ML13253A159

Issuance of Amendments Regarding Atmospheric Relative Concentration Values for Use in Control Room Envelop Radiological Dose Analysis (TAC Nos. ME9716 and ME9717)

ML13253A159
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/23/2013
From:	Jason Paige Plant Licensing Branch II
To:	Capps S Duke Energy Carolinas
Paige Jason, NRR/DORL 415-5888
References
TAC ME9716, TAC ME9717
Download: ML13253A159 (16)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 23, 2013 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING ATMOSPHERIC RELATIVE CONCENTRATION VALUES FOR USE IN CONTROL ROOM ENVELOPE RADIOLOGICAL DOSE ANALVSIS (T AC NOS. ME9716 AND ME9717)

Dear Mr. Capps:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 271 to Renewed Facility Operating License NPF-9 and Amendment No. 251 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2 (McGuire). The amendments consist of changes to the Updated Final Safety Analysis Report (UFSAR) in response to your application dated September 25,2012, as supplemented by leUers dated June 12, and August 8,2013.

The amendments revise selected atmospheric relative concentration values for use in Control Room radiological dose analysis that were withdrawn during McGuire's request for full scope implementation of the Alternate Source Term (AST). McGuire received NRC approval for full scope implementation of AST on March 31, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090890627). The licensee will make the necessary changes to the UFSAR in accordance with Title 10 of the Code of Federal Regulations, Section 50.71(e}.

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

S. Capps -2 If you have any questions, please call me at 301-415-5888.

Sincerely, Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosures:

1. Amendment No. 271 to NPF-9

2. Amendment No. 251 to NPF-17

3. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 271 Renewed License No. I'JPF-9

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

A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility),

Renewed Facility Operating License No. NPF-9, filed by the Duke Energy Carolinas, LLC (the licensee), dated September 25,2012, as supplemented by letters dated June 12, and August 8, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 Oi) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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.

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2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-9 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 271, are hereby incorporated into this renewed operating 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 of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 7Zr;P~.

Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-9 and the Technical Specifications Date of Issuance: Septarber 23, 2013

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS. LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 251 Renewed License No. NPF-17

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

A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility),

Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated September 25,2012, as supplemented by letters dated June 12, and August 8, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 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.

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2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 251, are hereby incorporated into this renewed operating 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 of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-17 and the Technical Specifications Date of Issuance:SepteTi:a' 23, 2013

ATTACHMENT TO LICENSE AMENDMENT NO. 271 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AI\ID LICENSE AMENDMENT NO. 251 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License Pages License Pages NPF-9, page 3 NPF-9, page 3 I\IPF-17, page 3 I\IPF-17, page 3

.3 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducls and special nuclear materials as may be produced by the operation of McGuire Nuclear Station. Units 1 and 2, and; (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive. possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provIsions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1 ) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).

(2) Technical Sqecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 271, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Anat~is Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16,2002, describes certain future activities to be completed before the period of extended operation.

Duke shall complete these activities no later than June 12. 2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16,2002, described above, shall be included In the next scheduled update to the Updated Final Safety AnalysiS Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed License No. NPF-9 Amendment No~271

-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or speCial nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and.10 CFR Parts 30.40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2; and, (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to alt applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authoriZed to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment N0l251 are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the pertod of extended operation.

Duke shall complete these activities no later than March 3, 2023, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59. and otherwise complies with the requirements in that section.

Renewed License No. NPF-17 Amendment No. 251

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 271 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 251 TO RENEWED FACILITY OPERATING LICENSE NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370

1.0 INTRODUCTION

By application dated September 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12272A343), as supplemented by letters dated June 12, 2013 (ADAMS Accession No. ML13165A321), and August 8, 2013 (ADAMS Accession No. ML13233A320), Duke Energy Carolinas, LLC (Duke, the licensee), requested changes to the Updated Final Safety Analysis Report (UFSAR) for the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2). The supplements dated June 12, 2013 and August 8, 2013, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on February 5, 2013 (78 FR 8199).

