ML20214M096

Forwards Response to NRC 861118 Request for Addl Info Re 851216 Application Extending OLs to Full 40-yr Term. Responses to NRC Questions & Data on Exposure of Plant Workers Encl

ML20214M096
Person / Time
Site:	McGuire, Mcguire
Issue date:	11/24/1986
From:	Tucker H DUKE POWER CO.
To:	Harold Denton, Youngblood B Office of Nuclear Reactor Regulation
References
TAC-60427, TAC-60428, NUDOCS 8612030276
Download: ML20214M096 (21)

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DUKE POWER GOMPm P.O. HOX 33180 CHARLOTTE. N.C. 28242 IIALH. TUCKER reternown vu.s russament (704) 373-4M1 pttLEAR PRODUCTION Novnber 24, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: B.J. Youngblood, Director PWR Project Directorate #4

Subject:

McGuire Nuclear Station Docket Nos. 50-369, -370 Supplement to Proposed License Amendment - 40 Year Life

Dear Mr. Denton:

By letter dated December 16, 1985, Duke Power proposed a License Amendment to extend the McGuire Operating Licenses to full 40-year terms. In support of this request, and in response to an NRC request for information dated November 18, 1986, the attached supplemental information is provided.

We request timely NRC review of this information and approval of the license amendment for 40 years of operating life.

Please contact us if you require any additional information.

Very truly yours,

. t' - A

@u Hal B. Tucker RLG/126/j gm Attachments xc: Dr. J. Nelson Grace Mr. W.T. Orders Regional Administrator NRC Resident Inspector U.S. Nuclear Regulatory Commission McGuire Nuclear Station Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

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8612030276 DR 861124  %

ADOCK 05000369 PDR

1 DUKE POWER COMPANY McGUIRE NUCLEAR STATION Response to Request for Additional Information Regarding License Extension The NRC staff has reviewed the Environmental Assessment provided by licensee's letter of December 16, 1985, which request 40-year term licenses beginning with issuance of the operating licenses rather than the construction permits. We require the following additional information pursuant to 10 CFR 51.30:

1. Discuss the need for the proposed extension.

Duke Response The granting of the proposed license amendments would allow Duke to operate McGuire Nuclear Station, Units 1 and 2, for an additional 8 1/2 and 10 years, respectively, beyond the currently approved dates.

Since the capacity is needed, this would allow Duke to continue operation of the facility for the full useful life of the plant to provide electrical energy to-our service customers, without having to incur additional capital costs. As detailed in the discussions that follow, Duke considers the extension of the operating licenses to the 40 year term to be the most attractive option available.

2. Provide a discussion of all changes in plant design or operation that would significantly affect the environmental impacts evaluated in the Environmental Report / Operating License Stage (ER) and the Final Environmental Statement (FES) associated with the requested change.

a. Include population projections within less than 50-miles of the Station (e.g. , 5 miles and 10 miles) . Projections based on the 1980 census for the area within 5 miles of McGuire appear to be higher than previous projections in the FES and FSAR which used 1970 census information.

Discuss this change with respect to the requirements of 10 CFR 100, including any changes in the previous characterization of the site boundary, nearest population center and low population zone. Justify the requested change in view of the updated population projections.

Duke Response Population Distributions Previous population data referenced in the McGuire FES and FSAR and updated population data based on 1980 census data and on projections made by the United States Department of Commerce, Bureau of Economic Analysis (Reference 1 and 2) are summarized as follows:

Page 2-Population Projections Within 5-Mile Radius of McGuire Nuclear Station Population Population Annual Year Total Average Growth (%/Yr)3 2015 (1970 census)f 6,813 1.51 2020 (1970 census) 7,399 1.53 2020 (1980 census) 10,739 2.29 2030 (1980 census) 11,103 1.96 As reported in McGuire FES.

From McGuire FSAR Table 2.1.3-2 3

Calculated based on 1970 population of 3465 within the 0-5 mile radius of McGuire as referenced in the McGuire FES.

Population Projections Within 10-Mile Radius of McGuire Nuclear Station Population Population Annual Year Total Average Growth (%/Yr)3 a

2015 (1970 census)f 83,095 1.67 2020 (1970 census) 88,721 1.64 2020 (1980 census) 71,252 1.19 2030 (1980 census) 73,982 1.06 As reported in McGuire FES.

