RA-20-0036, Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping

Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping

ML20062G131
Person / Time
Site:	Oconee
Issue date:	03/02/2020
From:	Burchfield J Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-20-0036
Download: ML20062G131 (15)

Text

£ DUKE

 ENERGY Serial: RA-20-0036 March 02, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 OCONEE NUCLEAR STATION, UNITS NO. 1 AND 2 J. Ed Burchfield, Jr.

Vice President Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672

0. 864. 873. 3478 f 864. 873.4208 Ed. Burchfield@duke-energy.com 10 CFR 50.55a DOCKET NO. 50-269 AND 270 / RENEWED LICENSE NO. DPR-38 AND DPR-47

SUBJECT:

Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW)

System Piping Pursuant to 10 CFR 50.55a(z)(2), Duke Energy Carolinas, LLC (Duke Energy) requests the NRC to grant relief from Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for Oconee Nuclear Station, Units 1 and 2 (Oconee).

Relief is being sought due to the hardship, with no compensating increase in quality or safety, caused by performing a repair/replacement activity in accordance with the ASME Code requirements applicable to Oconee's fifth ISi Interval. This Relief Request addresses the need to encapsulate a thru-wall leak in Low Pressure Service Water (LPSW) system piping shared by Units 1 and 2.

In accordance with ASME Code Case N-513-3, operation with the thru-wall leak through routine monitoring is allowed until the next Unit 1 Refueling Outage (01 R31, fall 2020). Approval of this Request would prevent the need to bring Unit 2 into a forced outage to isolate the piping for leak repair in accordance with ASME Code requirements. Therefore, Duke Energy requests that this Relief Request receive review and approval by August 1, 2020 to support the scheduled Unit 1 Fall refueling outage.

Relief Request RA-20-0036 is provided as an enclosure to this letter. If you have questions concerning this request, please contact Art Zaremba, Director - Fleet Licensing, at (980) 373-2062.

Sincerely, J E;f E-J,MI J J. Ed Burchfield, Jr.

Vice President Oconee Nuclear Station

RA-20-0036 Page 2

Enclosure:

1. Relief Request RA-20-0036

Attachment:

1. Relief Request RA-20-0036 Engineering Change (EC) 416973 Sketch

2. Relief Request RA-20-0036 Oconee Flow Diagram, OFD-124B-1.1 cc :

L. Dudes, Regional Administrator USNRC Region II J. Nadel, USNRC Senior Resident Inspector - ONS A. L. Klett, NRR Project Manager - ONS

RA-20-0036 Page 3 bcc:

Mark Pyne Art Zaremba Austin Keller Kate Nolan David Cummings ELL File: (Corporate)

Ed Burchfield Sheila Dalton Dave Peltola

Duke Energy Carolinas, LLC Oconee Nuclear Station, Units 1 and 2 Relief Request RA-20-0036 (7 pages)

Relief Request in Accordance with 10 CFR 50.55a(z)(2) to use an Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping

RA-20-0036, Page 2 of 7 1.0 ASME CODE COMPONENT(S) AFFECTED:

Oconee Nuclear Station, Units 1 and 2 Low Pressure Service Water (LPSW) System piping listed below:

The 3 inch piping (terminated with a line stop fitting) connected to a 12 inch LPSW header in the Turbine Building Basement, as shown on drawing OFD-124B-1.1 and attached sketch. This piping was constructed to USAS B31.1.0-1967, is classified as ISI Class 3, and is subject to the repair/replacement requirements of the ASME Code,Section XI, IWA-4000. The 12 inch LPSW header is shared between Units 1 and 2 and supplies cooling water to the Component Cooling (CC) Coolers for both Units 1 and 2.

Design data applicable to the above piping is provided below from Duke Energy Specification OSS-0243.00-00-0001 and Oconee Flow Diagram OFD-124B-1.1:

Nominal Wall Thickness: 0.216 inches (3 inch pipe schedule 40)

Design Pressure:

100 psig Design Temperature:

100°F Material Specification:

Carbon Steel, A-106 Gr B 2.0 APPLICABLE CODE EDITION AND ADDENDA:

The ASME Boiler and Pressure Vessel Code,Section XI, 2007 Edition with the 2008 Addenda is used for the Oconee Units 1 and 2, 5th Inservice Inspection Interval.

The 5th Inservice Inspection Interval for Oconee Units 1 and 2 began on July 15, 2014 and is scheduled to end on July 15, 2024.

3.0 APPLICABLE CODE REQUIREMENT:

IWA-4421 requires that defects be removed or mitigated in accordance with IWA-4340, IWA-4411, IWA-4461, or IWA-4462.