The amendments revise selected atmospheric relative concentration values (N/Q) for use in Control Room radiological dose analysis that were withdrawn during McGuire's request for full scope implementation of the Alternate Source Term (AST). The licensee withdrew the release points due to the source-to-receptor distances being less than 10 meters and needing to be addressed on a case-by-case basis. McGuire received NRC approval for full scope implementation of AST on March 31,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090890627). The purpose of this amendment is for the NRC to review and approve the licensee's withdrawn N/Q values on a case-by-case basis. The licensee will make the necessary changes to the UFSAR in accordance with Title 10 of the Code of Federal Regulations, Section 50.71(e).

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2.0 BACKGROUND

By application dated March 20, 2008 (ADAMS Accession No. ML080930505), as supplemented by letters dated May 28,2008 (ADAMS Accession No. ML081560395), October 6,2008 (ADAMS Accession No. ML082830014), December 17,2008 (ADAMS Accession No. ML083590342),

February ,12,2009 (ADAMS Accession No. ML090540682), and March 25, 2009 (ADAMS Accession No. ML090860776), Duke requested full scope implementation for McGuire 1 and 2 of the AST radiological analysis methodology as allowed by Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.67, "Accident source term," for the Loss of Coolant Accident (LOCA) described in NRC Regulatory Guide (RG) 1.183, "Alternate Radiological Source Terms for Evaluating Design Basis Accidents [DBAs] at Nuclear Power Reactors."

During the staff's review of the licensee's AST application, Duke withdrew several release points from consideration for NRC review including pOints that were discovered to have a source-to-receptor distance of less than ten meters by letter dated February 12, 2009 (ADAMS Accession No. ML090540682). Section C.3.4 of RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," states that ARCON96 computer code should not be used to assess NJQ values at a distance less than about ten meters without a case-by-case review from the NRC. McGuire received NRC approval for full scope implementation of AST on March 31, 2009 (ADAMS Accession No. ML090890627), and the removal from consideration for NRC review of these release points is documented in Section 3.2.2 of the NRC's Safety Evaluation.

The purpose of the September 25, 2012, license amendment request (LAR) was for the licensee to submit selected points for NRC review and provide its sensitivity analYSis for the points with a source-to-receptor distance of less than ten meters. In addition, the September 25, 2012, LAR submitted release points for NRC review and approval that were consistent with RG 1.194.

2.0 REGULATORY EVALUATION

The NRC staff evaluated the proposed control room NJQ values using guidance provided in RG 1.23, "Meteorological Monitoring Programs for Nuclear Power Plants," and RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants." RG 1.23 provides licensees and applicants with guidance concerning criteria for an onsite meteorological measurements program that the NRC staff considers acceptable for the collection of basic meteorological data needed to support plant licensing and operation. RG 1.194 provides guidance on determining atmospheric relative concentration NJQ values in support of deSign basis control room radiological habitability assessments at nuclear power plants for use in support of applications for licenses and LARs.

3.0 TECHNICAL EVALUATION

3.1 Atmospheric Relative Concentrations Estimates (NJQ)

By letter dated February 12, 2009, the licensee withdrew several release points from consideration during the McGuire full scope AST review, including points that were discovered to have a source-to-receptor distance of less than 10 meters. The licensee re-evaluated control room N/Q values for several release points at McGuire and submitted the proposed

- 3 September 25,2012, LAR for NRC staff review. These release points include: a main steamline break from a break in the yard (MSLB y) and main steamline break (MSLB) inside the doghouse.

3.1.1 Meteorological Data The licensee used hourly onsite meteorological data measured from 2001 through 2005 that were provided for a prior licensing action by letter dated December 17, 2008 (ADAMS Accession No. ML083590342). The evaluation of the data is discussed in the NRC staff SE associated with McGuire, Units 1 and 2, Amendments 251 and 231, respectively, dated March 31,2009 (ADAMS Accession No. ML090890627). The NRC staff reviewed the overall quality of the data and found it to be consistent with the guidance outlined in RG 1.23. Therefore, the NRC staff determined that the data are acceptable for use in licensing actions.

3.1.2 Control Room Atmospheric Relative Concentrations The licensee provided the inputs and assumptions used to generate the control room N./Q values for the proposed release points in the September 25,2012, LAR. In response to NRC staff requests for additional information dated May 6, 2013 (ADAMS Accession No. ML13122A219),

and August 1,2013 (ADAMS Accession No. ML13218A305), the licensee provided clarifications and revised tables for the inputs and assumptions in the June 12, and August 8, 2013, supplements to the LAR.

