ML090890782

From kanterella
Revision as of 01:52, 12 July 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Duke Energy - Submittal of Relief Request 09-GO-001 to Propose Alternative Examination for Certain Buried Components of the Condenser Circulating Water at Oconee, McGuire and Catawba Nuclear Station
ML090890782
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 02/24/2009
From: Brandi Hamilton
Duke Energy Carolinas, Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RR 09-GO-001
Download: ML090890782 (30)


Text

kDuke aEnergyFebruary 24, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUCE H HAMILTON Vice President McGuire Nuclear Station Duke Energy Corporation MG01 VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.

com

SUBJECT:

Duke Energy Carolinas, LLC (Duke)Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287 McGuire Nuclear Station, Units 1 and 2 Docket Numbers 50-369 and 50-370 Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Relief Request 09-GO-001 Pursuant to 10 CFR 50.55a(a)(3)(i), Duke hereby submits Relief Request 09-GO-001 to propose alternative examination for certain buried components of the Condenser Circulating Water System at Oconee Nuclear Station and Nuclear Service Water Systems at McGuire and Catawba Nuclear Stations in lieu of system pressure tests as required by ASME Section Xl, IWA-5244(b).

The enclosure to this letter contains this relief request. If you have any questions or require additional information, please contact P. T. Vu at (704) 875-4302.Sincerely, Bruce H. Hamilton Enclosure 44-oc7 k-14 www. duke-energy.

corn U. S. Nuclear Regulatory commission February 24, 2009 Page 2 xc: L. A. Reyes, Region II Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St., SW Atlanta, GA 30303-8931 J. H. Thompson, Project Manager U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2738 J. F. Stang, Jr., Senior Project Manager U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2738 G. A. Hutto NRC Senior Resident Inspector Oconee Nuclear Station J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station A. T. Sabisch NRC Senior Resident Inspector Catawba Nuclear Station Enclosure Duke Energy Corporation Oconee Nuclear Station, Units 1, 2, and 3 McGuire Nuclear Station, Units 1 and 2 Catawba Nuclear Station, Units I and 2 Relief Request Serial # 09-GO-001 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) for Pressure Testing Buried Components of the Condenser Circulating and Nuclear Service Water Systems Duke Energy Corporation Oconee Nuclear Station, Units 1, 2, and 3 McGuire Nuclear Station, Units I and 2 Catawba Nuclear Station, Units 1 and 2 Relief Request Serial #09-GO-001 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) for Pressure Testing Buried Components of the Condenser Circulating and Nuclear Service Water Systems Duke Energy Corporation Relief Request Serial #09-GO-001 Page 2 of 11 1. ASME Code Component(s)