From McGuire FSAR Table 2.1.3-1 Calculated based on 1970 population of 39,362 within the 0-10 mile radius of McGuire as referenced in the McGuire FES.

Population Projections Within 50-Mile Radius of McGuire Nuclear Station Population Population Annual l

Year Total Average Growth (%/Yr)3 2015 (1970 census)f 2.651 Million 1.46 2020 (1970 census) 2.818 Million 1.44 2020 (1980 census) 2.188 Million 0.925 2030 (1980 census) 2.279 Million 0.839 As reported in McGuire FES.

From McGuire FSAR Table 2.1.3-2 3

Calculated based on 1970 population of 1.38 Million within the 50 mile i radius of McGuire as referenced in the McGuire FES. l

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Page 3 Exclusion Area Impacts The exclusion area surrounding the reactor in which Duke Power Company, through ownership of the property and through agreements with and cooperation of the Mecklenburg County Police and North Carolina Highway Patrol and Lake Norman Marine Commission, can exercise adequate control, including exclusion or removal of personnel and property, remains unchanged from that described in FSAR Section 2.1.2.1.

Nearest Population Center The nearest population center distance, defined as the distance from the reactor to the nearest boundary of a densely populated center having more than 25,000 residents, continues to be greater than one and one-third the distance from the reactor to the outer boundary of the LPZ. The nearest population center continues to be Charlotte, NC and is projected to remain so throughout the proposed extended license period for McGuire. Therefore, the nearest population center remains the same as that described in McGuire FSAR Section 2.1.3.5. Additionally, updated population projections for 2020 for all the sectors which include Charlotte (i.e., S, SSE, SE @ 10 to 20 miles from the McGuire Site) and all the sectors just on the McGuire side of Charlotte (i.e., S, SSE SE @ 5 to 10 miles from the McGuire Site) are lower than those projected based on 1970 census data and presented in McGuire FSAR Figures 2.1.3-8 and 2.1.3-14.

Low Population Zone The McGuire LPZ extends cut to a 5.5 mile radius from the station. Estimates for the populations within a 5-mile radius and a 10-mile radius of McGuire were developed based on information previously presented in the McGuire FES and FSAR and on 1980 census data. These estimates are summarized above.

The increase in population within 5 miles of the station is primarily due to residential lakeshore development, upgrading of secondary roads, and the completion of Interstate 77. The land useage in the local area remains rural. The conclusion reached in FSAR Section 2.1.3.3 and the FES, that McGuire meets the requirements of 10CFR100 remains unchanged. Although there has been higher projected growth than previous projections in the FES and FSAR, the upgrading of secondary roads and the completion of Interstate 77 attendant with the population growth in the area assures that there continues to be a reasonable probability that appropriate measures can be taken on behalf of the population within the LPZ in the vent of a serious accident.

Radiological Impact on Man from Routine Operation The effect updated population projections would have on population doses presented in the FES would likely be favorable in terms of total population dose from liquid and gaseous effluents.

Page 4 The total population doses presented in FES Table 5.14 were calculated based on population within 50 miles of McGuire for liquid dose pathways, and the entire U.S. population for gaseous dose pathways. Considering the updated 50 mile radius population for 2020 is approximately 17 percent lower than projected for 2015 in the FES, liquid pathway population dose estimates would be lower based on updated population data. Although the population projections within the 5 miles radius of McGuire have increased from those presented in the FES, it is unlikely that this relatively small population would significantly affect the gaseous pathway doses presented in the FES Table 5.14. Therefore, the total population doses presented in the FES would likely be lower if updated pcpulation projections were considered.

Justification for Proposed Change Based upon the updated, 1980 census basis population estimates, the current Exclusion Area Boundary, Low Population Zone and nearest population center distances would likely be unchanged from those used for licensing the McGuire units. Therefore, the conclusion reached in the staff's Safety Evaluation in 1978, that McGuire meets the requirements of 10CFR100, remains unchanged.

Additionally, population doses presented in the staff's FES in 1976 would likely be lower with the consideration of updated population projections.