[Note: Use of IWA-4340 is prohibited by 10 CFR 50.55a(b)(2)(xxv)]

4.0 REASON FOR REQUEST:

On September 26, 2019 a thru-wall leak was discovered on the LPSW system at a 3 inch branch connection weld to a 12 inch header upstream of 1LPSW-109. The 12 inch header and the 3 inch branch line are both carbon steel piping and located inside the Turbine Building Basement. The 3 inch branch line had previously been

RA-20-0036, Page 3 of 7 removed from service and terminated with a line stop. At the time of discovery, the leakage was measured at 1 drop every two minutes. ASME Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping" was applied to allow continued operation through routine monitoring until the next Unit 1 Refueling Outage (O1R31, Fall 2020).

The 12 inch LPSW header is the common cooling water supply header to the Unit 1 and the Unit 2 Component Cooling (CC) System's heat exchangers (CC Coolers) which provide cooling on the respective Unit for the Reactor Coolant Pump (RCP) seals, High Pressure Injection (HPI) Letdown Coolers, Quench Tank (QT) Cooler, and the Control Rod Drive (CRD) stators. As a result, hydraulic isolation of this header for a code repair of the 3 inch line would only be possible through a forced shutdown of Unit 2 during the Unit 1 Refueling outage, or a forced shutdown of both Unit 1 and Unit 2 prior to the Unit 1 Refueling outage, since this continuous cooling supply is essential to plant operation. For example, Abnormal Procedures AP/1,2/A/1700/020 (Loss of CC) state that CRD stator temperatures will reach 180°F in approximately 4 minutes if CC is lost, resulting in a requirement to trip the reactor.

Additionally, if High Pressure Injection (HPI) letdown temperatures reach 135°F, containment isolation valve HP-5 on that unit will automatically close isolating letdown which would require initiation of a rapid unit shutdown per Abnormal Procedures AP/1,2/A/1700/032 (Loss of Letdown).

Relief is requested from the requirement of IWA-4421 to remove defects in accordance with IWA-4411, IWA-4461, or IWA-4462 on the piping identified in this request, prior to performing repair/replacement activities.

This request is submitted to allow the installation of pressure retaining materials that will be used to encapsulate the thru-wall leak on the 3 inch LPSW piping connected to the 12 inch LPSW header. Installation of replacement pressure retaining materials without first removing the degraded portions of the piping does not comply with the requirement of IWA-4421.

The proposed alternative has been developed because other repair/replacement options that would fully comply with IWA-4421 create a hardship or unusual difficulty without a compensating increase in the level of quality and safety, for the reasons detailed in this request. A fully compliant code repair requires a dual unit shutdown to remove the defect and replace the degraded pipe.

5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE:

Proposed Alternative In lieu of the requirement of IWA-4421 to remove the defective portion of the component prior to performing repair/replacement activities by welding, unacceptable wall thickness loss or thru-wall leakage caused by localized general or pitting corrosion shall be corrected by installation of replacement pressure retaining materials that fully encapsulate the degraded piping. The following requirements shall be met:

RA-20-0036, Page 4 of 7 5.1.1 Replacement pressure retaining materials shall comply with the Construction Code and Owners requirements, as shown in Attachment 1. The modification is being designed such that the piping system no longer relies on the degraded parts for structural integrity or leak tightness. The design pressure and temperature for this portion of the LPSW is 100 psig and 100°F. The outer piping (the encapsulation) is designed based on this pressure and temperature.

5.1.2 The original Construction Code is B31.1-1967. As allowed by ASME Section XI, IWA-4221(c), the encapsulation is procured and designed to B31.1-2007 (in lieu of the original construction code). Welding and Weld NDE requirements are performed per B31.1-2004 (in lieu of the original construction code).

5.1.3 The original 3 inch pipe run had no external supports in the span between the 12 inch header and the line stop. Design analysis of the new configuration did not require the addition of supports.

5.1.4 The locations where the encapsulation is to be welded to the system pressure boundary are located sufficiently far from the 3 inch pipe thru-wall leak to preclude the growth of identified corrosion from challenging the integrity of the encapsulation for the remaining life of the component to which the encapsulation is welded. The 12 inch header pipe will continue to be monitored as part of the Service Water Piping Inspection Program.

5.1.5 An ultrasonic thickness exam utilizing 1" x 1" grids was performed on the 12 inch LPSW header to determine pipe wall thickness in order to evaluate, a) circumferential (hoop) pressure stresses, b) longitudinal (bending) stresses.

a) The lowest thickness reading obtained was 0.215". The minimum required thickness for circumferential (hoop) pressure stress per B31.1 Code is 0.042" (Code Tmin). Therefore, the 12 inch pipe wall thickness was found to be acceptable with respect to circumferential (hoop) pressure stresses.

b) The mill tolerance value for this 12 inch Standard Schedule pipe is 0.328" (i.e., 87.5% of nominal) and the minimum average circumferential wall thickness was found to be 0.335". Therefore, longitudinal (bending) stresses for this pipe header were found to be acceptable.

5.1.6 Prior to installation of replacement pressure retaining materials, ultrasonic thickness measurements shall be re-performed where the encapsulation is to be welded to the 12 inch pipe header to confirm that material thickness has remained adequate for the encapsulation design. The other end of the encapsulation shall be welded to the reinforcing tee of the line stop fitting (See ).