Affected 1.1.Oconee Nuclear Station, Uhits 1, 2, and 3 ASME Class 3 Condenser Circulating Water (CCW) System buried piping bounded by valves listed in Table 1. Separate sections of buried piping are listed in the table, and are identified below.Note: Copies of referenced Flow Diagrams are included in Attachment C. The designation "EM" on the flow diagrams refers to portions of components that are embedded in concrete.Buried Piping Section 1 consists of 42", 36", 30", 18", 12", and 2" diameter piping from CCW Intake Pumps 1A, 1B, 1C, ID, 2A, 2B, 2C, and 2D bounded by valves listed in Table 1.Buried Piping Section 2 consists of 42", 36", 30", and 14" diameter piping from CCW Intake Pumps 3A, 3B, 3C, and 3D, bounded by valves listed in Table 1.Table 1 Buried Piping Valve Flow Diagram Drawing Valve Section Number Drawing Number Coordinate Type 1 1CCW-40 OFD-133A-1.1 D-9 Butterfly 1 CCW-72 OFD-133A-1.1 E-1 1 Butterfly 1 CCW-73 OFD-133A-1.1 E-12 Butterfly 1 1CCW-92 OFD-133A-1.4 E-1 Butterfly 1 2CCW-41 OFD-133A-2.1 D-7 Butterfly 1 3CCW-42 OFD-133A-3.1 E-10 Butterfly 1 3CCW-323 OFD-133A-3.1 E-10 Gate 1 3CCW-466 OFD-133A-3.1 D-10 Gate 1 3CCW-468 OFD-133A-3.1 D-10 Ball 2 3CCW-42 OFD-133A-3.1 E-10 Butterfly 2 3CCW-94 OFD-133A-3.1 E-7 Butterfly 2 3CCW-341 OFD-133A-3.1 D-8 Gate 2 3LPSW-120 OFD-124A-3.1 J-2 Gate 2 3LPSW-123 OFD-124A-3.1 G-2 Gate Duke Energy Corporation Relief Request Serial #09-GO-001 Page 3 of 11 1.2. McGuire Nuclear Station, Units 1 and 2 ASME Class 3 Nuclear Service Water (RN) System buried piping bounded by valves listed in Table 2. Separate sections of buried piping are listed in the table, and are identified below.Note: Copies of referenced Flow Diagrams are included in Attachment D.Buried Piping Section 1 consists of 42" and 36" diameter piping from Low Level Intake Cooling Water (RC) System at valve #1 RN0001 to Containment Ventilation Cooling Water System (RV) Pumps at valve #ORN0301AC and to Crossover piping at valves #ORN0012AC (Train "A") and #ORN0010AC (Train"B").Buried Piping Section 2 consists of 36" diameter piping from the Standby Nuclear Service Water Pond at valve #ORN0007A to Train "A" Nuclear Service Water Strainers at valves #1 RN0016A and #2RN0016A, and to 36" diameter crossover piping connecting to Train "B" at valves #ORN0013A and #ORN0014A.

