ML14282A118

Issuance of Amendments Regarding Containment Divider Barrier Seal (TAC Nos. MF3052 and MF3053)

ML14282A118
Person / Time
Site:	Cook
Issue date:	11/20/2014
From:	Chawla M L Plant Licensing Branch III
To:	Weber L J Indiana Michigan Power Co
Chawla M L
References
TAC MF3052, TAC MF3053
Download: ML14282A118 (18)

Text

Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 20, 2014 Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS REGARDING CONTAINMENT DIVIDER BARRIER SEAL RE: (TAC NOS. MF3052 AND MF3053)

Dear Mr. Weber:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 324 to Renewed Facility Operating License No. DPR-58 and Amendment No. 307 to Renewed Facility Operating License No. DPR-7 4 for the Donald C. Cook Nuclear Plant, Units 1 and 2. The amendments consist of changes to the technical specifications (TSs) in response to your application dated November 6, 2013, as supplemented by letters dated June 13, 2014, and August 15, 2014. The amendments would revise TS 3.6.13, "Divider Barrier Integrity", Surveillance Requirement 3.6.13.5 for the divider barrier seal inspection for the Donald C. Cook Nuclear Plant, Units 1 and 2. A copy of our related safety evaluation is also enclosed.

A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket Nos. 50-315 and 50-316

Enclosures:

1. Amendment No. 324 to DPR-58 2. Amendment No. 307 to DPR-74 3. Safety Evaluation cc w/encls: Distribution via ListServ Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No.324 License No. DPR-58 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Indiana Michigan Power Company (the licensee) dated November 6, 2013, as supplemented by letters dated June 13, 2014, and August 15, 2014, 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 the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-58 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 324, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Enclosure 1 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days.

Attachment:

FOR THE NUCLEAR REGULATORY COMMISSION L Pelton, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Technical Specifications Date of Issuance:

November 20, 2014 ATTACHMENT TO LICENSE AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following page of Renewed Facility Operating License DPR-58 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change. REMOVE INSERT 3 3 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. REMOVE INSERT 3.6.13-2 3.6.13-2 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, 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 and equipment calibration or associated with radioactive apparatus or components; and (5) 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.

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 1: 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; 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 steady state reactor core power levels not to exceed 3304 megawatts thermal in accordance with the conditions specified herein. (2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 324, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Less than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license. (4) Fire Protection Program Indiana Michigan Power Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee's amendment request dated July 1, 2011, as supplemented by letters dated September 2, 2011, April 27, 2012, June 29, 2012, August 9, 2012, October 15, 2012, November 9, 2012, January 14, 2013, February 1, 2013, Renewed License No. DPR-58 Amendment No. 324 SURVEILLANCE REQUIREMENTS SR 3.6.13.1 SR 3.6.13.2 SR 3.6.13.3 SR 3.6.13.4 SR 3.6.13.5 SURVEILLANCE Verify, by visual inspection, all personnel access doors and equipment hatches between upper and lower containment compartments are closed. Verify, by visual inspection, that the seals and sealing surfaces of each personnel access door and equipment hatch have: a. No detrimental misalignments;

b. No cracks or defects in the sealing surfaces; and c. No apparent deterioration of the seal material.

Verify, by visual inspection, each personnel access door or equipment hatch that has been opened for personnel transit entry is closed. Remove two divider barrier seal test coupons and verify: a. Both test coupons' tensile strength is 120 psi; and b. Both test coupons' elongation is<:: 100%. Visually inspect 95% of the divider barrier seal length, and verify: a. Seal and seal mounting connections are installed such that the total divider barrier bypass area is maintained within design limits; and b. Seal material shows no evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearance.

Divider Barrier Integrity 3.6.13 FREQUENCY Prior to entering MODE 4 from MODE5 Prior to final closure after each opening AND Only required for seals made of resilient materials 10 years After each opening 24 months 24 months Cook Nuclear Plant Unit 1 3.6.13-2 Amendment No. 237-, 324 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 307 License No. DPR-7 4 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Indiana Michigan Power Company (the licensee) dated November 6, 2013, as supplemented by letters dated June 13, 2014, and August 15, 2014, 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 the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-74 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 307, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Enclosure 2 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days.