5.1.7 A visual examination shall be performed on welds for the replacement pressure retaining materials in accordance with ASME B31.1-2004, Table 136.4.

5.1.8 A system leakage test shall be performed in accordance with ASME Section XI, 2007 edition with 2008 addenda, IWA-4540, IWA-5000, and IWD-5220 upon completion of the repair/replacement activity to confirm the leak-tight integrity of the modification and its connecting welds to the component pressure boundary.

RA-20-0036, Page 5 of 7 5.1.9 A threaded port in the outer pipe is used to facilitate filling the cavity between the inner pipe and the outer pipe for the inservice leakage test. The system leakage test will be conducted at a normal operating pressure (approximately 80 psig), a fluid temperature 100°F, and a hold time of 10 minutes after attaining test pressure. A pressure gauge shall be used to verify test pressure is achieved.

5.1.10 Upon implementation of this relief request, the encapsulation boundary (the outer piping) will become the credited pressure retaining boundary for this portion of the system. Thus, the encapsulation boundary will be subject to inservice inspection in accordance with Table IWD-2500-1, Category D-B, which requires a system leakage test and accompanying VT-2 examination each inspection period. The piping internal to the encapsulation boundary will be inaccessible and will not be examined under Section XI in the future because credit will no longer be taken for its pressure retaining function.

5.1.11 Encapsulation of the defective area at this location shall be performed only once.

Basis for Request Duke Energy believes that complying with IWA-4421 requirements to remove defective portions of this piping prior to performing a repair/replacement activity represents a hardship or unusual difficulty without a compensating increase in the level of quality and safety for the following reasons:

5.2.1 Removal of defective portions of this piping would require that the piping be isolated and depressurized. The 3 inch piping cannot be isolated for the following reason:

1.

System isolation using upstream valves is not possible without removing heat removal capability to Units 1 and 2 CC coolers. System isolation would require both Unit 1 and Unit 2 be in a shutdown condition.

5.2.2 Use of other alternative repair/replacement techniques that would avoid having to isolate and depressurize the 3 inch piping were considered, but were rejected for reasons identified below:

1.

Use of ASME Code Cases N-562-2 or N-661-2 Use of repair/replacement techniques detailed in Code Cases N-562-2 or N-661-2 are not possible because Figure 1 requires a minimum distance from branch reinforcement welds, and the location of the leak is located at one such weld.

2.

Use of ASME Code Case N-786-1 or N-786-2 Installation of a full-structural Type B reinforcing sleeve in accordance with Code Case N-786-1 or N-786-2, Figure 2 was considered, but was rejected because the degraded portion of the 3 inch piping is located very close to the branch connection weld to the 12 inch diameter LPSW header. General Requirement 1(f) states that this Case cannot be applied to branch connection welds.

3.

Use of ASME Code Case N-789-1 or N-789-2 Use of Code Case N-789-1 or N-789-2 to install reinforcing pads over locally thinned areas is not possible because paragraph 1(e) of the case

RA-20-0036, Page 6 of 7 allows the reinforcing pads to be used only until the next refueling outage.

Difficulty with isolating and depressurizing the system during the next refueling outage would still present a hardship. Additionally, Figure 1 requires a minimum distance from branch reinforcement welds, and the location of the leak is located at one such weld. Because N-789-1 or N-789-2 is not approved for use in NRC Regulatory Guide 1.147, Rev. 18, relief would also be required in order to use this case.

5.2.3 The proposed alternative shall be designed, constructed, and examined in accordance with all applicable requirements of the Construction Code. All welds shall be visually examined in accordance with ASME B31.1-2004. The encapsulation shall be pressure tested and VT-2 examined in accordance with IWA-4540 to confirm the absence of leakage from the replacement pressure retaining materials and their connecting welds. All other requirements of ASME Code,Section XI, for which relief has not been specifically requested, remain applicable including third-party review by the Authorized Nuclear Inservice Inspector. For these reasons, Oconee believes that the proposed alternative to IWA-4421 will provide reasonable assurance of continued structural integrity of the component.

6.0 DURATION OF PROPOSED ALTERNATIVE:

The proposed alternative is requested for the remaining life of ONS Unit 1 and Unit 2.

7.0 PRECEDENTS

ADAMS Accession Number ML15349A453. NRC approved dated December 29, 2015. Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1 and 2 "Relief Request in Accordance with 10 CFR 50.55a(z)(2) to use an Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water System Piping, dated June 12, 2015 (ML15169A860).

ADAMS Accession Number ML110800426. NRC approved dated March 28, 2011. Duke Energy Corporation, McGuire Nuclear Station, Unit 1, Relief Request Serial

1. 09-MN-002 "Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)", dated May 4, 2009, (ML092170658).

8.0 REFERENCES

2007 Edition through 2008 Addenda, ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components."

ASME Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1."