Buried Piping Section 3 consists of 36" diameter piping from the Standby Nuclear Service Water Pond at valve #ORN0009B to Train "B" Nuclear Service Water Strainers at valves #1 RN001 8B and #2RN001 8B, and to 36" diameter crossover piping connecting to Train "A" at valves #ORN001 1 B and #ORN001 5B.Table 2 Buried Valve Flow Diagram Drawing Valve Type Piping Number Drawing Number Coordinate Section 1 ORN0010AC MCFD-1574-01.00 F-10 Butterfly 1 ORN0012AC MCFD-1574-01.00 1-10 Butterfly 1 ORN0301AC MCFD-1574-01.00 F-9 Butterfly 1 1RN0001 MCFD-1574-01.00 1-9 Butterfly 1 1RN0813 MCFD-1574-01.00 H-9 Globe 1 1RN0814 MCFD-1574-01.00 H-10 Globe 1 1RN0815 MCFD-1574-01.00 H-9 Globe 1 1RN0844 MCFD-1574-01.00 1-10 Globe 1 1RN0846 MCFD-1574-01.00 G-11 Globe 2 ORN00013A MCFD-1574-01.00 J-10 Butterfly 2 ORN0003A MCFD-1574-01.00 K-9 Butterfly 2 ORN0007A MCFD-1574-01.00 J-9 Butterfly 2 ORN0014A MCFD-1574-01.00 1-13 Butterfly 2 ORN1051 MCFD-1574-01.00 J-13 Ball 2 1RN0861 MCFD-1574-01.00 J-10 Globe 2 1RN00016A MCFD-1574-01.01 J-2 Butterfly Duke Energy Corporation Relief Request Serial #09-GO-001 Page 4 of 11 Table 2 Buried Valve Flow Diagram Drawing Valve Type Piping Number Drawing Number Coordinate Section 2 1RN0830 MCFD-1574-01.01 J-2 Globe 2 2RN0016A MCFD-2574-01.01 J-2 Butterfly 2 2RN0817 MCFD-2574-01.01 J-2 Globe 3 ORN0005B MCFD-1574-01.00 F-11, Butterfly 3 ORN0009B MCFD-1574-01.00 D-9 Butterfly 3 ORN0011B MCFD-1574-01.00 F-10 Butterfly 3 ORN0015B MCFD-1574-01.00 F-13 Butterfly 3 1RN0862 MCFD-1574-01.00 D-12 Globe 3 1RN00018B MCFD-1574-01.01 E-2 Butterfly 3 1RN0831 MCFD-1574-01.01 F-2 Globe 3 2RN0018B MCFD-2574-01.01 E-2 Butterfly 3 2RN0814 MCFD-2574-01.01 F-2 Globe Duke Energy Corporation Relief Request Serial #09-GO-001 Page 5 of 11 1.3. Catawba Nuclear Station, Units 1 and 2 ASME Class 3 Nuclear Service Water (RN) System buried piping bounded by valves listed in Table 3. Separate sections of buried piping are listed in the table, and are identified below.Note: Copies of referenced Flow Diagrams are included in Attachment E.Buried Piping Section 1 consists of 42", 36", and 10" diameter piping from Nuclear Service Water Pumps 1A and 2A at valves #1 RN29 and #2RN29 to the Diesel Generator Cooling Water Supply Headers 1A and 2A, and to the Auxiliary Building where RN System Train "A" connects to other systems.Buried Piping Section 2 consists of 42", 36", and 10" diameter piping from Nuclear Service Water Pumps 1 B and 2B at valves #1 RN39 and #2RN39 to the Diesel Generator Cooling Water Supply Headers 1 B and 2B, and to the Auxiliary Building where RN System Train "B" connects to other systems.Table 3 Buried Valve Flow Diagram Drawing Valve Type Piping Number Drawing Number Coordinate Section 1 1RN29 CN-1574-1.0 B-4 Butterfly 1 1RN34 CN-1574-1.0 B-4 Butterfly 1 1RN67A CN-1574-1.1 F-9 Butterfly 1 1RN866 CN-1574-1.1 L-12 Globe 1 1RN867 CN-1574-1.1 J-11 Plug 1 1RN899 CN-1574-1.1 1-13 Plug 1 1RN950 CN-1574-1.1 1-13 Ball 1 1RNP03 CN-1574-1.1 J-13 Butterfly 1 1RNP06 CN-1574-1.1 K-13 Butterfly 1 1RNP21 CN-1574-1.1 F-8 Butterfly 1 1RNP33 CN-1574-1.1 G-9 Ball 1 1RNP34 CN-1574-1.1 F-8 Ball 1 1RNP40 CN-1574-1.1 F-12 Ball 1 1RNP41 CN-1574-1.1 G-13 Ball 1 2RN29 CN-1574-1.0 B-9 Butterfly 1 2RN67A CN-1574-1.1 F-13 Butterfly 1 2RN899 CN-1574-1.1 1-9 Plug 1 2RNP03 CN-1574-1.1 J-9 Butterfly 1 2RNP06 CN-1574-1.1 K-9 Butterfly Duke Energy Corporation Relief Request Serial #09-GO-001 Page 6 of 11 Table 3 Buried Valve Flow Diagram Drawing Valve Type Piping Number Drawing Number Coordinate Section 1 2RNP16 CN-1574-1.1 I-8 Ball 1 2RNP21 CN-1574-1.1 F-12 Butterfly 2 1RN39 CN-1574-1.2 C-4 Butterfly 2 1RN45 CN-1574-1.2 C-4 Butterfly 2 1RN69B CN-1574-1.1 G-2 Butterfly 2 1RN868 CN-1574-1.1 L-5 Globe 2 1RN869 CN-1574-1.1 J-4 Plug 2 1RN898 CN-1574-1.1 1-2 Plug 2 1RN956 CN-1574-1.1 1-2 Ball 2 1RNP02 CN-1574-1.1 J-2 Butterfly 2 1RNP04 CN-1574-1.1 K-2 Butterfly 2 1RNP22 CN-1574-1.1 F-3 Butterfly 2 1RNP35 CN-1574-1.1 G-3 Ball 2 1RNP36 CN-1574-1.1 F-3 Ball 2 1RNP42 CN-1574-1.1 G-7 Ball 2 1RNP43 CN-1574-1.1 G-6 Ball 2 2RN39 CN-1574-1.2 C-10 Butterfly 2 2RN69B CN-1574-1.1 F-6 Butterfly 2 2RN898 CN-1574-1.1 1-6 Plug 2 2RNP02 CN-1574-1.1 J-6 Butterfly 2 2RNP04 CN-1574-1.1 K-6 Butterfly 2 2RNP10 CN-1574-1.1 1-7 Butterfly 2 2RNP22 CN-1574-1.1 F-7 Butterfly Duke Energy Corporation Relief Request Serial #09-GO-001 Page 7 of 11 2. Applicable Code Edition and Addenda ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.3. Applicable Code Requirement The ASME Code, Section Xl, Subsection IWA, IWA-5244(b) specifies examination requirements for buried components where a VT-2 visual examination cannot be performed.