Therefore, the conclusion reached by the staff and presented in the FES, that the McGuire Nuclear Station will contribute a small fraction of the population dose that persons living the the U.S. normally receive from natural background, remains unchanged.

References

1. U.S. Department of Commerce, Bureau of Economic Analysis, Projection, Economic Activity in North Carolina, Series E Projection, April 1986.

2. U.S. Department of Commerce, Bureau of Economic Analysis, Projection, Economic Activity in South Carolina, Series E Projection, April 1986.

2.b. Discuss any change in public risks from reactor accidents associated with the requested change.

Duke Response The McGuire FES includes an assessment of the public risks from reactor accidents per year of operation. In all cases, the estimated reactor accident risks of early and latent cancer fatality per year of operation have been small compared to the background accident and cancer fatality risks to which the public is exposed, and did not increase with longer periods of operation.

1 l

1

Page 5 The proposed license amendment in no way affects the probability or consequences of an accident. The probability or consequence of an accident is determined by the design and operation of plant systems. Existing programs are unaffected by this change and it is these programs that tend to affect the probability and consequences of an accident. These programs remain in effect throughout the duration of the operating license, whatever duration it is. There exists an integral exposure to risk by virtue of the additional years of plant operation.

However, this additional exposure to risk is not significant, by virtue of above the operational programs continuing in effect. Thus, this proposed change does not involve a significant increase in the public risks from reactor accidents.

2c. Discuss any changes in radiological environmental effects associated with normal operation, including:

1) Impacts to the general public. Discuss the expected annual of fsite doses to and during the additional years of operation, projected on the bnsis of actual effluent releases to date. Include a discussion of the ingestion dose due to increase buildup of long life radionuclides in the soil.

Duke Response Dose commitments to the human population residing around nuclear power reactors have been calculated to assess the impact on people from radioactive material released from these reactors during normal operation. The annual dose commitment is calculated to be the dose that would be received over a 50-year period following the intake of radioactivity for one year under the conditions that would exist 15 years after the plant began operation.

The 15 year period is chosen as representing the midpoint of plant operation and is incorporated into the dose models by allowing for buildup of long life radionuclides in the soil. It affects the estimated doses only for radionuclides, that have half-lives greater than a few years, ingested by humans. For a plant licensed for 40 years, increasing the buildup period from 15 to 20 years would increase the dose from long life radionuclides via the ingestion pathways by less than one-third. It would have much less effect on dose from shorter life radionuclides.

In Appendix D of the McGuire Safety Evaluation Report dated March 1978, the NRC provided an assessment of McGuire with respect to the design objectives of Appendix I of 10CFR50.

Table 4 of Appendix D indicates that the estimated doses via the ingestion pathways are well below the regulatory design objectives. For example, the ingestion dose to the thyroid from Units 1 and 2 is .58 mrem /yr/ site compared to a design objective of 5 mrem /yr/ site.

Duke calculates annual offsite doses based upon actual effluent releases during each year of operation. These calculations are based upon methodology and parameters in the McGuire "Offsite Dose Calculation Manual". The results for 1985 and through July 1986 are provided in the attached table. These results are well within the Appendix I limits. The doses for earlier years of operation are comparable in that they, too, are far below Appendix I dose limits. Duke expects the annual doses calculated to date to remain typical of plant operations through the year 2023.

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Page 6 Thus, an increase of even as much as one-third in these pathways would remain well below the Appendix I to 10 CFR Part 50 guidelines and would not be significant.

The McGuire Technical Specifications presently include radiological ef fluent Technical Specifications that are in compliance with NRC requirements regarding ALARA.

