ML073180252

E-mail: Draft RAIs for Containment and HVAC Systems

ML073180252
Person / Time
Site:	Indian Point
Issue date:	10/19/2007
From:	Kimberly Green NRC/NRR/ADRO/DLR
To:	Tyner D Entergy Nuclear Operations
References
Download: ML073180252 (4)

Text

IPNonPublicHearingFile - Draft RAIs for Containment and HVAC Systems Page 1 From: Kimberly Green To: dtyner@entergy.com Date: Fri, Oct 19, 2007 4:23 PM

Subject:

Draft RAIs for Containment and HVAC Systems Donna, Attached are draft requests for additional information related to the Indian Point license renewal application. Please review and provide me with a couple of possible times for a telecon to discuss. The purpose of the telecon will be to obtain clarification on the staff's questions.

Thanks, Kim Green U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop O11 F1 Rockville, Maryland 20852-2738 phone: 301-415-1627 fax: 301-415-3313 email: kjg1@nrc.gov CC: Bruce Heida; IPNonPublicHearingFile; MICHAEL D STROUD; Nageswara Karipineni; Rajender Auluck; Rani Franovich

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Draft RAIs for Containment and HVAC Systems Creation Date Fri, Oct 19, 2007 4:23 PM From: Kimberly Green Created By: KJG1@nrc.gov Recipients entergy.com dtyner (dtyner@entergy.com)

MSTROUD CC (MICHAEL D STROUD) nrc.gov OWGWPO01.HQGWDO01 RCA CC (Rajender Auluck) nrc.gov OWGWPO02.HQGWDO01 BRH1 CC (Bruce Heida)

RLF2 CC (Rani Franovich) nrc.gov TWGWPO03.HQGWDO01 IPNonPublicHearingFile CC (IPNonPublicHearingFile)

NRK1 CC (Nageswara Karipineni)

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Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application Draft Request for Additional Information Set 4 Containment and HVAC Systems DRAI 2.3.1.3-1 The Reactor Coolant Pressure Boundary for Unit 2 is depicted on LRA 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 are not already in the submittal, please provide the drawing(s) to the NRC staff.

DRAI 2.3.2.3-1 (A) The Containment Isolation Support Systems (CISS) 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-F-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 aging management review (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.

(B) License renewal drawing LRA-9321-2726 (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 10CFR 54.4(a), and subject to AMR in accordance with 10CFR 54.21(a)(1). If they are excluded from the scope of license renewal and not subject to AMR, provide justification for the exclusion.

DRAI 2.3.2.5-1 The containment penetrations covered in this section are a grouping of containment penetration components not evaluated with other systems. The scope of the evaluation in this section is passive mechanical components not evaluated in other system evaluations. The evaluation in this section includes only the containment penetration portion of these systems. The applicable systems were described in this section because their only intended function is performed by a containment penetration.

(A) License renewal drawing LRA-9321-2027 referenced for Unit 2 depicts the containment penetration portion of steam supply and condensate return from various nuclear services and unit heaters. This system is not described in LRA section 2.3.2.5 or elsewhere in the LRA.

Please provide a brief description of this system, including the license renewal intended functions.

(B) 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 required, revise this section accordingly.