ML13186A197

Independent Spent Fuel Storage Installations - Issuance of Amendments for Changes to the Emergency Action Level Revisions

ML13186A197
Person / Time
Site:	Surry, North Anna
Issue date:	09/25/2013
From:	Evans G, V Sreenivas Plant Licensing Branch II
To:	Heacock D Virginia Electric & Power Co (VEPCO)
Sreenivas V, 415-2597
References
TAC ME9753, TAC ME9754, TAC ME9755, TAC ME9756
Download: ML13186A197 (30)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 September 25, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

NORTH ANNA POWER STATION, UNITS 1 AND 2 (NAPS), AND SURRY POWER STATION, UNITS 1 AND 2 (SURRY) -ISSUANCE OF AMENDMENTS FOR CHANGES TO THE EMERGENCY ACTION LEVEL REVISIONS (TAC NOS.

ME9753, ME9754, ME9755, AND ME9756)

Dear Mr. Heacock:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 270 and 252 to Renewed Facility Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station, Units 1 and 2, and Amendment Nos. 280 and 280 to Renewed Facility Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station, Units 1 and 2. This amendment is in response to your application dated September 27, 2012, for the proposed changes to the Emergency Action Level (EAL).

The amendments authorize the addition of a15-minute threshold for reactor coolant system leaks, based on NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, " 'Use of NEI 99-01, Methodoiogy for Development of Emergency Action Levels,' Revision 4, Dated January 2003,"

dated December 12, 2005.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

. V. Sreenivas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338,50-339,50-280, and 50-281

Enclosures:

1. Amendment No. 270 to NPF-4

2. Amendment No. 252 to NPF-7

3. Amendment No. 280 to DPR-32

4. Amendment No. 280 to DPR-37

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50~338 NORTH ANNA POWER STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 270 Renewed License No. NPF~4

1.

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

A.

The application for amendment by Virginia Electric and Power Company et aI., (the licensee) dated September 27,2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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; 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.

- 2

2.

Accordingly, the license is amended by changes to paragraph 2.C (2) of Renewed Facility Operating License No. NPF-4, as indicated in the attachment to this license amendment, and is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 270, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Further Renewed Facility Operating License No. NPF-4 is hereby amended to authorize changes to the North Anna Emergency Action Level (EAL) to add 15-minutes threshold for reactor coolant system leaks, based on NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, tI 'Use of NEI 99-01, Methodology for Development of Emergency Action Levels,' Revision 4, Dated January 2003," dated December 12, 2005. That is, an EAL is altered such that classification of the event could be different than the site-specific EAL as approved by the NRC Safety Evaluation Report dated February 4, 2008.

4.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

EGULA TORY COMMISSION Eric J. L ds, Director Office f Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-4 and the Technical Specifications Date of Issuance: September 25, 2013

ATTACHMENT TO LICENSE AMENDMENT NO. 270 RENEWED FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 AND TO LICENSE AMENDMENT NO. 252 RENEWED FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Licenses with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove License Pages License No. NPF-4, page 3 License No. NPF-7, page 3 License Pages License No. NPF-4, page 3 License No. NPF-7, page 3

-3 (2) Pursuant to the Act and 10 CFR Part 70, VEPCO to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30,40, and 70, VEPCO 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 component; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to a/l 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 VEPCO is authorized to operate the North Anna Power Station, Unit No.1, at reactor core power levels not in excess of 2940 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 270 are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

Renewed License No. NPF-4 NORTH ANNA - UNIT 1 Amendment No.270

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 252 Renewed License No. NPF-7

1.

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

A.

The application for amendment by Virginia Electric and Power Company et aI., (the licensee) dated September 27,2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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; 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.

2.

Accordingly, the license is amended by changes to paragraph 2.C (2) of Renewed Facility Operating License No. NPF-7, as indicated in the attachment to this license amendment, and is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Further Renewed Facility Operating License No. NPF-7 is hereby amended to authorize changes to the North Anna Emergency Action Level (EAL) to add 15-minutes threshold for reactor coolant system leaks, based on NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, " 'Use of NEI 99-01, Methodology for Development of Emergency Action Levels,' Revision 4, Dated January 2003," dated December 12, 2005. That is, an EAL is altered such that classification of the event could be different than the site-specific EAL as approved by the NRC Safety Evaluation Report dated February 4, 2008.

4.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCL R REGULATORY COMMISSION

~~

Eric J. eeds, Director Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-7 and the Technical Specifications 4 Date of Issuance: September 25, 2013

-3 (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO 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; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations as 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 VEPCO is authorized to operate the facility at steady state reactor core power levels not in excess of 2940 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252 ate hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the condition or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission:

a. If VEPCO plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the North Anna Power Station, the NORTH ANNA - UNIT 2 Renewed License No. NPF-7 Amendment No.252

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 280 Renewed License No. DPR-32

1.