RA-20-0036, Page 7 of 7 9.0 ATTACHMENTS

Engineering Change (EC) 416973 Sketch, (2 pages)

Oconee Flow Diagram, OFD-124B-1.1, (1 page)

Relief Request RA-20-0036 Engineering Change (EC) 416973 Sketch

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3" LPSW PIPE WITH 6" PIPE

& CAP ENCAPSULATION ATTACHMENT 1: Sketch Page 1 of 2 See Page 2, "Encapsulation Detail"

4 1/4" 5/16" 1/2" 3000#, A-105 CS THD. H.C.

1/2" THD. PLUG, A-105 N.S.

F.S.

6" SCH 40 PIPE CAP A-234 WPB 6" SCH 40 PIPE, A-106 B SEAL WELD ENCAPSULATION DETAIL SECTION VIEW LOOKING WEST ENGINEERING CHANGE EC416973/000 SKETCH NOTES:

1. ALL MATERIALS TO BE QA-1

2. PIPING IS DUKE CLASS F, ISI CLASSS C

3. DRILL 4-1/2" HOLE IN TOP OF 6" PIPE CAP AND BEVEL CAP OPENING 45 DEG. +/- 2.5 DEG.

4. ACCEPTABLE FOR WELDS TO OVERLAP.

LINE STOP TEE

ø 4.5" +/- 1/32" 12" LPSW HEADER 1" +/- 1/32" 5/16" FULL SCALE: 1" = 1" 1/8" - 1/16" EXISTING 3" PIPE ATTACHMENT 1: Sketch Page 2 of 2

Relief Request RA-20-0036 Oconee Flow Diagram, OFD-124B-1.1

DESIGN PARAMETERS DESIGN TEMP.

DESIGN PRESS.

DUKE CLASS LINE NO.

MATERIAL PIPE SPEC. NO.

PIPE SCH. NO.

ISI CLASS DESIGN FLOW FLOW NO.

CC OFD-144A-1.1 1"

1LPSW-109 1LPSW-717 1/2" R.B.

COMPONENT 1CC HX000A 1"

1" COOLER 1A 1CC TT H-9 0074 OFD-144A-1.1 TB TB AB AB 1"

12" LPSW-353 LPSW-352 1"

1" LPSW-114 1LPSW-115 LPSW-721 1"

1" 8"

8" 1"

LPSW-720 1"

8" 1LPSW-111 12" 8"

1" RETURN SIDE VENT FROM UNIT 2 1"

LPSW-299 LPSW-295 CC OFD-144A-1.1 8"

1" LWD-359 1"

LWD-957 1"

3/4" 1"

2 1/2" 1"

1" 1"

1LWD-956 1LWD-357 1"

1LWD-955 1"

SUPPLY SIDE VENT FROM UNIT 2 8"

LPSW-718 1"

8" COOLING SUPPLY TO R1A HEAT EXCHANGERS 8"

LPSW-113 LPS H-11 OFD-124A-1.1 1"

1" 1"

1" 1"

1LPSW-162 3/4" H.P.I. PUMP C MOTOR BEARING COOLING JACKET 1LPSW-660 BEARING COOLING JACKET 1"

H.P.I. PUMP B MOTOR 3/4" 1"

1HPIHX0003 1LPSW-72 LPI OFD-102A-1.2 1LWD-17 1LWD-952 FROM LPSW 1LPSW-348 1"

1LPSW-709 1LPIHX000B L.P.I. & DECAY HEAT COOLER 1B T

3/4" 3/4" 1"

1" 1LPSFX0027 1LPSFX0028 LPI OFD-102A-1.2 1LWD-15 1LWD-949 FROM LPSW L.P.I. & DECAY 1"

1" 1LPSW-4 E

1LPSW-528 VALVE J-6 1LPSW-252 OFD-124B-1.1 2"

1" 1"

1" 1"

L 1LPSW-507 1LPSW-508 1LPSW-150 1 1/2" 1"

3/4" 1 1/2" BLOW DOWN LINE 1LPSW-71 1LPSW-347 1"

VALVE J-6 1LPSW-251 OFD-124B-1.1 1LPIHX000A HEAT COOLER 1A 1LPSFX0025 1LPSFX0026 1"

1 1/2" T

3/4" 3/4" 1LPSW-238 LPS K-13 OFD-124B-1.5 1"

1" L

1 1/2" 3/4" 1 1/2" 1LPSW-708 2"

1" 1LPSFL0001 1LPSW-147 1"

BLOW DOWN LINE 1"

FROM HPSW 1LPSW-576 EM EM 1LPSFL0002 1

6 7

8 F

F G

F 100 PSIG 150 PSIG 150 PSIG 100 PSIG SS SS 151.4 151.4 NOTE 3 NOTE 3 NOTE 3 C

C 1

2 3

12 GPM 3000 GPM 1300 GPM 1LPSW-661 1HPIHX0002 1LPSW-663 1LPSW-662 UNIT 1 "B" SUPPLY UNIT 1 "A" SUPPLY SUPPLY TO UNIT 2 COMPONENT COOLER 8"

