NL-10-076, Amendment 10 to License Renewal Application

Amendment 10 to License Renewal Application

ML102150347
Person / Time
Site:	Indian Point
Issue date:	07/26/2010
From:	Dacimo F Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-10-076
Download: ML102150347 (8)

Text

Enterayv Nuclear Northeast Indian Point Energy Center

'--Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 788-2055 Fred Dacimno Vice President License Renewal NL-10-076 July 26, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Amendment 10 to License Renewal Application (LRA)

Indian Point Nuclear Generating Unit Nos. 2 & 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64

REFERENCES:

1. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application" (NL-07-039)

2. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Boundary Drawings (NL-07-040)

3. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Environmental Report References (NL-07-041)

4. Entergy Letter dated October 11, 2007, F. R, Dacimo to Document Control Desk, "License Renewal Application (LRA)" (NL-07-124)

5. Entergy Letter November 14, 2007, F. R, Dacimo to Document Control Desk, "Supplement to License Renewal Application (LRA)

Environmental Report References" (NL-07-133)

Dear Sir or Madam:

In the referenced letters, Entergy Nuclear Operations, Inc. applied for renewal of the Indian Point Energy Center operating license. This letter contains Amendment 10 of the License Renewal Application (LRA).

If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-734-6710.

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NL-10-076 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on Sincerely, FRD/cbr

Attachment:

1. Annual Update Amendment cc: Mr. Marc Dapas, Acting Regional Administrator, NRC Region I Mr. Sherwin E., Turk, NRC Office of General Counsel, Special Counsel Mr. Kenneth Chang, NRC Branch Chief, Engineering Review Branch I Mr. John Boska, NRR Senior Project Manager Mr. Paul Eddy, New York State Department of Public Service NRC Resident Inspector's Office Mr. Francis J. Murray, President and CEO, NYSERDA

ATTACHMENT 1 TO NL-10-076 Annual Update Amendment ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286

NL-10-076 Docket Nos. 50-247 and 50-286 Attachment 1 Page 1 of 5 INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION ANNUAL UPDATE AMENDMENT In accordance with 10 CFR 54.21(b), each year following submittal of the license renewal application and at least 3 months before scheduled completion of the NRC review, an amendment to the renewal application must be submitted that identifies any change to the CLB of the facility that materially affects the contents of the license renewal application (LRA), including the FSAR supplement. This attachment is the required annual update amendment to the Indian Point Energy Center (IPEC) LRA.

This amendment is based on a review of documents potentially affecting the CLB during the period of March 2, 2009 through April 30, 2010. The last annual update of the LRA included a review of documents through March 1, 2009.

The review concluded that certain sections of the LRA are affected by changes to the CLB that occurred during the period of review. The table below summarizes the changes listing the affected system (if applicable), an explanation of the change (including effect on the LRA), and the affected LRA section.

IPEC LRA Sections Affected CLB Change LRA Section Affected Entergy modified the sodium hypoclorite system by replacing 1" carbon steel piping with 1" Schedule 40 PVC that extends below deck to replace diffusers and allow chlorination of the service water and circulating water bays. Table 3.3.2-19-5-1P3 Added plastic piping to Table 3.3.2-19-5-1P3 This material environment combination was evaluated in NUREG-1930, Section 3.3A.2.3.29.

An IP2 drawing revision for Drawing 238106 added the component type Filter Housing Table 2.3.2-5-1P2 Table 3.2,2-5-1P2 This material environment combination was evaluated in NUREG-1930, Section 3.2A.2.3.5.

IP3 correspondence notified the NRC that IP3 had entered the Inservice Inspection fourth ten-year Section A.3.1.17, interval using ASME 2001 Edition, 2003 Addenda. Section B.1.8 and Section B.1.18

NL-10-076 Docket Nos. 50-247 and 50-286 Attachment 1 Page 2 of 5 CLB Change LRA Section Affected IP3 correspondence notified the NRC that IP3 fourth ten-year Interval Inservice Inspection (ISI)

Program Plan identifies Code Case N-729-1 as an Section B.1.31 inspection requirement as required by 10CFR50.55a(g)(6)(ii)(D).

IPEC LRA changes are shown below.

(Changes are shown as strikethroughs for deletions and underlines for additions)

LRA Table 2.3.2-5-1P2, Containment Penetrations, is revised to add the following line items Component Type Intended Function(s)

Filter Housing Pressure boundary LRA Table 3.2.2-5-1P2, Containment Penetrations, is revised to add the following line items Aging Effect Aging NUREG-Component Intended Table 1 Material Environment Requiring Management 1801 Vol. 2 Notes Type Function Item Management Programs Item Filter Pressure Stainless Air- indoor None None V.F-12 3.2.1-53 A housing boundary steel (ext) (EP-1 8)

Filter Pressure Stainless Air - indoor None None .G housing boundary steel (int)

NL-10-076 Docket Nos. 50-247 and 50-286 Attachment 1 Page 3 of 5 LRA Table 3.3.2-19-5-1P3, Chlorination System, is revised to add the following line items Component Intended Aging Effect Aging NUREGo Table 1 Type Function Material Environment Requiring Management 1801 Vol. 2 Item Management Programs Item Piping Pressure Plastic Air - indoor None None .... F boundary (ext)

Piping Pressure Plastic Treated water None None .... F boundary (int)

LRA Section A.3.11.17 is revised as follows:

A.3.1.17 Inservice Inspection - Inservice Inspection (ISI) Program The ISI Program 'is an existing program based on ASME Section Xl Inspection Program B (Section XI, IWA-2432), which has ten-year inspection intervals. Every ten years the program is updated to the latest ASME Section Xl code edition and addendum approved in 10 CFR 50.55a.