The requirement of IWA-5244(b) is as follows: (b) For buried components where a VT-2 visual examination cannot be performed, the examination requirement is satisfied by the following:

(1) The system pressure test for buried components that are isolable by means of valves shall consist of a test that determines the rate of pressure loss. Alternatively, the test may determine the change in flow between the ends of the buried components.

The acceptable rate of pressure loss or flow shall be established by the Owner.(2) The system pressure test for nonisolable buried components shall consist of a test to confirm that flow during operation is not impaired.4. Reason for Request The requirements of IWA-5244 have been the subject of a number of relief requests and NRC violations, as cited in Sections 7.0 and 8.0 of this request. The alternative proposed in this request will eliminate the risk of misinterpreting (or misapplying) the requirements of either IWA-5244(b)(1) or IWA-5244(b)(2), and will eliminate or minimize the risk of receiving additional NRC violations for non-compliance with the ASME Code, Section Xl during the current inservice inspection intervals.

The following additional information is provided in support of this request: 1. Catawba recently received a violation for performing an unimpaired flow test on buried portions of the Nuclear Service Water (RN) System during the previous inspection interval in accordance with the requirements of the ASME Code,Section XI, 1989 Edition (Reference 8.6). This violation appears to support the position that licensees must request relief to allow the use of an unimpaired flow test in lieu of either a pressure drop test or a change in flow test.2. Reference 8.8 documents an NRC Inspection at Point Beach Nuclear Plant in which an NRC Inspector documented a position that Point Beach failed to meet the requirements of the ASME Code, Section Xl, IWA-5244 (1998 Edition through the 2000 Addenda).

This NRC Inspection Report supports the need to seek relief from the requirement of IWA-5244(b)(1) of the 1998 Edition through the 2000 Addenda, to allow the use of IWA-5244(b)(2) for buried components.

Duke Energy Corporation Relief Request Serial #09-GO-001 Page 8 of 11 3. ASME has issued the following interpretations pertaining to IWA-5244: a. On November 21, 2007, ASME issued an interpretation that clarified examination requirements specified in IWA-5244(b)(2).

This inquiry (ASME File #1N07-09), and ASME's response, is included as Attachment A to this request. Using this interpretation would require a licensee to comply with IWA-5244(b)(2) when testing buried components with valves that are not capable of isolating the portion of the component under test. The test required by IWA-5244(b)(2) is a test to confirm that flow during operation is not impaired.

Complying with IWA-5244(b)(2)

[which ASME has stated is required when following the 1998 Edition with the 2000 Addenda], could subject Oconee, McGuire, and Catawba Nuclear Stations to potential NRC violations during the current inservice inspection intervals which use the 1998 Edition through the 2000 Addenda of the ASME Code,Section XI.b. On October 14, 2008, ASME issued an interpretation pertaining to the intent of IWA-5244(b)(1) as it applies to buried components with butterfly valves that are not designed to be leak-tight.

