NL-07-145, Reply to Request for Additional Information, Regarding License Renewal Application

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Reply to Request for Additional Information, Regarding License Renewal Application
ML073470241
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 12/06/2007
From: Dacimo F
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-145
Download: ML073470241 (6)


Text

SEntergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President December 6, 2007 Re: Indian Point Units 2 & 3 Docket Nos. 50-247 & 50-286 NL-07-145 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Reply to Request for Additional Information Regarding License Renewal Application

Reference:

NRC letter dated November 9, 2007; "Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application"

Dear Sir or Madam:

Entergy Nuclear Operations, Inc is providing, in Attachment I, the additional information requested in the referenced letter pertaining to NRC review of the License Renewal Application for Indian Point 2 and Indian Point 3. The additional information provided in this transmittal addresses staff questions regarding HVAC and Containment Systems.There are no new commitments identified in this submittal.

If you have any questions or require additional information, please contact Mr. R. Walpole, Manager, Licensing at (914) 734-6710.I declare under penalty of perjury that the foregoing is true and correct. Executed on __/_"-.S Fred R. Dacimo Site Vice President Indian Point Energy Center cc: next page NL-07-145 Docket 50-247 & 50-286 Page 2 of 2 cc: Mr. Bo M. Pham, NRC Environmental Project Manger Ms. Kimberly Green, NRC Safety Project Manager Mr. John P. Boska, NRC NRR Senior Project Manager Mr. Samuel J. Collins, Regional Administrator, NRC Region I Mr. Mark Cox, NRC Senior Resident Inspector, IP2 Mr. Paul Cataldo, NRC Senior Resident Inspector, IP3 Mr. Paul D. Tonko, President, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service ATTACHMENT I TO NL-07-145 REPLY TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE RENEWAL APPLICATION (HVAC and Containment Systems)ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 and 3 DOCKETS 50-247 and 50-286 NL-07-145 Attachment I Page 1 of 3 INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION (LRA)REQUESTS FOR ADDITIONAL INFORMATION (RAI)The U.S. Nuclear Regulatory Commission (NRC or staff) has reviewed the information related to the HVAC and Containment Systems provided by the applicant in the Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3) LRA. The staff has identified that additional information is needed to complete the review as addressed below.RAI 2.3A.1.3-1 The reactor coolant pressure boundary for Unit 2 is depicted on license renewal drawing LRA-9321-2738, under systems "Pressurizer' and "Reactor Coolant, Sheet 1" as denoted in page 2.3-20. Please clarify if there are any additional sheets depicting the reactor coolant pressure boundary, and if so, where they can be found in the LRA submittal.

If they have not already been provided, please provide the drawing(s) to the staff.Response for RAI 2.3A.1.3-1 The term "Sheet 1" in the first column of the drawing listing on page 2.3-20 of the LRA is unnecessary since there is only one sheet for drawing LRA-9321-2738.

Drawing LRA-9321-2738 identifies the major components in the reactor coolant system for Unit 2 and includes the reactor vessel, pressurizer, reactor coolant pumps and steam generators.

The remaining reactor coolant pressure boundary components for IP2 and IP3 that are in scope and subject to aging management review are shown on the other LRA drawings listed on Page 2.3-20.Continuations of lines to the other drawings depicting portions of the reactor coolant pressure boundary are shown on drawing LRA-9321-2738.

RAI 2.3A.2.3-1 License renewal drawing LRA-9321-2726 (LRA page 2.3-63) depicts the "Penetration and Liner Weld Joint Channel Pressurization System." The drawing contains several line mounted components denoted by component numbers PRV PCV 1193 through PRV PCV 1200. Though the subject components are located in lines with a pressure boundary function, the components themselves are not highlighted.

Clarify whether these components are within the scope of license renewal in accordance with 10 CFR 54.4(a), and subject to aging management review (AMR) in accordance with 10 CFR 54.21 (a)(1). If they are excluded from the scope of license renewal and not subject to AMR, provide justification for the exclusion.