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

A.

The application for amendment by Virginia Electric and Power Company et al.. (the licensee) dated September 27,2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act). and the Commission's rules and regulations 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; 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.

2.

Accordingly, the license is amended by changes to paragraph 2.C (2) of Renewed Facility Operating License No. DPR-32, as indicated in the attachment to this license amendment, and is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 200, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Further Renewed Facility Operating License No. DPR-32 is hereby amended to authorize changes to the Surry Emergency Action Level (EAL) to add 15-minutes threshold for reactor coolant system leaks, based on NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, " 'Use of NEI 99-01, Methodology for Development of Emergency Action Levels,' Revision 4, Dated January 2003," dated December 12, 2005. That is, an EAL is altered such that classification of the event could be different than the site-specific EAL as approved by the NRC Safety Evaluation Report dated February 4, 2008.

4.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

FOR THE NUCL R REGULATORY COMMISSION

~~

Eric J. eeds, Director Offic of Nuclear Reactor Regulation

Attachment:

Changes to License No. DPR-32 and the Technical Specifications Date of Issuance: September 25, 2013

ATTACHMENT TO LICENSE AMENDMENT NO. 280 RENEWED FACILITY OPERATING LICENSE NO. DPR-32 DOCKET NO. 50-280 AND TO LICENSE AMENDMENT NO. 280 RENEWED FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NO. 50-281 Replace the following pages of the Licenses with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove License Pages License No. DPR-32, page 3 License No. DPR-37, page 3 License Pages License No. DPR-32, page 3 License No. DPR-37, page 3

-3

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 1 0 CFR Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2587 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment N02oo, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.

D. Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.

E. Deleted by Amendment 65 F. Deleted by Amendment 71 G. Deleted by Amendment 227 H. Deleted by Amendment 227 I. Fire Protection The licensee shall implement and maintain in effect the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report and as approved in the SER dated September 19, 1979, (and Supplements dated May 29,1980, October 9, 1980, December 18,1980, February 13, 1981, December 4, 1981, April 27, 1982, November 18,1982, January 17,1984, February 25, 1988, and Surry - Unit 1 Renewed License No. DPR-32 Amendment No. 200

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 280 Renewed License No. DPR-37

1.

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

A.

The application for amendment by Virginia Electric and Power Company et ai., (the licensee) dated September 27, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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; 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.

2.

Accordingly, the license is amended by changes to paragraph 2.C (2) of Renewed Facility Operating License No. DPR-37, as indicated in the attachment to this license amendment, and is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 280, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

Further Renewed Facility Operating License No. DPR-37 is hereby amended to authorize changes to the Surry Emergency Action Level (EAL) to add 15-minutes threshold for reactor coolant system leaks, based on NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, "'Use of NEI 99-01, Methodology for Development of Emergency Action Levels,' Revision 4, Dated January 2003," dated December 12, 2005. That is, an EAL is altered such that classification of the event could be different than the site-specific EAL as approved by the NRC Safety Evaluation Report dated February 4, 2008.

4.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance.

Eric J.

eds, Director Offic of Nuclear Reactor Regulation

Attachment:

Changes to License No. DPR-37 and the Technical Specifications Date of Issuance: September 25, 2013

-3 E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2587 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No200, are hereby incorporated in this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.

D. Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.

E. Deleted by Amendment 54 F. Deleted by Amendment 59 and Amendment 65 G. Deleted by Amendment 227 H. Deleted by Amendment 227 Renewed License No. DPR-37 Surry - Unit 2 Amendment No.200

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 270 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-4, AMENDMENT NO. 252 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-7, AMENDMENT NO. 280 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-32, AMENDMENT NO. 280 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNITS 1 AND 2, AND SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-338, 50-339,50-280 AND 50-281

1.0 INTRODUCTION

By application dated September 27, 2012 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML12283A069), Virginia Electric and Power Company (the licensee) submitted a license amendment request to the U.S. Nuclear Regulatory Commission (NRC) to change the Emergency Action Levels (EALs) for North Anna Power Station (NAPS),

Units 1 and 2, and Surry Power Station, Units 1 and 2.

The licensee requested authorization to add is-minutes threshold for reactor coolant system (RCS) leaks, based on NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, "'Use of NEI 99-01, Methodology for Development of Emergency Action Levels,' Revision 4, Dated January 2003," dated December 12,2005. That is, an EAL is altered such that classification of the event could be different than the site-specific EAL as approved by the NRC Safety Evaluation Report dated February 4, 2008.