This inquiry (ASME File #08-701), and ASME's response, is included as Attachment B to this request. This interpretation supports the position that buried components with butterfly valves that are not leak-tight should receive an unimpaired flow test.Approval of the alternative in this request will clarify the examination requirements for buried components of the Condenser Circulating and Nuclear Service Water Systems subject to examination in accordance with IWA-5244(b) for the current inservice inspection intervals at Oconee, McGuire, and Catawba Nuclear Stations.5. Proposed Alternative and Basis for Use In lieu of performing a system pressure test in accordance with the requirements of IWA-5244(b) for buried components of the Condenser Circulating Water (CCW) System at Oconee and Nuclear Service Water (RN) Systems at McGuire and Catawba identified in Section 1 of this request, Duke proposes the following alternative in accordance with 1 OCFR50.55a(a)(3)(i):

(1) A test that confirms that flow during operation is not impaired (unimpaired flow test) shall be performed.

(2) A visual examination of the ground surface areas (includes surfaces of asphalt or other pavement materials) above components buried in soil shall be performed during all current and subsequent inspection periods to detect evidence of through-wall leakage in the buried components.

This visual examination shall be performed during the unimpaired flow test, or may be performed at any time after the buried component has been in operation at nominal operating conditions for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Duke Energy Corporation Relief Request Serial #09-GO-001 Page 9 of 11 The basis for the proposed alternative is as follows: Neither the change in flow test [IWA-5244(b)(1)]

nor the unimpaired flow test [IWA-5244(b)(2)]

are sufficiently sensitive to detect small through-wall leakage in these buried components, due to relatively high system flow rates and accuracy of flow measurement instrumentation.

As such, there is no appreciable difference between the level of quality and safety achieved by performing either of these tests.Visual examinations of ground surface areas are capable of detecting potentially small through-wall leakage in the buried component.

These visual examinations and unimpaired flow tests will provide reasonable assurance of the structural and leak-tight integrity of the buried components.

For these reasons, the proposed alternative to IWA-5244 provides an acceptable level of quality and safety for buried components of the Condenser Circulating Water (CCW)System at Oconee and. Nuclear Service Water (RN) Systems at McGuire and Catawba.6. Duration of Proposed Alternative The proposed alternative is requested for use during the following inservice inspection intervals:

Station Unit ISl Interval Interval Start Date Interval End Date Number (Tentative)

Oconee 1 4 January 1, 2004 July 14, 2013 Oconee 2 4 September 9, 2004 September 8, 2014 Oconee 3 4 January 2, 2005 December 15, 2014 Catawba 1 3 June 29, 2005 June 28, 2015 Catawba 2 3 October 15, 2005 August 19, 2016 McGuire 1 3 December 1, 2001 November 30, 2011 McGuire 2 3 March 1, 2004 February 28, 2014 7. Related Industry Relief Requests Relief from the requirements of IWA-5244 (for various ASME Code Editions/Addenda) has been granted to other licensees, as documented in the following relief requests.Please note that the basis for Duke's relief request is not identical to any of the cited requests listed below.7.1. Millstone Power Station, Units 2 and 3, Relief Request #1R-2-40, #RR-89-57, and#IR-2-41, Approved July 10, 2008, TAC Nos. MD7732 and MD7733.7.2. Vermont Yankee Nuclear Power Station, Relief Request #ISI-PT-01, Approved January 31, 2008, TAC No. MD5436.

