ML20207K046
| ML20207K046 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/30/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207K033 | List: |
| References | |
| NUDOCS 8701090199 | |
| Download: ML20207K046 (4) | |
Text
.
3 4Gg 6
Io UNITED STATES 4
g
[
p, NUCLEAR REGULATORY COMMISSION 5
.-l WASHINGTON, D. C. 20555 Y
% *.W.. + p SAFETY FVAlllATION RY THF OFFICE nF N'ICLEAR PEACTOR REGULATTON RELATED TO AMENDMENT NOS.
89 ANO 75 TO FACTLITY OPERATING LICENSF UGS. NPF-4 AND NDF-7 viRGTNTA ELECTRIC AND POWE0 CnypANy OLO nn'4INTON ELECTRIC COOPERATIVE NORTH ANNA POWED STATION,IJNITS NO. 1 ann NO. 2 00CKET NOS. 50-338 AND 50-110 INTR 00llCTION Ry application dated August ??, 1986, and as supplemented by letters dated December 5, and December 10, 1986, the Virninfa Electric and Power Company (the licenseel reauested amendments to Facility Operatina licenses No. NPF d and No. NDF 7 for the North Anna Dower Station, linits No. I and No. ? (WA-1A?i, respectively. The proposed amendments would change the license expiration date for NA-1 from February 18, 2011 to April 1, 9018, and change the license exoiration date for NA-2 from Februarv 19, ?011, to August 21, 2020 DISCtJSSION Section 103.c of the Atomic Energy Act of 195a provides that a license is to be issued for a specified period not exceeding 40 vears.
10 CFR 50.51 specifies that each license will he issued for a fixed period of time not to exceed 40 years from date of issuance.
10 CFR 50.56 and 10 CFD 50.57 allow the issuance of an operatina license pursuant to 10 Cr4 50.51 after the construction of the facility has been substantially completed, in confomity with the construction oermit and when other provisions specified in 10 CFR 50.57 are met.
The currently licensed tern for NA-1&2 is 40 years from the date of issuance o# the construction permits (February 19, 10711 Accountina for the time that was required for plant construction, this represents an effective operating license term of 33 vears for NA-1 and 30 years and 6 months for NA-9 Consistent with Section 103.c of the Atomic Eneroy Act and Sections 50.51, 50.56 and 50.57 of the Commission's reaulations, the licensee, by its application of August ??,
1986, seeks extensions of the operatino license tems for NA-1A2 such that the
- ixed period of the licenses would he 40 vears from the date of operatino
~
license issuance.
EVAlllATION The Commission has reviewed the licensee's application for amendments and previous licensing documents, including the NA-14? Final Sa#etv Analysis Report 8701090199 861230 PDR ADOCK 05000338 P
~
l
. (FSAR1, the NA-1A2 Safety Evaluation Deport / SED 1 with its supplements, and more recent Commission policy and documents, to determine the effects of the requested extension upon safety. The Commission's evaluation considered the potential effects to systems and eautoment, including effects due to aging of electrical equipment important to safetv and chances in the fracture toughness properties of reactor vessel beltline materials due to neutron irradiation. The evaluation also included the effects of updated population estimates upon the previous determination of exclusion area, low population zone (LP7.' and popu-lation center distance, in accordance with 10 CFR 100 Other areas of the Commission's previous safety review of the NA-1A9 Station are not affected bv the reouested extension since NA-142 was oriainally desioned, constructed and has been evaluated hv the Commission on the basis o# a 40 year service life.
3.
Updated Population Fstinates The. 'NA-1A2 Safety Evaluation Deport (SERI, issued. lune 1076, discussed the NoC finiings regarding the 10 CFR Part 100 siting criteria for the NA-1A? Exclusion Arei. Low Population Zone, and nearest population centers in Section 2.1.
The licehsee's request to extend the license periods on these criteria are discussed belok:
Exclusion Area: The exclusion area is discussed in the NA-1A2 SER, Section 2.1.7 The Exclusion Area consists of the licensee-owned property in approximatelv a 5000 ft. radius (min. distance 4427 ft.i of the station. The licensee owns all of the land, includino the plant access road, within the Exclusion Area, as well as the mineral rights to the land. The licensee has the authority to control all activities within the Exclusion Area and anticipates no chances to the Exclusion Area boundary during the extended license period. The Exclusion Area remains unchanged from that discussed in Section 9.1.7 of the NA-1&7 SER and therefore the NPC conclusions in the SER reaarding the Exclusion Area also remain unchanged.
Low Ponulation Zone: The Low Population Zone (LPZi is described in Section 9.1.3 of the NA-1A7 SEP. NA-1A9 LP7 has an outer radius of six miles. The present and pro.iected populations for the 5,10, 30 and 50 mile radii for the vears 1070,1900, and 20?n are oiven in Table 2.1 of the NA-la? SER. The data in Table 2.1 assumes an annual population growth rate o# about 1.5%.
This assumption is consistent with that estimated hv the Commonwealth of Virainia (October 19861 for the approximately 50 mile radius around North Anna.