Specifically, the licensee requested a change to EAL SU6 for each site. The requested change would add 15 minutes to the EAL to preclude classification for brief and readily isolatable RCS leaks.

2.0 REGULATORY EVALUATION

The NRC staff reviewed the proposed revision against the following regulations and guidance:

- 2 2.1 Regulations Title 10 of the Code of Federal Regulations (10 CFR), Section S0.47, "Emergency plans," sets forth emergency plan requirements for nuclear power plant facilities. Section S0.47(a)(1 )(i) states, in part, that "no initial operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency".

Section S0.47(b) establishes the standards that the onsite and offsite emergency response plans must meet for NRC staff to make a finding that there is reasonable assurance that the licensee can and will take adequate protective measures in the event of a radiological emergency.

Planning Standard (4) of this section requires that a licensee's emergency response plan contain:

"A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures." Section S0.47(b)(4) to 10 CFR specifies a standard emergency classification and action level scheme, and as such, the NRC staff will ensure that implementation methods are relatively consistent throughout the industry for a given reactor and containment design while simultaneously providing an opportunity for a licensee to modify their EAL scheme as necessary to address plant-specific design considerations or preferences.

Section SO.S4(q)(4) states, in part, that:

The changes to a licensee's emergency plan that reduce the effectiveness of the plan as defined in paragraph (q)( 1 )(iv) of this section may not be implemented without prior approval by the NRC.

The proposed change was submitted to the NRC for a technical and regulatory review prior to implementation by the licensee, as required under 10 CFR SO.S4(q).

2.2 Guidance EAL development guidance was initially established via Generic Letter (GL) 79-S0 and subsequently established in NUREG-06S4/FEMA-REP-1, which was endorsed as an approach for the development of an EAL scheme via NRC Regulatory Guide (RG) 1.101, Revision 2. As industry and regulatory experience was gained with the implementation and use of the EAL scheme, the industry developed revised EAL scheme development guidance documents to gain the benefit of lessons learned. To date, NUMARC/NESP-007, NE199-01 Revision 4, NE199-01 Revision S, and NEI 99-01 Revision 6 were provided to the NRC for review and endorsement as generic (non plant-specific) EAL development guidance. RG 1.101, Revisions 3 and 4 endorsed NUMARC/NESP-007 and NEI 99-01 Revision 4 as acceptable alternatives for licensees to consider in the development of their plant-specific EAL schemes, as well as allowing licensees to develop plant-specific EALs based upon an alternative approach not endorsed by the NRC. NEI 99-01 Revision S was endorsed as generic (non plant-specific) EAL development guidance via letter dated February 22,2008. NE199-01 Revision 6 was endorsed as generic (non plant-specific) EAL development guidance via letter dated March 28, 2013.

- 3 GL 79-50, NUREG-0654/FEMA-REP-1, NUMARC/NESP-007, NEI 99-01 Revision 4, and NEI 99-01 Revision 5 are all considered generic EAL development guidance documents, as they are not plant-specific and may not be entirely applicable for some reactor designs. However, the guidance contained in these documents bounds the most typical accident/event scenarios for which emergency response is necessary in a format that allows for industry standardization and consistent regulatory oversight. Most licensees choose to develop their plant-specific EAL schemes using the latest endorsed EAL development guidance with appropriate plant-specific alterations as applicable.

The NRC considers the following methods acceptable for use in developing plant-specific EALs that meet the requirements of Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4), with the understanding that licensees may want to develop EALs that differ from the applicable guidance document as allowed in RG 1.101 and in the letters dated February 22, 2008, and March 28, 2013, respectively:

Appendix 1, "Emergency Action Level Guidelines for Nuclear Power Plants," to NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," dated November 1980; NUMARC/NESP-007, Revision 2, "Methodology for Development of Emergency Action Levels,"

dated January 1992; NEI 99-01, Revision 4, "Methodology for Development of Emergency Action Levels," dated January 2003; NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels," dated February 2008; and NEI 99-01, Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors,"

dated November 2012.

NRC Regulatory Issue Summary (RIS) 2003-18, Supplements 1 and 2, "Use of NEI 99-01, Methodology for Development of Emergency Action Levels", also provide guidance for developing or changing a standard emergency classification and action level scheme. In addition, this RIS and its Supplements provide recommendations to assist licensees, consistent with Section IV.S of Appendix E to Part 50, in determining whether to seek prior NRC approval of deviations from the guidance.