Duke Energy Corporation Relief Request Serial #09-GO-001 Page 10 of 11 7.3. Duane Arnold Energy Center, Relief Request #NDE-R007, Approved June 12, 2007, TAC No. MD2523.7.4. Prairie Island Nuclear Generating Plant, Units 1 and 2, Relief Request #1-RR-4-7 and #2-RR-4-7, Approved October 31, 2007, TAC Nos. MD3809 and MD3810.7.5. Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, Relief Requests #13R-07 and #12R-46, Approved January 16, 2007, TAC Nos. MD1757, MD1758, MD1759, MD1760.7.6. Cooper Nuclear Station, Relief Request #PR-06, Approved October 2, 2006, TAC No. MD0286.7.7. Brunswick Steam Plant, Relief Request #RR-1 1 SER, Dated February 17, 2000, TAC Nos. MA2108 and MS2109.8. References 8.1. Letter from ASME to M. J. Ferlisi, Dated November 21, 2007, issuing interpretation pertaining to requirement of IWA-5244(b)(2).

Reference File #1N07-09 (Attachment A).8.2. Letter from ASME to J. M. Boughman, Dated October 14, 2008, issuing interpretation pertaining to requirement of IWA-5244(b)(1). (Attachment B).8.3. Oconee Flow Diagrams for Condenser CirculatingWater (CCW) System (Attachment C): 8.3.1. #OFD-124A-3.1 8.3.2. #OFD-133A-1.1 8.3.3. #OFD-133A-1.4 8.3.4. #OFD-133A-2.1 8.3.5. #OFD-133A-3.1 8.4. McGuire Flow Diagrams for Nuclear Service Water (RN) System (Attachment D): 8.4.1. #MCFD-1574-01.00 8.4.2. #MCFD-1574-01.01 8.4.3. #MCFD-2574-01.01 8.5. Catawba Flow Diagrams for Nuclear Service Water (RN) System (Attachment E): 8.5.1. #CN-1574-1.0 8.5.2. #CN-1574-1.1 8.5.3. #CN-1574-1.2 Duke Energy Corporation Relief Request Serial #09-GO-001 Page 11 of 11 8.6. Catawba Nuclear Station -NRC Integrated Inspection Report 05000413/2007005 and 05000414/2007005, Dated January 31, 2008.8.7. NRC Letter Dated January 31, 2008 to Mr. David Baxter, Vice President, Oconee Nuclear Station, Oconee Integrated Inspection Report.Activity #40A7 in this report documents a Licensee Identified Violation of very low significance related to compliance with the requirements of IWA-5244.

It should be noted that there are two errors in this report, as follows: 1. The 1998 Edition of the ASME Code,Section XI was cited. The correct Code of record for this violation should have been the 1989 Edition.2. PIP #0-07-06007 was cited, instead of PIP #0-07-05502.

8.8. Point Beach Nuclear Plant, Units 1 And 2 NRC Safety System Design And Performance Capability Inspection 05000266/2004004(DRS);

05000301/2004004(DRS), Dated September 7, 2004.

Duke Energy Corporation Relief Request Serial #09-GO-001 Attachment A, Page 1 of 1 CODES~ & TAD?,xIrJ Novernbei 21 2007 Mark J. Ferlisi, PE.Senior Engineer Ouke Eneigy Corporation Nuclear Generation Dept Po Box 1006 Charlotte, NL zd2w11IoUb

Subject:

ASME BPVC Section X!, iWA-5244, 1995 Edition with the 1995 Addenda through the 2007 File #: IN07-09

Dear Mr. Ferlisi:

Cur understanding of the question in your letter and cur reply is as follows: Question:

Does the requirerment of IWA.5244(b).i2) app4y to buried Components with valves that are not capable of isolating the porilon of the componont under test?Reply: Ye", Sinceirely, Ryan L. Crane, P.E.Secretary, SC Xl Interpretation Committee (212) 591-7004 FAX: (212)-591-8501 craner~asmeo ng CC: Joel Feldstein Thomas Pastor Gary Park Rick Sayne Duke Energy Corporation Relief Request Serial #09-GO-001 Attachment B, Page 1 of 1 Three P3 k Avenue Krfl I, I212.591.8500 ENew Yokri., NY 1a.m12.511 USD SFTTJW4 TAF ;IFAOARD ID0r-5~ .. w.nce CODES & STANDARDS October 14, 2008 James M. Boughman Pressure Test Program Owner Duke Energy PO Box 1006 -EC05A Charlotte, NC 28201-1006

Subject:

ASME BPVC Section XI, IWA-5244, 1995 Edition through the 2007 Edition with the 2008 Addenda File W: 08-701 (previously 08-416)

Dear Mr. Boughman:

Our understanding of the question in your letter and our reply is as follows: Question:

Is it the intent of IWA-5244(b)(1) that the configuration of isolable by means of valves apply to buried components with Butterfly valves that are not designed to be leak-tight?