TO UNIT 2 RETURN HEADER TO & FROM UNIT 2 C.C. RIA SAMPLE HEADER SS 151.4 NOTE 3 NOTE 3 C

10 H

ATM CS 150.4 150.4 (NOTE 5)

CS (NOTE 5) 1LPSW-108 1"

2" 18" 24" 24" CCW LPS 24" 1"

CCW G-9 OFD-133A-1.4 TO RCW COOLER DISCHARGE HEADER 1LPSW-157 3/4" 3/4" 1

LPSPG 0235 6

1 LPSPG 6

0237 6

8" 10" FO 1LPSW-356 OFD-124B-2.1 LPS C-5 OFD-124B-2.1 LPS E-6 S

V OFD-124C-1.2 HPS F-9 1

6 6

6 CUNO FILTER NORMAL SUPPLY 1LPSW-148 8 6 2"

2 20" 20" 16" 1

8 1

20" 1 1 LPS E-14 OFD-124A-1.1 SUPPLY HEADER 1

1 LPSTX 0232 LPSFE 0076 1

1 LPSFT 0124 0127 1

0040 1

T 1

1 1

LPSTX 0233 1LWD-14 1LWD-948 1LWD-947 LWD OFD-107C-1.2 H-2 T

1 1

1 1

1 LPSTX 0234 1

0041 1

1 1

0128 1

LPSPS 0360 LPSFT 0125 LPSFE 0077 1

1 20" 16" 14" 2

LPS K-14 SUPPLY HEADER 14" 8 6 1

1LPSW-151 1LPSW-502 1 1 12" 12" 1LWD-953 1LWD-951 1"

LWD OFD-107C-1.2 H-1 TO D-1 DRAIN HEADER TO L.A. WASTE TANK LWD E-1 OFD-107C-1.2 TO L.A. WASTE DRAIN TO D-1 DRAIN HEADER 12" 1

1 LPSTX LPSTX 0222 0220 T

1 1

1 1

1LWD-356 10 10 OFD-124B-2.1 FROM UNIT 2 SUPPLY SIDE DRAIN LPS OFD-124B-1.1 B-13 TO LAWT FLR DRAIN LWD-358 10 1

1 1

T LPS OFD-124B-2.1 C-4 FROM UNIT 2 RETURN SIDE DRAIN LWD-958 10 OFD-124B-2.1 LPS E-2 6

CUNO FILTER EMER. SUPPLY V

V S

1LPSW-719 1LPSW-354 1LPSW-110 1LPSW-298 1LPSW-294 LPSW-297 LPSW-301 1

1" 1

0223 LPSTX 0221 LPSTX 1

1 1 1 LPS E-5 OFD-124B-2.1 1LPSW-240 COOLER "1B" R.V.

FR. R.B. COMPONENT COOLER "1A" R.V.

FR. R.B. COMPONENT 2 1l2" 2 1l2" 2 1l2" 2 1l2" 1"

2 1l2" 2 1l2" CC CC CC OFD-144A-2.1 OFD-144A-1.1 OFD-144A-1.1 F-3 I-6 I-6 10 10 10 10 10 10 100{F 100{F 100{F 100{F 200{F COOLER "2A" R.V.

FR. R.B. COMPONENT TO L.A. WASTE TANK TO D-1 DRAIN HEADER 6

6 1LWD-954 1LWD-16 OFD-124A-1.1 1LWD-950 27 27 25 26 25 25 25 3

58 F

100 PSIG NOTE 3 NOTE 3 C

NOTE 3 NOTE 3 C

25 F

100 PSIG 246{F CS (NOTE 5) 150.4 (NOTE 5) 26 F

100 PSIG CS (NOTE 5)

CS (NOTE 5) 150.4 (NOTE 5) 150.4 (NOTE 5)

C 27 150{F 42 G

150 PSIG 200{F SS 151.4 C

LPSSS LPSSS C

C 1"

8 8

1LPSW-1033 1LPSW-1034 1LPSW-343 1"

6 16" MARBO TAP 24" NOTE 3 C

29 F

246{F SS 151.4 LPS I-8 OFD-124B-1.5 17 25 17 1/2" 3/4" TO 1RIA-35 17 G

246{F SS 151.4 40S 3/4" 1"

1/2" 1LPSW-760 1LPSW-749 193{F (NOTE 7) 4 4

5 5 1/2 GPM 2 GPM 100 PSIG (NOTE 6) 100 PSIG (NOTE 6) 25 46 1/2" 1

LPSFT 1000 1

LPSPS 0359 1

LPSFT 1001 C

LPS P LPS P 1"

1LPSW-711 1"

DISCHARGE TO A.H.U.