Regardless of the generic EAL scheme development guidance document used by a licensee to develop their EAL scheme, or if a licensee chose to develop their EAL scheme using an alternative approach not endorsed by the NRC, or a combination of the two (most typical), the NRC will review the EAL scheme to ensure it meets the requirements of Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4).

3.0 TECHNICAL EVALUATION

The licensee submitted a license amendment to revise the EAL for classifying a (Notice of)

Unusual Event (UE) for RCS leaks. Specifically, the licensee requested a change to EAL SU6 for

-4 NAPS and SPS. The requested change would add 15 minutes to the EAL to preclude classification for brief and readily isolatable RCS leaks. That is, an EAL is altered such that classification of the event could be different than the site-specific EAL as approved by the NRC Safety Evaluation Report dated February 4, 2008. The addition of a 15-minute time threshold allows for the plant operators to isolate the RCS leaks using readily accessible means available in the Control Room. The addition of this timing statement is consistent with the above stated guidance and the NRC staff expectations regarding basing EAL classification on events that pose, or could pose if escalated, a radiological risk to the public.

The NRC staff has evaluated that the changes would not affect plant safety and would not have an adverse effect on the probability of an accident. The proposed change has no effect on the consequences of any analyzed accident since the change does not affect any equipment related to accident mitigation. The addition of a 15-minute criterion to the EAL only serves to ensure the EAL declaration is based upon plant conditions that are more indicative of a (Notice of) UE emergency classification level. The brief delay in declaring the proposed action would not result in radiological hazard beyond those previously analyzed in the Updated Final Safety Analysis Report, as this emergency classification level is based upon plant events that have no radiological consequences. There will be no change to radioactive effluents that affect radiation exposures to plant workers and members of the public. No changes will be made to plant buildings or the site property. Therefore, no changes or different types of radiological impacts are expected as a result of the proposed changes. The NRC staff has determined that the proposed change meets the guidance in NEI 99-01, the requirements of 10 CFR 50.47(b)(4}, and the standards in Appendix E to 10 CFR 50. Therefore, the NRC staff concludes that the proposed EAL change for EAL SU6 provides reasonable assurance that the licensee can and will take adequate protective measures in the event of a radiological emergency.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments authorize the addition of a 15-minute threshold for RCS leaks applicable to EALs. 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 amendment involves no significant hazards considerations, and there has been no public comment on the finding (77 FR 73691, December 11, 2012).

In addition, pursuant to 10 CFR 51.21,51.32, and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Register on August 1,2013 (78 FR 46616). Accordingly, based upon the environmental assessment, the Commission has determined that issuance of this amendment will not have a significant effect on the quality of the human environment.

- 5

6.0 CONCLUSION

The NRC staff has concluded, on the basis of 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) 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: D. Johnson, NSIR/DPR Date: September 25, 2013

September 25, 2013 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

NORTH ANNA POWER STATION, UNITS 1 AND 2 (NAPS), AND SURRY POWER STATION, UNITS 1 AND 2 (SURRY) -ISSUANCE OF AMENDMENTS FOR CHANGES TO THE EMERGENCY ACTION LEVEL REVISIONS (TAC NOS.

ME9753, ME9754, ME9755, AND ME9756)

Dear Mr. Heacock:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 270 and 252 to Renewed Facility Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station, Units 1 and 2, and Amendment Nos. 280 and 280 to Renewed Facility Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station, Units 1 and 2. This amendment is in response to your application dated September 27,2012, for the proposed changes to the Emergency Action Level (EAL).

The amendments authorize the addition of a 15-minute threshold for reactor coolant system leaks, based on NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, " 'Use of NEI 99-01, Methodology for Development of Emergency Action Levels,' Revision 4, Dated January 2003,"

dated December 12, 2005.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRA!

Dr. V. Sreenivas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338, 50-339, 50-280, and 50-281

Enclosures:

1. Amendment No. 270 to NPF-4

2. Amendment No. 252 to NPF-7

3. Amendment No. 280 to DPR-32

4. Amendment No. 280 to DPR-37

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

Public LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsNrrPMNorthAnna (hard copy)

RidsN rrDorl DprResou rce RidsAcrsAcnw_MailCTR Resource RidsRgn2MailCenter JAnderson, NSIR DJohnson, NSIR RidsNrrDdssStsb Resource RidsNrrLASFigueroa Resource RidsNrrPMSurry ADAMS Accession No.: ML13186A197 OFFICE LPL2-1/PM LPL2-1/PM LPL2-1/LA VSreenivas KCotton,for SFigueroa JAnderson* MYoung 09/11/2013 09/11/2013 911312013 06/18/2013 09/10/2013 09/13/2013 OFFICIAL RECORD COpy LPL2-1/PM VSreenivas 09/25113