Attachment:

NUCLEAR REGULATORY COMMISSION avid L. Pel on, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Technical Specifications Date of Issuance:

November 20, 2014 ATTACHMENT TO LICENSE AMENDMENT N0.307 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following page of Renewed Facility Operating License DPR-74 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change. REMOVE INSERT 3 3 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. REMOVE INSERT 3.6.13-2 3.6.13-2 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, 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 and equipment calibration or associated with radioactive apparatus or components; and (5) 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.

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 1: 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; 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 steady state reactor core power levels not to exceed 3468 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to the renewed operating license. The preoperational tests, startup tests and other items identified in Attachment 1 to this renewed operating license shall be completed.

Attachment 1 is an integral part of this renewed operating license. (2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 307, I are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) ,Additional Conditions (a) Deleted by Amendment No. 76 (b) Deleted by Amendment No.2 (c) Leak Testing of Emergency Core Cooling System Valves Indiana Michigan Power Company shall prior to completion of the first inservice testing interval leak test each of the two valves in series in the Renewed License No. DPR-74 Amendment No. 307 SURVEILLANCE REQUIREMENTS SR 3.6.13.1 SR 3.6.13.2 SR 3.6.13.3 SR 3.6.13.4 SR 3.6.13.5 SURVEILLANCE Verify, by visual inspection, all personnel access doors and equipment hatches between upper and lower containment compartments are closed. Verify, by visual inspection, that the seals and sealing surfaces of each personnel access door and equipment hatch have: a. No detrimental misalignments;

b. No cracks or defects in the sealing surfaces; and c. No apparent deterioration of the seal material.

Verify, by visual inspection, each personnel access door or equipment hatch that has been opened for personnel transit entry is closed. Remove two divider barrier seal test coupons and verify: a. Both test coupons' tensile strength is 2:: 120 psi; and b. Both test coupons' elongation 100%. Visually inspect 2:: 95% of the divider barrier seal length, and verify: a. Seal and seal mounting connections are installed such that the total divider barrier bypass area is maintained within design limits; and b. Seal material shows no evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearance.

Divider Barrier Integrity 3.6.13 FREQUENCY Prior to entering MODE 4 from MODES Prior to final closure after each opening AND Only required for seals made of resilient materials 10 years After each opening 24 months 24 months Cook Nuclear Plant Unit 2 3.6.13-2 Amendment No. 269, 307 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 AND AMENDMENT NO. 307 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316

1.0 INTRODUCTION

By application dated November 6. 2013 (Agencywide Documents Access and Management System (ADAMS Accession No. ML 13312A006), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (CFR), Indiana Michigan Power Company (I&M, or licensee) submitted a license amendment request (LAR) for changes to Donald C. Cook Nuclear Plant (CNP) Units 1 and 2 technical specifications (TSs). The licensee's proposed change would revise TS 3.6.13, Divider Barrier Integrity, and Surveillance Requirement (SR) 3.6.13.5 for the divider barrier seal inspection.

The licensee's letter dated November 6, 2013, was supplemented by letters dated June 13, 2014 (ADAMS Accession No. ML 14167A374), and August 15, 2014 (ADAMS Accession No. ML 14230A678), which provided responses to the U.S. Nuclear Regulatory Commission (NRC) staff's requests for additional information (RAis). The supplemental letters dated June 13, 2014, and August 15, 2014, 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 19, 2014 (79 FR 9496).