3.1.2.1 MSLB from a Break in the Yard The inboard main steamline source in the yard at McGuire is within 10 meters of the control room air intake receptor at its closest point (7.5 meters). The outboard main stearnline source in the yard is also within 10 meters of the control room air intake receptor (9.5 meters) at its closest pOint. In Section 2.1.1 of the LAR, the licensee notes that Section C.3.4 of RG 1.194 states that ARCON96 should not be used for source-to-receptor pairs separated by distances less than about 10 meters. This guidance also specifies that such situations should be analyzed on a case-by-case basis.

To support the LAR, the licensee performed a sensitivity analysis for the inboard and outboard steam lines for the MSLBy release points for Units 1 and 2 to evaluate the source-to-receptor distance limitations of ARCON96. For the inboard steam line, in Section 3.1.2 of the LAR, the licensee states that hypothetical release points were assumed, extending from the intake toward the point representing the minimum distance to the steam line and beyond. This sensitivity analysis included the site-specific layout and other parameters relating only to the MSLBy accident at McGuire. The licensee states that results for Unit 1 were reasonable and well-behaved for source-to-receptor distances greater than 2.3 meters. For distances less than or equal to 2.3 meters, attempts to use ARCON96 produced error messages. The 2.3 meter distance is less than any source-to-receptor distance in the proposed LAR. The NRC staff found this to be acceptable due to the inboard main steam line source-to-receptor's closest point being 7.5 meters or greater than 2.3 meters.

The licensee performed similar studies for the outboard steamline. The licensee states that for the outboard steamline a height difference of 4.5 meters between the source and the intake allows ARCON96 to calculate well-behaved results for all postulated horizontal distances

-4 between 1 and 20 meters without producing error messages. The sensitivity analysis also examined points along the steamlines in the general area of the intake. The licensee states that this ensured that the minimum distance case is truly the most limiting release point, since the wind variability coupled with the source-to-receptor angles could result in a release point farther away being the limiting dispersion factor. The licensee stated that analysis for Unit 2 exhibited the same behavior which was expected due to plant symmetry. The NRC found this to be acceptable due to the outboard main steam line source-to-receptor minimum distance case being the most limiting.

After performing the sensitivity study to show that the use of ARCON96 was appropriate for the proposed MSLBy source-to-receptor pairs, the licensee made estimates for the control room KIa values. In Section 2.1.1 of the LAR, the licensee states that the MSLBy sources were modeled as ground level releases by conservatively setting the vertical velocities to zero meters/second (m/s) in ARCON96, in spite of the release being thermally buoyant relative to the surrounding atmosphere. The licensee noted that an additional conservatism included the use of a pOint source to represent the break in the main steamline. The NRC staff reviewed the licensee's ARCON96 dispersion modeling results and based on the staff's confirmatory calculations using ARCON96, concluded that the licensee's estimated control room N./O values to be acceptable.

See Table 3.1 for the licensee's Control Room KIa values for a release from the main steamline.

Table 3.1 McGuire Control Room KIa Values Release from Main Steam line Same Unit Inboard Same Unit Outboard Cross Unit Inboard Time Period KIa (81m 3) KIa (81m 3) KIa (s/m3) o to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 9.10 x 10.2 4.63 X 10.2 5.81 X 10-4 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8.41 x 10.2 3.42 X 10-2 4.08 x 10-4 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.69 x 10.2 1.25 X 10.2 1.61 X 10.4 1 to 4 days 2.76 x 10-2 9.66 X 10.3 1.24 X 10-4 4 to 30 days 2.09 x 10.2 7.45 X 10.3 9.49 X 10.5 3.1.2.2 MSLB Inside the Doghouse The MSLB inside the doghouse release points were withdrawn from consideration for review by letter dated February 12, 2009. The licensee states in its September 25,2012, application that the doghouse release points could be assumed to be an area source but now have been conservatively modeled as a line source in conformance with RG 1.194. The NRC staff notes that the source-to-receptor distances for the inboard and outboard doghouse release points are listed as more than 10 meters and thus are consistent with the guidance outlined in RG 1.194 for the use of ARCON96. Therefore, no sensitivity study was done for these release points. In Section 2.2 of the LAR, the licensee notes that the doghouses at McGuire are the large reinforced structures directly attached to containment which house the main steam isolation valves and other equipment. There are two doghouses per each unit. A steam release could occur inside the doghouse as a result of a failure in the secondary system piping. The release pathway from the