HEADER 1"

1LPSW-771 6

2" OFD-124B-1.6 41 3/4" 1"

1 1LPSW-159 LPSPG 0236 1LPSW-160 3/4" 3/4" 3/4" 1"

3/4" 1"

1 1LPSW-164 LPSPG 0238 1LPSW-165 41 3/4" 3/4" 3/4" 1"

1LPSW-158 1LPSW-163 41 1

LPSFE 1008 1

LPSPS 1014 1

LPSFE 1009 1

LPSPS 1015 1"

1" 42 1LPSW-932 41 F

150 PSIG SS 151.4 NOTE 3 C

200{F 42 1

LPSFE 0204 L

1LPSFL0018 CUNO FILTER 1"

3/4" 1 1/2" 45 7

D 1LPSW-935 1 1/2" 1"

45 45 HPS OFD-124C-1.3 J-13 45 G

150 PSIG 100{F 46 G

100 PSIG 246{F SS 1501.4 (NOTE 8) 160 TO RIA-31 NOTE 9 48 26 48 F

100 PSIG SS C

151.4 NOTE 3 193{F (NOTE 7) 1LPSW-742 S

35 NOTE 3 35 G

150{F 100 PSIG CS(NOTE 5) 150.4(NOTE 5) 150.6 (NOTE 5)

NOTE 3 CS(NOTE 5)

AB TB AB TB OFD-124B-1.1 1"

FO 1LPSW-251 1LPSW-170 1

LPSTX 0249 1LPSW-169 0040 10" 11 25 11 25 1 1/2" 1"

1/2" 1LPSW-850 46 25 1LPSSS J-1 1

LPSSV 1000 D

1" 25 50 D

1" V

1" 1

LPSPG 0855 25 11 25 11 8"

1LPSW-972 1LPSW-971 1LPSW-973 16" 34 50 50 11 50 34 11 50 50 34 10" V

25 47 47 25 1"

1LPSW-254 1"

AB TB AB TB 1LPSW-239 LPS K-12 OFD-124B-1.5 1LPSW-256 EM EM OFD-124B-1.1 FO LPS CCW 1LPSW-167 1

LPSTX 0250 1LPSW-168 25 1LPSW-252 0041 16" MARBO TAP 11 MARBO TAP 1O" 1O" 10" 25 11 1LPSW-873 LPS H-8 OFD-124B-1.5 25 29 1LPSW-750 1/2" 1/2" TO 1RIA-35 29 1"

1LPSW-898 1/2" 16" 1LPSW-864 1/2" 3/4" 4

1/2" 1LPSW-863 25 46 25 11 1/2" 25 46 1/2" 1LPSSS I-1 1

LPSSV 1001 46 V

1 LPSPG 0856 1"

25 50 8"

25 11 11 25 D

1" D

1" 16" 16" 1LPSW-974 1LPSW-975 1LPSW-976 34 50 50 11 50 34 34 50 11 50 1LPSW-5 E

1" V

1LPSW-529 V

1" 47 25 10" 50 F

100 PSIG SS C

246{F 1501.4 (NOTE 10) 160 (NOTE 10)

NOTE 3 34 G

246{F 100 PSIG 150.4(NOTE 5)

CS NOTE 3 11 F

SS 151.4 C

246{F 100 PSIG 16" 1"

1LPSW-977 V

47 F

100 PSIG 246{F CS C

150.4 60 6

7 6

7 TO RIA-31 1

LPSPG 0116 1

LPSPG 0117 1"

3/4" PX 1037 1LPSW-PX 1/2" 1/2" PX 1LPSW-1035 PX 1LPSW-1036 1/2" PX 1038 1LPSW-947 1LPSW-1/2" PX PX PX PX PX 1LPSW-505 1LPSW-506 PX OFD-101A-1.3 G-7 0002 1HPIPU OFD-101A-1.3 D-7 0003 1HPIPU 58 F

100 PSIG C

150{F 59 G

100 PSIG 150{F CS(NOTE 5) 150.6 (NOTE 5)

NOTE 3 CS(NOTE 5) 150.6 (NOTE 5)

NOTE 3 27 58 27 58 1"

& RETURN THRU L.P.I. & DECAY HEAT COOLERS, H.P.I. PUMP MOTOR BEARING COOLING JACKETS, AND REACTOR BUILDING COMPONENT COOLER 1A.

3. 1\\2" THRU 10" SCH. = 40 12" THRU 24" SCH. = STD

1. OPERATING MODE REPRESENTED BY BOLD LINES: LPSW SUPPLY PO-124B-1, REV. 9, & PO-115B, REV. 27.

2. ORIGINAL ISSUE OF THIS DRAWING WAS BASED ON PO-124A-1, REV. 7,

6. OPEN ENDED - NO HYDROTEST REQD.

8. BRASS AND BRONZE VALVES MAY BE USED.

9. VALVE 1LPSW-356 IS A 4" VALVE WITH 8" END CONNECTIONS.

STRESS CONSIDERATIONS FOR VIBRATION.

10. PIPE SPEC. AND PIPE SCH. WERE DICTATED BY OF OS-243.00-00-0001.

SEE NOTE 24 IN APPENDIX C, MATERIAL REQUIREMENTS, PRIOR TO ANY CHANGE OF THE EXISTING MATERIAL.