NL-07-145 Attachment I Page 2 of 3 Response for RAI 2.3A.2.3-1 These components are in the scope of license renewal and subject to aging management review. PRV-PCV-1 193 through PRV-PCV-1200 are in LRA table 2.3.2-3-1P2 as component type "valve body" with aging management review results in LRA table 3.2.2-3-1P2.

The material.is stainless steel for PRV-PCV-1 194/ 1196/ 1198/ 1200 and environments are "air -indoor (ext)" and "gas (int)". The following line item for aluminum valve bodies is added to LRA table 3.2.2-3-IP2 for PRV-PCV-1193/

1195/ 1197/ 1199.Valve Pressure Aluminum Air-treated None None V.F-2 3.2.1- C, 301 body boundary (int) (EP-3) 50 RAI 2.3B.2.3-1 The-containment isolation support systems are described in LRA Section 2.3.2.3 and depicted on several license renewal drawings listed in LRA Section 2.3.2.3. License renewal drawing LRA-9321-27463 displays "Isolation Valve Seal Water System." The drawing contains two components, PCV 1076 and PCV 1090, which are in the pressure boundary.

The components are highlighted indicating that the components are subject to an AMR; however, the sensing lines connecting these components to the main line are not highlighted.*

Please provide additional information to describe what these components are, their intended function, and why the sensing lines are not subject to an AMR.Response for RAI 2.3B.2.3-1 The components in question are sensing lines for valves PCV-1 076 and PCV-1090 that provide a control function for operation of the valves. These sensing lines are internal to the valve bodies even though they are shown on the drawing as a separate component.

The sensing lines are in scope and subject to aging management review. Because these sensing lines are internal to the valve body they are included in the component type "valve body" in LRA table 2.3.2-3-1P3 with aging management review results provided in LRA table 3.2.2-3-1P3.

The valve body material is stainless steel with environments of "air -indoor (ext)" and "gas (int)".RAI 2.3B.2.3-2 License renewal drawing LRA-9321-27263 (LRA page 2.3-63) depicts the "Penetration and Liner Weld Joint Channel Pressurization System." The drawing contains several line mounted components in the 3/8" stainless steel tubing associated with component numbers PCV 1193 through PCV 1199. Though the subject components are located in lines with a pressure boundary function, the components themselves are not highlighted.

Clarify whether these components are within the scope of license renewal in accordance with 10 CFR 54.4(a), and subject to AMR in accordance with 10 CFR 54.21(a)(1).

If they are excluded from the scope of license renewal and not subject to AMR, provide justification for the exclusion.

NL-07-145 Attachment I Page 3 of 3 Response for RAI 2.3B.2.3-2 The components in the 3/8" stainless steel tubing are associated with PCV-1 193/1195/1197 and PCV-1 199 on drawing LRA-9321-27263.

The components are aluminum pressure regulator valves. These components are in scope and subject to aging management review.The following line items are added to LRA table 3.2.2-3-1P3.

ilve Pressure Aluminum Air- indoor None None V.F-2 3.2.1-50 C)dy boundary (ext) (EP-3)dive Pressure Aluminum Air-treated None None V.F-2 3.2.1-50 C)dy boundary (int) (EP-3) 3(RAI 2.3A.2.5-1 License renewal drawing LRA-9321-72043 depicts the "Reactor Vessel Instrumentation System." This drawing was referenced for Unit 2. No similar system drawing was referenced for Unit 3. It appears that the referenced drawing under Unit 2 is actually applicable to Unit 3, and the correct drawing for Unit 2 should be LRA-208798.

Please confirm the correctness of the referenced drawings, and if necessary, revise this section accordingly.

Response for RAI 2.3A.2.5-1 An administrative error occurred when transferring the LRA drawing numbers from the site basis document to the LRA drawing list on page 2.3-63. LRA drawing, LRA-9321-72043 is a Unit 3 drawing. Additional drawings applicable to Unit 2 are LRA-208798 and LRA-9321-2738.