Based on available census data, the permanent 1980 population within the in mile radius is la,610. The extrapolated population from the NA-1&7 SER, Table 2.1 for the 10 mile radius in 1080 is 0101. Thus, the actual population in this instance (where comoerable data is availablei shows an actual population about 59T areater than the proiected value in the SER.
However, based on vore general population trends and the reasons listed below, the staff expects no sianificant increase in LPZ population durino the extended license period and believes that there will continue to be reasonable assurance that appropriate measures can he taken on behalf of the population within the LP7. in the event of an accident.
. Ore, consistert with the oriainal NA-1A' SER evaluation, the area within five miles (LPZ equals six milesl of the plant remains rural, extensively wooded, interspersed with farms and is expected to remain predominantiv rural during the extended license period. Two, the licensee has established a 10 mile radius Emeroency Planning Zone, enveloping the LP7, over which the licensee provides reasonable assurance that protective measures could be taken on behalf of the population in the event of an accident. Three, the NDC Safetv Evaluation supporting license amendment numbers Ra and 71 for NA-1&?, respectively, and dated Aucust ?5,1986, regardino the NA-1&? core uprate, considered the radiological consequences of accidents analyzed in the NA 1&? UrSAR (includino consideration of the current LPZ), and found them to remain boundino. Thus, no change to the LD7 as a result of the core uprate was reauired.
Resed on the above, the staff concludes that there continues to be reasonable assurance that appropriate measures can be taken on behalf of the population within the LPZ in the event of an accident and that the NRC conclusions as stated in the NA-l&? SFR, Section 2.1.3, remain unchanged as a result of the extended license period.
Ma.ior Population Centers: Maior population centers are discussed in Section 7.1.3 of the NA-l&? SER. The current nearest ma.ior population center, as defined in 10 CFR part 100 (containing more than 25,000 residentsi, is Fredericksburg, Vircinia, located 24 miles northeast of the site. Thus, the nearest population center remains the same as that identified in Section 2.1.3 of the Na-1&? SER and the nearest population center distance continues to be greater than one and one-third times the distance from the reactors to the outer boundarv of the LPZ.
Based on the Commonwealth of Virginia population estimates (October 1986),
Fredericksburg is expected to remain the nearest oopulation center throughout the extended license period for NA-1&2 and therefore the conclusions in Section 2.1.3 of the NA-1&2 SER remain unchanged.
2.
Effects Upon System and FouiDment The licensee's request for extension of the operatinn licenses is based on the fact that a 40-year service life was considered durinn the desian and construction of the plant. Althounh this does not mean that some components will not wear out during the plant lifetime, design features were incorporated which maximize the inspectability of structures, systems and equipment.
Surveillance and maintenance practices which were implemented in accordance with the ASME code and the facility Technical Specifications provide assurance that any unexpected degradation in plant eouipment will be identified and corrected.
1 The design of the reactor vessel and its internals considered the effects of 40 years of operation at full power and a comprehensive vessel material surveillance proaram is maintained in accordance with 10 CFR Part 50, Appendix H.
The sta##
has completed analyses related to the pressurized thermal shock (PTSI rule, 10 CFR 50.61, for both units which shows that the most critical weld, materials for both reactor vessels meet the criterion of 10 CFR 50.61 by a laroe margin throuah the end of the a0-year operating life.
in addition to these calculations, surveillance capsules placed inside the reactor vessels provide a means of monitoring the cumulative effects of power operation.
. Aging analvses have been performed for all safetv-related electrical equipment in accordance with 10 CFR 50.49, " Environmental Dualification of Electrical Eauipment Important to Safety for Nuclear Power Plants," identifving qualified lifetimes for this equipment. These lifetimes will be incorporated into plant eouipment maintenance and replacement practices to ensure that all safetv-related electrical equipment remains qualified and available to perform its safety function regardless of the overall ace of the plant.
3.
Findinos Based upon the above, we find that extension of the operatino licenses for NA-1A2 to allow a 40-vear service life is consistent with the safety analvses for NA-l&2 and that the commission's previous safety findinos are not chanced.
All issues associated with plant systems and eouipment, including aging and changes in fracture touchness properties of materials, have been addressed and are acceptable for 40 years of operation. The site continues to meet the guidelines of 10 CFR 100 Accordingly, we find the proposed change to the expiration dates of the NA-1A2 Facility Operating Licenses to be acceptable.
ENVIRONMENTAL CONSinFDATION A Notice of Issuance of an Environmental Assessment and Finding of No Sionificant Impact relatino to the proposed extension o# facility operatino license termination dates for the North Anna finit Nos. I and ? Was published in the Federal Reaister on December 24,1986 (51 FR '46737).
CONCLUSION We have concluded, based on the considerations discussed above, that Ili there is reasonable assurance that the health and safety of the public will not be endancered bv operation in the proposed manner, and (91 such activities will be conducted in compliance with the Commission's reculations, and the issuance of the amendrents will not be inimical to the common defense and security or to the health and safety of the public.
Date: December 30, 1986 l
Principal Contributor:
L. Engle
-w w
.