The program consists of periodic volumetric, surface, and visual examination of components and their supports for assessment of signs of degradation, flaw evaluation, and corrective actions.

On July 21, 20-G-2009, the-site, IP3, entered the thid-fourth ISI interval. The ASME code edition and addenda used for the thid-fourth interval is the 41-989-2001 Edition with-ne 2003 a-Addenda.

LRA Section B.1.8 is revised as follows:

B.1.8 Containment Insevice Inspection Program Description (1st paragraph as amended by letter NL-08-092 dated June 11, 2008)

The Containment Inservice Inspection (CII) Program is an existing program encompassing ASME Section Xl Subsection IWE and IWL requirements as modified by 10 CFR 50.55a. The IP2 program uses the ASME Boiler and Pressure Vessel Code, Section Xl, 2001 Edition, 2003 Addenda. The IP3 program uses the ASME Boiler and Pressure Vessel Code, Section Xl,41-998 2001 Edition, F*) 2003 Addenda. Every 10 years, each unit's program is updated to the latest ASME Section Xl code edition and addenda approved by the Nuclear Regulatory Commission in 10 CFR 50.55a.

NL-10-076 Docket Nos. 50-247 and 50-286 Attachment 1 Page 4 of 5 LRA Section B.1.18 is revised as follows:

B.1.18 Inservice Inspection Proaram Description

( 7 th paragraph) (IP2 revision provided in letter NL-08-092 dated June 11, 2008)

On March 1, 2007, IP2 entered the fourth ISI interval and on July 21, 2-00-2009, IP3 entered the thid-fourth ISI interval. The ASME code edition and addenda used for the IP2 and IP3 fourth interval is the 2001 Edition, with 2003 a-Addenda. The ASME Code edition and addenda u..d for the, P3 third intor.al- iho 08 E with no addonda.

4. Detection of Aging Effects (last paragraph)

F-r b9th 122 ad 11P3, AticIe IWE of ASME Stio;n XI, 1980 Editior, d*es not contain any specific exemption crite-ria forF component ao ac1nrda in nc with thin cnritoria supports.

lonti*nmd Cdol in Components eXempt fFGroexmntn N. 11 2, Alternate ,ules for Examination of Class 1,2, 3 and MG ComponRent Supports of Light-%Watelr Cooled Power PlantI, SoctiOn XI, DIViionu 1, IWF 1230.

Section B.1.31 is revised as follows:

B.1.31 Reactor Vessel Head Penetration Inspection Program Description The Reactor Vessel Head Penetration Inspection Program is an existing program that manages primary water stress corrosion cracking (PWSCC) of nickel-based alloy reactor vessel head penetrations exposed to borated water to ensure that the pressure boundary function is maintained. This program was developed in response to NRC Order EA-03-009 and it is maintained in accordance with the requirements of 10CFR50.55a(q)(6)(ii)(D). The ASME Section X', Subsection IWB Inservice Inspection and Water Chemistry Control Programs are used in conjunction with this program to manage cracking of the reactor vessel head penetrations. Detection of cracking is accomplished through implementation of a combination of bare metal visual examination (external surface of head) and non-visual examination (underside of head) volumetric and surface techniques. Procedures are developed to perform reactor vessel head bare metal inspections and calculations of the susceptibility ranking of the plant.

IPEC will continue to implement commitments associated with (1) NRC Orders, Bulletins and Generic Letters associated with nickel alloys and (2) staff-accepted industry guidelines.

NL-10-076 Docket Nos. 50-247 and 50-286 Attachment 1 Page 5 of 5 Clarification of B.1.28, One-Time Inspection - Small Bore Piping During recent LRA reviews, NRC staff has questioned applicants whether volumetric examinations are performed for inspection of small-bore socket welds.

IPEC performs volumetric examination of small-bore socket welds under the Inservice Inspection Program. Under category R-A (risk informed) periodic volumetric examinations of small-bore socket welds are performed. During the IP2 fourth ISI interval, IPEC performed volumetric examinations on 2 socket welds. During the IP3 third ISI interval that ended July 20, 2009, IPEC performed 21 socket weld volumetric examinations. Periodic volumetric examinations of socket welds will continue during each ISI interval through the period of extended operation. Specifically, IP2 and IP3 plan to perform examinations consistent with the requirements of an NRC approved Risk Informed ISI program, but no less than 6 examinations at each plant during the fourth ISI interval. No indications have been discovered during any of these socket weld examinations at IPEC.

The examination method is a volumetric examination of the base metal 1/2" beyond the toe of the socket fillet weld using qualified ultrasonic examination techniques as close as possible to the fillet weld. The volumetric examinations are performed by certified examiners following guidelines set forth in ASME Section V, Article 4 consistent with the guidelines for examination volume of 1/2" beyond the toe of the weld as established in MRP-146, "Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-isolable Reactor Coolant System Branch Lines."

Regarding related operating experience with socket welds, on March 18, 2010 Entergy discovered boric acid adjacent to a 3/4 inch valve in the reactor coolant system. After cleaning, a surface examination was performed on the socket weld attaching the upstream pipe to the valve. The surface examination identified a 5/16 inch diameter rounded indication as the leakage source. The failure was determined to be a minor weld defect introduced at the time of system construction that propagated through wall as a result of system loading conditions during plant operation. No linear indications were found during the surface examination of this weld. The indication was repaired and post maintenance examination confirmed successful removal of the indication and acceptable repair.

(Reference LER #2010-004-00 dated May 14, 2010)