2.0 REGULATORY EVALUATION

The regulation at 10 CFR Section 50.36(c)(3), "Surveillance requirements" states: Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Enclosure 3 The licensee states "The construction permits for CNP were issued and the majority of construction was completed prior to issuance of 10 CFR 50, Appendix A, General Design Criteria" and "CNP was designed and constructed to comply with the Atomic Energy Commission (AEC) General Design Criteria (GDC) as proposed on July 10, 1967". Therefore the licensee will be complying with the AEC proposed General Design Criteria to the CNP which is contained in the CNP Updated Final Safety Analysis Report (UFSAR) as the Plant Specific Design Criteria (PSDC) and differs from Appendix A of 10 CFR Part 50 GDC in both numbering and content. The PSDC applicable to this LAR are discussed below: PSDC 10 Reactor Containment The CNP UFSAR states: The containment structure shall be designed (a) to sustain without undue risk to the health and safety of the public the initial effects of gross equipment failures, such as a large reactor coolant pipe break, without loss of required integrity, and (b) together with other engineered safety features as may be necessary, to retain for as long as the situation requires the functional capability of the containment to the extent necessary to avoid undue risk to the health and safety of the public. PSDC 49 Reactor Containment Design Basis The CNP UFSAR states: The reactor containment structure, including openings and penetrations, and any necessary containment heat removal systems, shall be designed so that the leakage of radioactive materials from the containment structure under conditions of pressure and temperature resulting from the largest credible energy release following a loss-of-coolant accident, including the calculated energy from water or other chemical reactions that could occur as a consequence of failure of any single active component in the emergency core cooling system will not result in undue risk to the health and safety of the public. 3.0 TECHNICAL EVALUATION CNP Units 1 and 2 containment buildings are reinforced concrete structures consisting of a vertical cylinder, a hemispherical dome, and a flat base slab. A steel liner is attached to the inside face of the concrete (shell, dome, and the base slab); the interior of the containment structure is divided into three compartments:

• A lower compartment that houses the reactor and the reactor coolant system;

• An intermediate compartment that houses the energy absorbing ice bed (ice condenser compartment);

and

• An upper compartment that accommodates the air displaced from the other two compartment volumes during an accident condition.

The ice condenser is an insulated cold storage room in which ice is contained in a vertical cylindrical column. In an accident scenario, lower inlet doors located below the operating deck at the bottom of the ice condenser open due to the rise in pressure in the lower compartment.

This allows steam to flow from the lower compartment into the ice condenser compartment.

The steam is condensed as it enters the ice condenser compartment, thus limiting the peak pressure in the containment.

The divider barrier between the upper and lower containment compartment is designed to carry the differential pressure between the lower and upper compartments during the postulated of-coolant accident.

The divider barrier seal provides a pressure boundary between the lower and upper containment compartments of the containment structure and is located on the boundary of these compartments.

The divider barrier seal is a structurally mounted flexible seal backed up by a steel plate that prevents the flow of steam and air from bypassing the ice condenser.

The licensee's submitted amendment proposes to revise the SR 3.6.13.5.a as follows: Current SR 3.6.13.5.a: "Seal and seal mounting bolts are properly installed; and" Revised SR 3.6.13.5.a: "Seal and seal mounting connections are installed such that the total divider barrier bypass area is maintained within design limits; and" The proposed change to the SR 3.6.15.5.a involves two changes. The first proposed change to the SR replaces the word "bolts" with the word "connections".

In an RAI, the NRC staff requested the licensee describe the types of connections and the procedure that will be used for verifying acceptable installation of these connections.

On June 13, 2014, the licensee provided a response to SCVB-RAI-2 (ADAMS Accession No. ML 14167A374), stating the following:

Procedures for performing the divider barrier seal surveillance contain design configuration criteria for the proper/acceptable installation of these connections.

The criteria specified by the surveillance procedures include: bolt spacing, edge distances, number of connections, and tightness.