INDICATED. PIPING ENGINEERING APPROVAL IS REQUIRED OR OF CARBON STEEL TO THE APPLICABLE "PS" MAY BE OF AUSTENITIC STAINLESS STEEL MATERIAL FOR PIPE SIZES 1/2" THRU 6". EXISTING PIPING

5. STAINLESS STEEL (PS-151.4) MAY BE SUBSTITUTED NOTES:

CC COOLER SPARE UNIT 1 & 2 0CC HX000B 1

LPSPG 0700 7

7

}=0.576" 1/2" 1"

1/2" 1"

1" 3/4" P

F G

1" O

PX P

F G

O 11 2"

11 25 16" 1LPSW-1141 D

1" 1

LPSTX 0235 LPS G-12 8

8 8

1" 8

1 LPS H-2 OFD-124B-1.5 LPS D-1 OFD-124B-2.1 1

1 27 27 58 58 LPS C-3 1LPSW-152 3/4" BEARING COOLING JACKET 1"

1LPSW-149 1"

3/4" 1"

H.P.I. PUMP A MOTOR 1"

1LPSW-659 1LPSW-658 1HPIHX0001 6

1 LPSPG 0233 1LPSW-153 1"

1 1LPSW-154 LPSPG 0234 1LPSW-155 3/4" 3/4" 1"

41 1

LPSFE 1007 1

LPSPS 1013 3/4" 3/4" 6

7 OFD-101A-1.3 J-7 0001 1HPIPU 18" 18" 18" 1LPSW-1127 1LPSW-1119 1LPSW-1120 1LPSW-1121 1LPSW-1122 1LPSW-1124 1LPSW-1125 1LPSW-1126 3/4" D

1" D

1LPSW-1130 1LPSW-1128 1"

D 1"

1LPSW-1131 D

1" 1LPSW-1129 18" 1"

LPSW DISCHARGE FROM UNIT 1 REACTOR BLDG.

1 LPSSV 1121 3"

1 LPSSV 1123 1

LPSSV 1124 1

LPSSV 1122 V

1LPSW-1133 1"

V 1LPSW-1132 FO FO FO 1LPSMJ0012 LPS C-1 OFD-124B-1.2 AB AB TB TB D

1LPSW-1138 1LPSW-1139 2"

3" 1"

NOTE 11 18" 1"

1 1/2" 1LPSW-1149 1LPSW-1148 1LPSW-1151 1LPSW-1150 FC FC 1

LPSSV 1151 1

LPSSV 1150 6"

6" 1LPSW-1137 NOTE 11 1LPSW-1135 1LPSW-1136 FO 1"

D 2 1/2" 1"

NOTE 12 NOTE 12 1LPSW-1123 1"

1" 26 26 68 68 NOTE 11 OFD-124B-2.1 (REF. OFD-107C-1.1 @ E-3)

TO LAWT FLR DRAIN 2 1l2" 2 1l2" 1"

CC OFD-144A-1.1 G-3 10 10 27 27 10" D

1LPSW-1153 1LPSW-1152

}= 3/4" 2 1l2" 10 10 OFD-124B-1.1 LPS B-5 DRAINS FROM SUPPLY SIDE 1IA-2967 1IA-2964 2"

IA J-2 O-449U AIR SUPPLY FROM INSTRUMENT 1

LPSPG 1561 V

1" 1LPSW-1154 24" TO "2B" RETURN HEADER 10" 1

LPSLT 0129 1

LPSLG 0001 1LPSW-1161 1LPSW-1160 1/2" 1/2" 2"

2" 1"

2" 1HPSW-943 1HPSW-951 HPS F-7 OFD-124C-1.3 FROM HPSW 6

1 1

7 7

6 6

6 6

LPS K-4 OFD-124B-1.1 2"

2" 24" 2"

2" 1LPSTK0001 SEE NOTE 13 VOL. = 77 GALS.

(WATER PORTION)

ACCUMULATOR LPSW LEAKAGE 1LPSTK0002 LPS H-9 SEE NOTE 14 VOL. = 16.2 FT (AIR PORTION)

ACCUMULATOR LPSW LEAKAGE 3

SUPPLY DRAIN FROM C.C. COOLER 2 1/2" 2 1/2" 14" D

1" 1LPSW-1109 1LPSW-1112 OFD-124B-1.2 LPS L-1 UNITS TO R.B. COOLING 14" 1

LPSPT 0010 1

LPSPT 0011 OFD-124B-1.1 LPS D-13 D

1LPSW-1110 1LPSW-1111 NOTE 12 1LPSW-1113 2"

2" TREATED AS ISI CLASS C PIPING.

PIPING WITH PIPE CAPS. TANK AND ASSOCIATED SUPPORTS ARE TO BE

13. TANK TO BE FABRICATED AS CLASS F PIPING FROM 2 FEET OF 24" STD.

TREATED AS ISI CLASS C PIPING.