RADWASTE

SUMMARY

McGUIRE McGUIRE 7/31/86 1985 LIQUID RADWASTE EFFLUENT-TOTAL BODY DOSE YEAR TO DATE DOSE (MREM) 1.93E-01 1.76E-01 ANNUAL LIMIT (BASED ON 3 MREM / UNIT) 6 6

% OF ANNUAL LIMIT 3.2 2.9 LIQUID RADWASTE EFFLUENT-ORGAN DOSE YEAR TO DATE DOSE (MREM) 2.47E-01 2.24E-01 ANNUAL LIMIT (BASED ON 10 MREM / UNIT) 20 20

% OF ANNUAL LIMIT 1.2 1.1 GASEOUS RADWASTE EFFLUENT-GAMMA DOSE YEAR TO DATE DOSE (MRAD) 1.53E+00 4.24E+00 ANNUAL LIMIT (BASED ON 10 MRAD / UNIT) 20 20

% OF ANNUAL LIMIT 7.7 21.2 GASEOUS RADWASTE EFFLUENT-BETA DOSE YEAR TO DATE DOSE (MRAD) 3.82E+00 1.00E+01 ANNUAL LIMIT (BASED ON 20 MRAD / UNIT) 40 40

% OF ANNUAL LIMIT 9.6 25.0 GASEOUS RADWASTE EFFLUENT-ORGAN DOSE YEAR TO DATE DOSE (MREM) 4.35E-01 7.87E+00 ANNUAL LIMIT (BASED ON 15 MREM / UNIT) 30 30

% OF ANNUAL LIMIT 1.45 26.2 1

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Page 7 2.c.2) Annual and total occupational exposures during the additional years of operation, and bases for these projections.

Duke Response The proposed additional years of reactor operation is not expected to increase annual occupational doses to workers or doses to the general public.

With regard to normal plant operation, Duke Power Company will continue to comply with NRC guidance and requirements for keeping radiation exposures "As Low As Is Reasonably Achievable" (ALARA) for occupational exposures and for radioactivity in effluents, (hence doses to the public).

The following table presents past annual person-rem exposure for McGuire Nuclear Station. (Details are provided in the attached cables.)

McGUIRE NUCLEAR STATION ANNUAL PERSON-REM YEAR PERSON-REM COMMENT 1981 25.38 Initial Criticality (IC) 8/8/81 (Unit 1) 1982 169.08 Unit 1 Only 1983 563.236 Unit 2 IC 5/16/83 S/G MODS; Unit 1 1st RF0 1984 587.595 Two Units Operating 1985 771.07 Two Refuelings Rerack Unit 1, 2 Currently operating PWRs average more than 700 person-rems per Unit annually, with particular plants experiencing an average lifetime annual dose as high as 1300 person-rems. These dose averages are based on widely varying yearly doses at PWR.

Duke does not expect any increase in the average annual station doses for the

, years 2013 to 2023. It is likely also that decommissioning doses will be less, due to improved technology.

Duke estimates that an average annual dose of 700 person-rem for both units will be incurred for each additional year of operation. The total occupational dose expected over the period of the operating license extension is 7000 person-rem, and is based on 10 additional years of operation and 15 additional refuelings during this period with no major unanticipated maintenance.

Duke Power Company will utilize criteria established in its current formal ALARA program in addition to any improvements that are made throughout the duration of the operating license. The program is constantly evolving as techniques are

l e Page 8 I

) perfected, technology is improved, and the work force becomes more educated in j radiation protection practices. Duke can only speculate on specific future ALARA i measures, but we anticipate items such as robotics, remote surveillance, remote

! tooling, decontamination, improved computer resources, etc. to be major factors in

7. further achieving ALARA doses.

1

! As a supplement to the corporate ALARA program, for which the Nuclear Production l Department has responsibility, the Design Engineering Department has developed an l ALARA program applicable to the design process. This program consists of periodic j training, the Design Engineering Department ALARA Guide, and peer review of l'

designs. Following initial design ALARA training, refresher training is required for appropriate Design Engineering personnel every two years. State-of-the-art ALARA design techniques, emphasizing crud and modification dcse reductions, are l introduced at the training sessions. In addition, the ALARA Guide is distributed i to appropriate personnel for use as a reference during the design process. This

, guide is revised to reflect new design ALARA techniques and concepts. Finally, i designs are subject to review by personnel responsible for ALARA training and guide development. Also, a methodology that considers personnel dose received during modification implementation at the design stage, is being evaluated .

'i The Design Engineering Department's ALARA program has been audited both internally and externally (by INPO) with favorable results.

Planned plant modifications that will contribute to reduced occupational exposure include removal of the Upper Head Injection System and RTD Bypass manifolds at each unit.