The licensee also provided a response to STSB RAI-1C (ADAMS Accession No. ML 14167A374), stating the following:

Seal mounting connections currently holding the divider barrier seal in place include bolts, screws, welded studs, nuts, welds, and concrete anchors. These connections are not specifically described in the UFSAR but are described on various CNP controlled design drawings, including but not limited to 1-2-3207E, 1-2-3207F, and 1-AEQS-226-A. Based on the NRC staff's review of the licensee's responses to SCVB-RAI-2 and STSB RAI-1 C, (ADAMS Accession No. ML 14167A374), the staff finds that the proposed change to the SR replacing the word "bolts" with the word "connections" is acceptable because the licensee describes connections used in CNP controlled design drawings in 1-2-3207E, 1-2-3207F, and 1-AEQS-226-A.

Further, the licensee explains that they have procedures in place for performing the divider barrier seals surveillance for the acceptable installation of these connections.

The proposed change to the SR 3.6.13.5.a also includes the requirement that the installed connections should maintain the total divider bypass area within the design limits. In RAI-3, the licensee was requested to describe the NRC-approved methodology that will be used to determine that the acceptance criteria for the bypass area are met. In a letter dated June 13, 2014 (ADAMS Accession No. ML 14167A374), the licensee stated the following:

In case deficient connections are discovered, then the resulting divider barrier bypass would be determined, using an accepted standard, the American Institute of Steel Construction (AISC) Manual of Steel Construction, (tables for beam diagrams and formulas), as referenced in Updated Final Safety Analysis Report (UFSAR) Chapter 5, or using a simplified method that is more conservative, to determine the deflections of the as found configurations due to a postulated blowdown, and these deflections would be used to quantify the bypass area. The total bypass area for that unit is then compared against the Allowable Design Basis Bypass Area of seven square feet, per UFSAR 5.3.5.15.4.

The assumed Analysis Value is 35 square feet, per UFSAR 14.3.4.1.3.1.1.e.

After reviewing the above response, the NRC staff requested the licensee to explain: simplified method that is more conservative to determine the deflections of the as found configurations." More specifically, the licensee was requested to discuss the simplified method, the standard on which it is based, and the conservatism in the method. In a letter dated August 15, 2014 (ADAMS Accession No. ML 14230A678), the licensee stated, in part: "The simplified method is also based on the AISC standard." The licensee provided a pictorial drawing describing two cantilever beams, each attached at one end, with a uniformly distributed load (as referenced in the AISC Manual of Steel Construction 7th edition) to determine the assumed divider barrier bypass area. The NRC staff finds the licensee's responses acceptable because the assumed bypass area derived by using the simplified method based upon the pictorial drawing (two cantilever beams) would be approximately three times larger than the bypass area calculated by the exact AISC structural analysis method based on the fixed beam and thus would be more conservative.

Based on its review, the staff finds that the proposed change meets the requirements of PSDC contained in the licensee's UFSAR, (1) PSDC 10, because the licensee showed that the containment design structure important to safety are not exceeded during an accident.

The staff also finds that the proposed change meets the requirements of PSDC contained in UFSAR, (2) PSDC 49, because the licensee showed that the reactor containment structure and penetrations, with the aid of containment heat removal systems including the ice bed, are designed to limit radioactive fission products from the containment below 10 CFR 100 values. In addition, the NRC staff determined that the proposed modification does not change the intent of the surveillance requirements in SR 3.6.13.5.a and that the licensee will continue to meet the requirements in 10 CFR 50.36(c)(3).

Therefore, the NRC staff finds the proposed license amendment to be acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendments.

The State official had no comments.

5.0 ENVIRONMENTAL

CONSIDERATION The amendments change the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements.

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 (79 FR 9496). 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:

Samina Shaikh Date: November 20, 2014 A copy of our related safety evaluation is also enclosed.

A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket Nos. 50-315 and 50-316

Enclosures:

1. Amendment No. 324 to DPR-58 2. Amendment No. 307 to DPR-74 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION:

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• REIIiott DATE 10/22/14 10/23/14 08/27/14 11/02/14 OFFICE OGC NRR/LPL3-1/BC NRR/LPL3-1/PM NAME A Ghosh DPelton MChawla DATE 11/19/14 11/20/14 11/20/14 OFFICIAL RECORD COPY