Reply: No.Sincerely, Ryan L. Crane, P.E.Secretary, SC Xl I terpretailon Committee (212) 591-7004 FAX: (212)-591-8501 craneraasme.or0 CC: Joel Feldstein Thomas Pastor Gary Park Rick Swayne r-tkh 111t irr4, irr ults migm wi s a$ W'!p ircreloirmFnn f 'et c no ufj'rue$ by INS intntbrctltinmy 40W1t~ WC Oth r+/-5riksrt ASME rsnriitite Wr iuk- trnitottASAt osd iA iht Thototef Or itk ewet tXVrtla*ASME &Me nut lupowe,' "errrfyf 'rate.' or ýnrdnne' art item ocnrurtinn.

prurprietary devxr o, act~ity, Duke Energy Corporation Relief Request Serial #09-GO-001 Attachment C -Oconee Flow Diagrams for Condenser Circulating Water (CCW) System and Low Pressure Service Water System Page 1 of 6 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. OFD-124A-3.1,EV.

33"FLOW DIAGRAM OF LOW PRESSURE SERVICE WATER SYSTEM TURBINE BLDG.(LOW PRESSURE SERVICE WATER PUMPS." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-01 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. OFD-133A-1.1 REV. 28"FLOW DIAGRAM OF CONDENSER CIRCULATING WATER SYSTEM, (CCW INTAKE PUMPS DISCHARGE)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-02 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. OFD-133A-1.4, REV. 25"FLOW DIAGRAM OF CONDENSER CIRCULATION WATER SYSTEM, (RCW COOLERS)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-03 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. OFD-133A-2.1, REV. 26"FLOW DIAGRAM OF CONDENSER CIRCULATING WATER SYSTEM, (CCW INTAKE PUMPS DISCHARCH)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-04

.THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. OFD-133A-3.1, REV. 33"FLOW DIAGRAM OF CONDENSER CIRCULATING WATER SYSTEM, (CCW INTAKE PUMPS DISCHARGE)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-05 Duke Energy Corporation Relief Request Serial #09-GO-001 Attachment E- Catawba Flow Diagrams for Nuclear Service Water (RN) System Page 1 of 4 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. CN-1574-1.0, REV. 52"FLOW DIAGRAM OF NUCLEAR SERVICE WATER SYSTEM, (RN)" WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-06 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. CN-1574-1.1 REV. 49"FLOW DIAGRAM OF NUCLEAR SERVICE WATER SYSTEM (RN)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-07 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. CN-1574-1.2, REV. 49"FLOW DIAGRAM OF NUCLEAR SERVICE WATER SYSTEM (RN)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-08 Duke Energy Corporation Relief Request Serial #09-GO-001 Attachment D -McGuire Flow Diagrams for Nuclear Service Water (RN) System Page 1 of 4 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. MCFD-1574-01.00 REV. 7"FLOW DIAGRAM OF NUCLEAR SERVICE WATER SYSTEM, (RN)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-09 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. MCFD-1574-01.01, REV. 15"FLOW DIAGRAM OF NUCLEAR SERVICE WATER SYSTEM (RN)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-10 THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED: DWG. NO. MCFD-2574-01.01, REV. 13"FLOW DIAGRAM OF NUCLEAR SERVICE WATER SYSTEM (RN)." WITHIN THIS PACKAGE...

OR BY SEARCHING USING THE D-11