In addition, Duke has invested considerable resources to prolong the life of the 4

McGuire steam generators. These include development of technical specification revisions to the plugging criteria for tube defects located well within the tube

sheet region and implementation of a shot-peening to reduce stresses on the j

primary water surface of the tubes. These efforts are expected to result in reduced person-rem exposure over the remainder of plant life.

McGuire is presently shipping about 10,000 f3 t of solid radwaste per unit per

! year, with year to year variations based on duration of outages. This volume is l expected to remain constant at about the present level for the life of the plant.

j Spent fuel will be stored in the reracked spent fuel pool (previously evaluated by the staff for radiological environmental consequences) in lieu of shipment offsite as stated in the FES. Any further expansion of on-site spent fuel storage

, capacity will be further evaluated for radiological environmental effects by the

] NRC staff.

]

l The FES evaluated the annual population doses resulting from plant operation and

, concluded that such doses are a small fraction of the total population dose that l persons living in the U.S. normally receive from natural background. The attached j projected annual occupational doses to workers during the proposed additional

years of operation remain a small fraction of the dose to the total population.

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Page 9 2.c.3) Impacts on the Uranium fuel cycle.

Duke Response The impacts of the uranium fuel cycle as considered for the FES were originally.

based on 30 years of operation of a model light water reactor (LWR). The fuel requirements for the model LWR were assumed to be one initial core load and 29 annual refuelings (approximately 1/3 core per refueling). In considering the annual fuel requirement for 40 years for the model LWR, fuel use is averaged out over a 40-year operating life (1 initial core and 39 refuelings of approximately 1/3 core) and results in a slight reduction compared to the annual fuel requirement averaged for a 30-year operating life. The net result is an

, approximately 1.5% reduction in the annual fuel requirements for the model LWR, due to averaging out of the initial core load over 40 years, instead of 30 years.

This small reduction in fuel requirements would not ' lead to significant changes in the annual impacts of the uranium fuel cycle.

In addition, Duke as examined actual plant performance. For plant operation i

through 1986, McGuire 1 has had one initial core and three reloads; McGuire 2 has had one initial core and two reloads. Duke expects 23 more refuelings (based on 14 month fuel cycle length) between now and 2013 (the expiration of the present operating licenses). This results in approximately 895 MTU required for Unit 1 (based on an initial core of 89 MTU and 31 MTU per reload) and 864 MTU for Unit 2.

Duke expects seven additional refuelings over the extended plant life of McGuire Unit 1 (approximately 8 years, 3 months) and eight additional refuelings over the

extended plant life of Unit 2 (approximately 10 years) at a typical refueling i

frequency of once per 14 months. This results in approximately 217 MTU additional

) required for Unit 1 and 248 MTU for Unit 2.

Thus, the total expected demand for uranium for each McGuire unit over the 40-year life is approximately 1112 MTU. This amount is about 5% over that assumed in the

! FES. This is not a significant environmental impact when compared to that created j by alternative forms of energy generation.

Duke has been in the process of converting from Westinghouse Standard Design Fuel to Optimized Fuel Assemblies (OFA) on both McGuire units. This transaction is complete on Unit 1 and has one more cycle to complete on Unit 2. Such changes have been previously evaluated by the staff to have no significant environmental impact.

1 Duke considers that there would net be any changes to the FES that would be necessary in order to consider 40 years of operation.

1

3. Discuss alternative courses of action for providing the equivalent electric

! energy that will result from the proposed license extension. Include in your discussion the "no action" alternative.

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Page 10 Duke Response The principal alternative to issuance of the proposed license extensions would be to deny the applications. This alternative is, in effect, the same as the "no-action" alternative. In either case, McGuire Nuclear Station, Units 1 and 2 would shutdown upon expiration of the present operating licenses at midnight on February 28, 2013.

Alternative means for providing equivalent electric energy would include construction of a new facility, either nuclear, fossil or some other form of power generation or purchase of replacement power. In either case, the environmental impact would be greater than that caused by extension of the present operating l

licenses of McGuire. This is due to the environmental impact associated with the construction of any generation facility.

