 2 to 40 years from the date the operating licenses were issued.
The existing operating license expiration dates are based on 40 years from the date the construction permits were issued.
By letter dated June 29,1990, CP&L responded to an NHC request to assess the impact of the proposed extension on the reactor vessel, mechanical equipment, electrical equipment, and plant structures. On August 7,1901, the NRC Staff requested a clarification of the Brunswick Steam Electric Plant's compliance with the requirements of 10 CFR 50, Appendix H relative to the reactor vessel. A conference call was held on August 13,1991 to discuss this issue. Based on the call, the following clarifying information is being provided.
The Brunswick Plant reactor vessels comply with the requirements of 10 CFR 50, Appendix H and the ASME Code,Section XI. As required by 10 CFR 50, Appendix H, a reactor vessel materiel surveillance program was established at the time the Facility Operating Licenses were issued to monitor the effects of radiation induced changes on the material properties of the reactor vessel.
The Brunswick Plant established a surveillance capsule withdrawal schedule which uses three capsules. By letter dated October 26,1988, CP&L proposed revisions to the surveillance capsule withdrawal schedule in accordance with 10 CFR 50, Appendix H, paragraph 11,0.3. The revised schedule was intended to tso more compatible with boiling water reactor irradiation conditions and Brunswick specific materials. The NRC Staff subsequently approved the withdrawal schedule revisions through the issuance of Amendment Nos.140 and 172 to the Facility Operating Licenses.
The reactor material surveillance program will require the surveillance capsules to be withdrawn and exaniined to dctermine radiation-induced changes in material properties of the reactor vessels.
The data so obtained will be used as described in 10 CFR 50, Appendix G, Sections IV and V and, based on the observed changes, any necessary revisions to the pressure / temperature limit curves and surveillance capsule withdrawal schedules will be submitted to the NRC Staff for review and approvalin accordance with Section ill of 10 CFR Part 50, Appendix H. Therefore, the Brunswick Plant teactor vessel surveillance program complies with the requirements of 10 CFR Part 50, Appendix H and provides adaquate assurance that the reactor vessel will be monitored through out the licensed life of the plant for radiation-induced changes in material t,roperties.
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Document Control Desk NLS 91213 / Page 2 Based on plant operating history and a projected 75 percent capacity for the remainder of the proposed 40 calendar year operating life of the plant, Brunswick Unit 1 is expected to achieve 20.9 effective full power years (EFPY) of operation. Brunswick Unit 2 is expected to achieve 25.8 EFPY of operation. Based on these expected operating projections and the resulting vessel irradiation, the most limiting 4RTm values are estimated to be 628 F (ID) and 45* F (1/4T) for Unit 1 and 720 F (ID) arid 63' F (1/4T) for Unit 2. Thus the expected transition temperature shifts at the end of 40 calendar years of plant life are still expected to be less than 100* F, and the use of throo surveillance capsules as required by ASTM E 185 82 remains adequate.
Please refer any questions regarding this submittal to Mr. W. R. Murray at (919) 546-4601.
Yours very truly, j
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G.E.Vaughn WPM /wrm (olext5.wpf) cc:
Mr. Dayno H. Brown Mr. S. D, Ebneter Mr. N. B. Le Ms. B. L. Moraf ari Mr. R. L. Prevatte G. E. Vaughn, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Lloht
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