PIPING WITH PIPE CAPS. TANK AND ASSOCIATED SUPPORTS ARE TO BE

14. TANK TO BE FABRICATED AS CLASS F PIPING FROM 4 FEET OF 24" STD.

68 G

100 PSIG 100{F NOTE 3 SS 151.4 ACCUMULATOR FROM LPSW LEAKAGE LPS L-1 OFD-124B-1.4 SUPPLY TO RC PUMP COOLERS V

1LPSW-704 1"

10" 1

8 14" 1

LPSPT 0012 1

LPSPT 0013 OFD-124B-1.2 LPS K-11 BYPASS TO RBCU SUPPLY HEADER 14" D

1LPSW-1115 1LPSW-1114 2"

1/2" 1/2" 1LPSW-1107 1LPSW-1108 D

1LPSW-1117 1"

1LPSW-1116 1LPSW-1118 NOTE 12 OR A DRAIN.

1LPSW-1108 CAN BE TREATED AS CLASS "G" AS IF THEY WERE A VENT

15. THE PIPE NIPPLE AND CAP ON THE OUTLET OF VALVES 1LPSW-1107 AND (NOTE 15)

(NOTE 15)

SERVICE WATER FROM PROTECTED OFD-131A-1.2 PSW D-14 1"

1" V

1LPSW-930 1LPSW-931 72 6

6 72 72 F

150 PSIG 150{F SS C

NOTE 3 151.4(a) 1LPSW-946 47 75 F

100 PSIG 246{F CS C

150.4 40 75 25 47 47 75 LPSW RB WATERHAMMER SYSTEM IS OPERABLE.

OVERPRESSURE PROTECTION ANY TIME THE

11. VALVES TO BE LOCKED OPEN TO PROVIDE EVALUATED FOR 150 PSIG.

1LPSW-1122,1LPSW-1123 AND 1LPSW-1124.THIS REGION HAS BEEN 1LPSW-1111,1LPSW-1116 AND AIR OPERATED VALVES,1LPSW-1121, THE REGION OF THIS INCREASED PRESSURE IS BETWEEN CHECK VALVES, THE PRESSURE MAY MOMENTARILY INCREASE ABOVE THE DESIGN PRESSURE.

12. DURING ACTUATION OF THE LPSW RB WATERHAMMER PREVENTION SYSTEM, SCREWED CONNECTIONS DO NOT REQUIRE SEAL WELDS.

NOTE 3 F

CS (NOTE 5) 150.4 (NOTE 5)

C NOTE 3 F

CS (NOTE 5) 150.4 (NOTE 5)

C 193{/260{F(NOTE 7,17)

NOTE 3 F

100 PSIG C

80 83 94 100 PSIG(NOTE 12) 100 PSIG(NOTE 12) 100{/260{F(NOTE 17) 100{/260{F (NOTE 17) 94 83 83 83 83 83 83 26 26 26 26 80 1

80 94 80 80 80 80 80 80 1

80 SS 151.4

7. 193{F IS THE MAXIMUM POST-LOCA TEMPERATURE.

BY THE 100{F DESIGN TEMPERATURE.

ALL OTHER PLANT SYSTEM CONDITIONS ARE ENVELOPED EVENT THAT IS NOT COINCIDENT WITH AN EARTHQUAKE. ALL OTHER PLANT

17. THE 260{F TEMPERATURE IS A RESULT OF A ONE-TIME NON DESIGN BASIS SYSTEM CONDITIONS ARE ENVELOPED BY THE 100{F DESIGN TEMPERATURE FROM PROTECTED SERVICE WATER PSW H-13 OFD-131A-1.2 3"

8 8

1 8

4" NOTE 18

18. 3"DIA. HOLE CUT INTO 12"HEADER.

1 8

3" D

1" LPSW-1249 LPSW-1250 SUPPLY HEADER FROM LPSW STOP LINE AB TB AB TB QA CONDITION 1 OFD-124B-1.1 FLOW DIAGRAM OF LOW PRESSURE SERVICE WATER SYSTEM (AUXILIARY BUILDING SERVICES) 68 REV. PER EC410600 68 REV. PER EC77313, EC412128, EC414792 AS=1, OMD-05 A

B C

D E

F G

H I

J K

L 1

2 3

4 5

6 7

8 9

10 11 12 13 14 A

B C

D E

F G

H I

J K

L 1

2 3

4 5

6 7

8 9

10 11 12 13 14 REV.

No.

Revisions DWG. No.

SCALE D U K E E N E R G Y OCONEE NUCLEAR STATION - Unit 1 67 1142 1LPSW-D 1"

25 11 2"

1" 11 68 68 SERIES) IN CONJUNCTION WITH ALL REVISIONS MADE TO THIS DRAWING.

16. UPDATE INSERVICE INSPECTION NDE BOUNDARY DRAWINGS (O-ISIL & O-ISIN 6" Pipe Cap added to maintain pressure boundary due to thru-wall leak at 3 pipe branch connection.

ATTACHMENT 2: Oconee Flow Diagram, OFD-124B-1.1 PAGE 1 of 1