-5 doghouse for any effluent would be from a series of louvers near the top of the doghouse. These louvers are located on the three sides of each doghouse. The licensee states that although these openings could be assumed to be an area source, they have been conservatively modeled as a line source which was created by assuming a vertical diffusion coefficient of zero and calculating the horizontal diffusion coefficient as the width of the total opening divided by six. The licensee states that per RG 1.194 Section 3.2.4.5, the release is assumed to originate from a line projected perpendicular to the line of sight between the receptor and the building surface closest to the control room intake. The licensee notes that the cross unit release 'H./Q values are derived based on the doghouse releases modeled as point sources. Releases from within the doghouses could place both intake pairs within the 90 degree window centered about the line drawn between the source and closest receptor. The licensee states that the entire release inside the doghouse was conservatively assumed to preferentially flow through only the louvers on the side adjacent to the control room intakes. Similar to the MSLBy, the staff reviewed the licensee's ARCON96 dispersion modeling results and based on the staff's confirmatory calculations using ARCON96, concluded that the licensee's estimated control room 'H./Q values to be acceptable. See Table 3.2 for the licensee's Control Room 'H./Q values for a release from the doghouse.

Table 3.2 McGuire Control Room 'H./Q Values Release from Doghouse Same Unit Inboard Same Unit Outboard Cross Unit Outboard Time Period

'H./Q (s/m3) 'H./Q (s/m3) 'H./Q (s/m 3) o to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4.61 x 10-3 i 1.70 X 10-2 6.54 X 10-4 i

4 I 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.87 x 10-3 1.62 X 10-2 4.62 X 10- i

,~'-_. .._ _. - - - - J

~ 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.60 x 10-3 7.61 X 10-3 1.75 X 10-4 i I 1 to 4 days 1.17 X 10-3 5.53 X 10-3 1.36 X 10-4 I

4 to 30 days 8.53 x 10-4 4.20 X 10-3 1.05 X 10-4 I i

3.2 Summary The licensee used meteorological data that had been evaluated by the NRC staff for a previous licensing action and were found to be acceptable for use in licensing actions based on guidance in RG 1.23. The NRC staff reviewed the licensee's sensitivity analysis for using ARCON96 for source-to-receptor distances less than about 10 meters for the site-specific layout and other parameters relating to the MSLBy accident at McGuire. In addition, Figure 1 in the licensee's September 25,2012, LAR shows an expected trend for H..IQ values as the distance to intake from hypothetical release point varies. After review of the sensitivity analysis and Figure 1 in the licensee's LAR, the staff found the assumptions and methods used to be reasonable. Regarding the MSLB inside the doghouse, the source-to-receptor distances for the inboard and outboard doghouse release points are more than 10 meters and thus consistent with the guidance outlined in RG 1.194. The NRC staff reviewed the licensee's inputs and assumptions used in calculations for the control room 'H./Q value assessment for the proposed release points and found them to be consistent with the guidance of RG 1.194 and the associated site configuration drawings.

Therefore, the NRC staff found the inputs and assumptions to be acceptable. As stated above,

- 6 the NRC staff also reviewed the licensee's ARCON96 dispersion modeling results and based on the staff's confirmatory calculations using ARCON96, concluded that the licensee's estimated control room H./Q values to be acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the North Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (78 FR 8199). Accordingly, the amendments 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 the amendments.

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) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: J. White Date: ~pteIDer 23, 2013

S. Capps -2 If you have any questions, please call me at 301-415-5888.

Sincerely, IRA by RGuzman forI Jason C. Paige, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosures:

1. Amendment No. 271 to NPF-9

2. Amendment No. 251 to NPF-17

3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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