ML20238B082
| ML20238B082 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/17/1987 |
| From: | Eury L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20238B083 | List: |
| References | |
| 87TSB17, NLS-87-111, NUDOCS 8708210167 | |
| Download: ML20238B082 (5) | |
Text
e CP&L Carolina Power & Light Company AUG 171987 l
SERIAL: NLS-87-i l l 10CFR50.51 l
87 TSB 17 1
I 1
United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 i
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT EXPIRATION DATE OF OPERATING LICENSE EXTENSION Gentlemen:
SUMMARY
In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, i
Carolina Power & Light Company (CP&L) hereby requests a revision to the operating licenses (OLs) for the Brunswick Steam Electric Plant, Unit Nos. I and 2 (BSEP-1 and BSEP-2). The proposed changes revise the operating license expiration dates for BSEP-1 from February 7,2010 to September 8,2016 and for BSEP-2 from February 6,2010 to December 27, 2014. Consistent with 10 CFR 50.51, this establishes the period of the OLs as 40 years from date of issuance. The OLs currently specify an expiration date based on 40 years from date of issuance of the BSEP Construction Permit, February 7,1970.
DISCUSSION The current OLs' expiration dates (February 7,2010 for BSEP-1 and February 6,2010 for BSEP-2) are 40 years from the date of issuance of the Construction Permit (February 7, 1970). Construction of BSEP-1 and BSEP-2 took approximately 6 years,7 months and 4 years,10 months, respectively. As such, the effective periods of the OLs are approximately 33 years,5 months for BSEP-1 and 35 years,2 months for BSEP-2.
Environmental Report Review Carolina Power & Light Company believes that the minimum useful life of the BSEP-1 and BSEP-2 is the 40 years requested in this license amendment request. The plant was designed and constructed on the basis of 40 years of plant operation. The Company has reviewed the BSEP Environmental Report, ~ updated through Amendment No. 7, and has concluded that the report, as amende ', does not use or discuss a specific period of plant operation in its evaluations.
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Document Control Desk NLS-87-111/ Page 2 l
i Mechanical Systems /NSSS Assessment A research of plant documents was conducted to determine the basis of the 40-year l
design life of the BSEP units. Section 3.9.3.1 of the original Final Safety Analysis Report (FSAR) states that the BSEP components were specified prior to April 1,1970, and are in compliance with AEC Regulations and Codes in effect at that time. Piping and fittings were designed in compliance with USAS B3l.l.0, Power Piping Code,1967 Edition and Code Cases N7, N9, NIO Thus, pipe wall thickness, fittings, and flange ratings include adequate allowances for corrosion, as delineated in the plant piping specification, and for erosion, according to individual system requirements, for a design life of 40 years. Valves are designed in accordance with USAS B16.5. The reactor pressure vessel was designed in accordance with ASME Boiler and Pressure Vessel Code, Section 111,1965 Edition with Addenda through Summer 1967. Appendix 5.3B of the FSAR defines the reactor vessel end of life fluence in terms of the 40-year service life of the vessel, and Section 5.3.3.1.2.1 states that "the reactor vessel was designed and fabricated for a useful life of forty years based upon the specified design and operating conditions." Reactor vessel neutron fluence I
analyses have shown that the cumulative neutron fluence of the reactor vessels will not limit their minimum 40-year operating life. Surveillance capsules, irradiated inside the reactor vessel, along with the neutron dosimetry programs are providing a means of monitoring the cumulative ef fects of neutron exposure on the reactor vessel materials and confirm that the predictions used in the analytical techniques for establishing operating limitations for the reactor vessels are conservative. In addition, the design basis for Engineered Safety Features (U. S. Atomic Energy Commission, Docket Nos. 50-324 and 50-325, Design Report No.12 entitled " Design Basis for Engineered Safety Features," dated March 29,1972) states that equipment falling into categories A, B, or C is designed to withstand the total radiation dose attributed to 40 years of normal operation plus varying degrees of dosage from the 30-day design basis accident.
The Seismic Class I structures were designed considering three interrelated primary functions for the design loading combinations. The first consideration was to provide structural strength equal to or greater than that required to sustain the combination of design loads and to provide protection to other Seismic Class I structures and components. The second consideration was to maintain structural deformations within i
such limits that Seismic Class I components and/or systems would function. The third consideration was to limit containment leakage by maintaining the integrity of the primary containment liners. The primary containment system was designed, fabricated, and erected to accommodate without failure the pressures and temperatures resulting from, or subsequent to, the double-ended rupture or equivalent failure of any coolant pipe within the primary containment. The leak tightness of the primary containment was proven by actual test of leakage at the peak pressure anticipated in the design basis accident (DBA). The primary and secondary containment systems and their associated safety systems are designed and maintained so that the of f-site doses, which could result from postulated DBA, remain below the guideline values stated in 10 CFR 100. Integrity tests are performed at regular intervals to determine the integrity of the primary and secondary containments. Any abnormal degradation of the containments would be detected during the performance of these tests.
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Document Control Desk NL5-87-111/ Page 3 Since the BSEP units began operation, a number of modifications have been made. These modifications were generally made to improve the reliability and safety of the plant or to reduce the environmental impact of plant operation. Significant modifications are described in the BSEP Updated Final Safety Analysis Report (UFSAR). Modifications made without prior NRC approval were in accordance with the provisions of 10 CFR 50.59. These modifications were reported on an annual basis to the Commission. Modifications requiring prior NRC approval were made following receipt of l
a Safety Evaluation Report.
