Resolution

Gentlemen: Grand Gulf Nuclear Station (GGNS) provided an action plan for the resolution of Generic Letter (GL) 96-06. This justification was provided for the continued operability of the penetrations until RF01 1 at which time the modifications necessary to remedy the affected penetrations were to be installed. Subsequent to the commitment to complete all modifications by RF01 1 extenuating circumstances have arisen requiring GGNS to defer four penetrations requiring installation of seven relief valves until RFO12. The circumstances dictating the need for this deferral are lack of resources (qualified welders). Additionally, due to work locations for some of the penetrations scheduling around other work presented a significant outage impact. Attachment 1 identifies the commitments GGNS has remaining open to resolve GL 96-06. Attachment 2 identifies the scope of work to be performed in RF01 1 and RF012 with regards to GL 96-06. GGNS generated Condition Reports to track and resolve the issues related to this subject. The affected Condition Reports were entered into the GL 91-18 process and as such will receive appropriate review by the Plant Safety Review Committee to ensure continued operability. GNRO-2001100005 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on January 29,200l. Very truly yours, LFD attachments: C

Possible Licensing And Construction Of Small Modular Reactor Modules At The Clinch River Site"

In Reference 1, TVA outlined the key licensing assumptions underpinning its evaluation of the feasibility of siting up to six Babcock &Wilcox (B&W) mPower design small modular reactor (SMR) modules at TVA's Clinch River site in Roane County, Tennessee. In response to TVA's Key Licensing Assumptions, the NRC Staff requested additional details regarding the key assumptions in a letter dated December 1, 2010 (Reference 2). On December 14, 2010, the NRC Staff held a public meeting with TVA to further discuss these questions and to help to clarify the assumptions. U.S. Nuclear Regulatory Commission Page

IN NRC PUBLICATIONS NRC Reference Material

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PLANT NAME DOCKET NO. 50- APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT TO EXTEND THE INSPECTION INTERVAL FOR REACTOR COOLANT PUMP FLYWHEELS USING THE CONSOLIDATED LINE ITEM IMPROVEMENT

PROCESS Dear Sir or Madam: Pursuant to 10 CFR 50.90, [license holder] hereby requests an amendment to the Technical Specifications (TS) for [PLANT NAME, UNIT NOS.]. The proposed amendment will extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years. The changes are consistent with Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, “Revision to RCP Flywheel Inspection Program (WCAP-15666). ” The availability of this TS improvement was announced in the Federal Register on [DATE OF NOTICE OF AVAILABILITY] as part of the consolidated line item improvement process (CLIIP). Attachment 1 provides a description of the proposed change and the requested confirmation of applicability. Attachment 2 provides the existing TS pages marked-up to show the proposed change. Attachment 3 provides revised, clean TS pages. [LICENSEE] requests approval of the proposed License Amendment by [DATE], with th

Component Cooling Water System Issues Reference: 1) Letter from Wisconsin Electric Power Company to Document Control Desk, "Component Cooling Water System Issues Update", dated July 7,

conducted portions of an Inspection Procedure (P95003) at the Point Beach Nuclear Plant (PBNP). This inspection was initiated by the NRC in response to the identification by the licensee of a regulatory oversight process (ROP) red finding associated with the PBNP auxiliary feedwater system. The inspection was conducted from September 8 to October 3, 2003, and consisted of an in-depth examination of engineering, operations and maintenance issues and activities associated with three PBNP safety-related systems. One of those systems was the component cooling water (CCW) system. As part of the preparations for this inspection, a summary was prepared of the design and licensing bases for the CCW system. The summary included identification of significant changes to these bases since initial plant licensing. Among these changes was the upgrade of the CCW system to safety-related status. During the preparation of this summary, NMC identified correspondence between the licensee and the NRC, including Reference 1, that discussed our schedule and commitments for this CCW upgrade

An Equal Opportunity Employer M/F/HCNETET 06-0026

Generating Station (WCGS). This amendment application proposes a one time revision t

Request for Relief from ASME OM Code Test Intervals for Pressure Relief Valves

In accordance with 10 CFR 50.55a, "Codes and standards, " PSEG Nuclear LLC (PSEG), hereby requests NRC approval of proposed Relief Request V-07 to extend the test intervals for certain Class 2 and 3 pressure relief valves on a one-time basis until restart after refueling outage 2R17, which is currently scheduled to begin in October 2009. PSEG requests approval of the proposed request by April 17, 2009 to permit continued plant operation until 2R17. Relief Request V-07 applies to the end of the current third 10-year inservice testing (IST) interval and to the start of the fourth interval. The third interval will end on August 30, 2009, and the fourth interval will begin on August 31, 2009. The Code of Record for the current third interval is American Society of Mechanical Engineers (ASME)/American National Standards Institute, "Code fo

*Office of State Programs "Office of Nuclear Reactor Regulation

The purpose of this report is to provide a basis for Federal,State and local government emergency preparedness organizations to determine the appropriate degree of emergency response planning efforts in the environs of nuclear power plants. The report is the product of a Task Force of NRC and EPA representatives formed in 1976 to address this issue. The Task Force hopes that the guidance provided here will be used to supplement the extensive emergency planning guidance already published by NRC and EPA. This report introduces the concept of generic Emergency Planning Zones as a basis for the planning of response actions which would result in dose savings in the environs of nuclear facilities in the event of a serious power reactor accident. Application of the Task Force guidanc

Facility Operating License Nos. DPR-63 & NPF-69 Application for License Transfers and Conforming Administrative License Amendments

(1) Constellation Nuclear, LLC, on behalf of its indirect subsidiary (to be created) Nine Mile Point Nuclear Station, LLC ("NMP LLC") (hereinafter collectively referred to as "Constellation Nuclear") and Niagara Mohawk Power Corporatio

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