4. Discuss the effect of the proposed license extension on the cost-benefit analysis in the McGuire FES.

Duke Response The cost-benefit analysis in the McGuire FES included a comparison of various options for producing an equivalent electrical power capacity. Even considering significant changes in the economics of the alternatives, operation of McGuire Nuclear Station Unit 1 for an additional 81/2 years and Unit 2 for an additional 10 years would only require incremental yearly costs. These costs would be substantially less than the purchase of replacement power or the installation of new electrical generating capacity. Moreover, the overall cost per year of the facility would decrease since the large initial capital outlay would be averaged over a greater number of years. In summary, the cost / benefit advantage of McGuire Nuclear Station, compared to alternative electrical power generating capacity, improves with the extended plant lifetime.

5. Identify any use of resources associated with the proposed request not previously considered in connection with the McGuire FES or its addendum.

Duke Response This action does not involve the use of resources not previously considered in connection with the " Final Environmental Statement Relating to Operation of William B. McGuire Nuclear Station Units 1 and 2" dated April 1976 or its addendum dated January 1981.

I)UEE POWER C0!!PA!1Y - 11CGulRE tiUCLEAR STATION ,

TA!!UI.ATION OF tilf!!BER OF PERS0!i!3EL A!Jil PERS0tl-Rett IlY WORK AtID J0lt FUt4CTION FOR 1981 .

11Ut!BER OF PERS0!!!1EL (>100 MHEM) TOTAL PERSON-REM (>100 ffREM)

UORK L JOB FUtiCTION Station Utility Contract Workers Station Utility

• Contract Workers Employees Employees and Ottiers Employees Employees and Ottiers REACTOR OPERATIOt3S & SURVEILLANCE Main:crance Personnel 30 65 30 3.372 6.168 3.615 Operating Personnel 5 0 0 .745 .000 .000 llealth Physics Personnel 9 3 7 .990 .135 .825 Engineering Personnel 2 5 1 .210 .455 .150 ROUTitJE flAlt3TE!1A!!CE ttiintenance Personnel 29 60 21 1.370 4.335 .900 operating Personnel 3 0 0 .025 .000 .000 IIcaltli Physics Personnel 10 2 5 .375 .090 .500 Engineering Personnel 1 5 0 .055 .415 .000 I!1SERU!CE I!1SPECTIO!1 Maintenance Personnel 0 3 0 .000 .955 .000 llealth Physics Personnel 1 0 1 .020 .000 .245 SPECI AL !!AltlTEllA!!CE ttsintenance Personnel 18 42 2 1.740 2.640 .000 operating Personnel 1 0 0 .010 .000 .000 llealth Physics Personnel 4 2 4 .070 .030 .220 Engineering Personnel 0 3 0 .000 .090 .000 UASTE PROCESS!!IC ,

itsintenance Personnel 7 10 5 .040 .170 .015 operating Personnul 2 0 0 .070 .000 .000 Health Physica Personnel 8 0 3 .060 .000 .015

DUKE POWER C0t!PAtIY - itCGulltE TJUCLEAR STATIO!1 TABUllTInti 0F F3Ut!BER OF PERS0!1tJEL ARID PERS0ti-Rett BY WORK A!!D JOB FUt3CTIOli FOR 1981 (00tJTIllUED) 11 UMBER OF PERS0!1tlEL (>100 ftREtt) TOTAL PERS0!i-REM (>100 HREM)

WORK & JOB FUNCTIOff Station Utility Contract Workers Station Utility Contract Workers Employees Employees and Others Employees Employees and Others REFUELI!!G tiaintenance Personnel 1 4 0 .040 .160 .000 llealth Physics Personnel 1 3 1 .080 .140 .055

'10TAL tt.iintenance Personnel 30 65 30 5.027 11.223 4.530 Operating Personne1 5 0 0 .850 .000 000 lie.alth Physics Personnel 9 0 7 1.370 .095 .910 1:ngineering Personnel 2 5 1 .265 .960 .150 GRA!1D TOTAL 46 70 38 7.512 12.278 5.590 f f. b

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!* ......T : O n t~57

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!. CRIMO TOTAL. .. ............

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08/29/06 ..

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