Procedures and programs are in place to detect abnormal deterioration and aging of critical plant components. Plant pressure retaining vessels, piping, and support systems are inspected in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and 10CFR50.55(g). An augmented inspection program has been instituted for those portions of the recirculation and reactor water cleanup systems which are susceptible to intergranular stress corrosion cracking (IGSCC). The Company is aggressively pursuing means of mitigating the effects of ICSCC. For example, large portions of the reactor water cleanup system piping have been replaced with non-susceptible materials. Additionally, induction heat stress improvement (IHSI) has l
been applied to many susceptible welds. Also, the Company has performed a hydrogen l
water chemistry mini-test and is evaluating the possibility of adopting hydrogen water chemistry for both BSEP units.
A comprehensive environmental qualification program has been developed for BSEP.
Safety-related electrical equipment has been environmentally qualified in accordance with the requirements of 10CFR50.49. Aging reviews have been conducted to establish a l
qualified life for the equipment. Where necessary, qualification-related maintenance j
requirements are integrated into the program to ensure that environmental qualification l
is maintained throughout the life of the facility.
Based on the above, it is evident that the design life of the BSEP units is based on 40 l
years of operation and not 40 years from issuance of the construction permit.
Occupational Exposure Assessment Carolina Power & Light Company has also considered the impact on occupational radiation exposures for the additional years'of operation proposed in this request.
Based on the operating history of BSEP and other considerations, the additional operation of BSEP-1 and BSEP-2 is expected to result in approximately 1000 man-rem per year
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L (near the industry average for a two unit site). The Company is committed to the l
ALARA concept and has a strong health physics program. The additional doses will '
represent no undue risk to the plant staff.
Population Assessment Population estimates are contained in the Brunswick Plant Environmental Report and the UFSAR. The total population within the 10-mile Emergency Planning Zone is expected to remain relatively small and the basic character of the surrounding area is expected to remain rural. The emergency plan for BSEP contains population estimates. This plan is updated in accordance with NUREG-0654, Revision 1, and provided to the NRC for 1
review.
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Document Control Desk NLS-87-111/ Page 4 1
1 Economic Assessment Operation of BSEP beyond its current operating license will be a considerable financial benefit to the customers served by CP&L. The Brunswick Plant is jointly owned by CP&L and the North Carolina Eastern Municipal Power Agency (NCEMPA).
Carolina Power & Light Company maintains and operates the NCEMPA's 18.33 percent ownership interest in BSEP. Therefore, the following information is provided on a total system basis, including both the portion of BSEP owned by CP&L and that owned by NCEMPA. Nuclear generation provides approximately 40 percent of the electric power generated by CP&L's system. Replacement of BSEP-1 generation based on the present license expiration date is currently projected to cost CP&L customers about $3.8 billion
($330 million in 1987 dollars) over the six-year period of the requested license l
extension. Replacement of BSEP-2 generation based on the present license expiration I
date is currently projected to cost CP&L customers about $2.5 billion ($240 million in j
1987 dollars) over the nearly five years requested for license extension. Therefore, j
l extending the operating license for the two BSEP units is projected to save those
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customers served by CP&L and NCEMPA approximately $6.3 billion ($570 million in 1987 dollars)in replacement power costs over the requested license extension period. The alternative to the issuance of the proposed license extension would be the cessation of I
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operation of both BSEP units in February 2010.
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SIGNIFICANT HAZARDS ANALYSIS I
l The Commission has provided standards in 10 CFR 50.92(c) for determining whether a I
significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in l
accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated;(2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Carolina Power & Light Company has reviewed this request and determined that:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because the plant was designed and constructed on the basis of 40 years of plant operation. The original BSEP FSAR analyzed operation of the facility for a minimum of 40 years. Procedures and programs are in place to detect abnormal deterioration and aging of critical plant components. A comprehensive environmental qualification program has been developed for BSEP to ensure that environmental qualification is maintained throughout the life of the facility. No changes to operational restrictions or physical alterations to the f acility will be made as a result of this request. The proposed amendment will merely allow a full 40 years operation of the BSEP units.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed change introduces no new mode of plant operation nor does it require physical modifications to the plant.
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Document Control Desk NL5-87-Ill / Page 5
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3.
The proposed amendment does not involve a significant reduction in the margin of safety. The margin of safety established in the original BSEP FSAR is based on a minimum operational period of 40 years. The proposed amendment l
merely provides this 40-year period, i
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l Based on the above reasoning, CP&L has determined that the proposed amendment does not involve a significant hazards consideration.
ADMINISTRATIVE INFORMATION I
l The revised BSEP license paragraphs are provided in Enclosures I and 2. The Company
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has evaluated this request in accordance with the provisions of 10 CFR 170.12 and determined that a license amendment application fee is required. A check for $150 is j
enclosed in payment of this fee.
l Please refer any questions regarding this submittal to Mr. Sherwood R. Zimmerman at l
(919) 836-6242.
i, Yours very truly, LA
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L. W. Eury Senior Vice President Operations Support LWE/ MAT /ccj (5205 MAT)
Enclosure cc:
Mr. Dayne H. Brown Dr. 3. Nelson Grace Mr. W. H. Ruland Mr. E. Sylvester L. W. Eury, 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 of ficers, employees, contractors, and agents of Carolina Power & Light Company.
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