ML101250246

Inservice Insp Program for Welds & Pipe Supports & Pump Valve Surveillance Test Program

ML101250246
Person / Time
Site:	Indian Point
Issue date:	10/31/1979
From:	Ruddle P, Sorrentino A Power Authority of the State of New York, Westinghouse, Div of CBS Corp
To:
Shared Package
ML093421077	List: ML093421076 ML101250246
References
NUDOCS 7911020341
Download: ML101250246 (62)

Text

INDIAN POINT UNIT 3 NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR WELDS AND PIPE SUPPORTS and ab \\c PUMP AND VALVE SURVEILLANCE TEST-PROGRAM Revision 0 October, 1979 Prepared by:

Date:

(Ci ) IL ('

(° 71 P. L.-Ruddle, Westinghouse Nuclear Service Division Approved by:

bi

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Date:

0.. 6_-CA-_ 4 1

A. V. Sorrerdino Power Authorityof the State of New York t/

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POWER AUTHORITY STATE OF NEW YORK INDIAN POINT UNIT 3 SECOND 40 MONTH PERIOD OF FIRST 10 YEAR INTERVAL The attached tables provide a listing Of the Class 1, 2 and 3 pressure-retaining components (and their supports) which are subject to the inspection requirements of Subsections IWB, IWC and IWD of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summier, 1975.

These tabulations identify the components to be inspected, the components safety class, the applicable code to which the component was built, and the method of examination.

Relief from the inspection requirements of each Subsection is requested in cases where these inspection requirements have been determined to be impractical.

Where relief is requested, specific information is provided which identifies the applicable code requirement, justification for the relief request, and the inspection method to be used as an alternative.

The following pro vide further clarification concerning the Class 1, 2 and 3 system inspection programs.

(a) Articles IWC-3000 and IWD-3000 entitled, "Evaluation of Examination Results" are in the course of preparation by the Code Commnittee and, as yet, are not available for use. Standards for examination evaluations as included in the 1974 Edition of Section XI with Addenda through the Sumrier, 1975, are incomplete and "Acceptance Standards for Flaw Indications "as given in Article IWB-3000 of the 1977 Edition of Section XI will be utilized.

(b) Articles IWC-4000 and IWD-4000 entitled, "Repair Procedures" state that the rules of IWB-4000 shall apply. When the repair procedures outlined in IWB-4000 are not applicable for the Class 2 and 3 components in this program, the rules of IWA-4000 will be applied.

'(c) Requirements for the visual examination of Class 1 systems and components for evidence of leakage during the performance of a system pressure test following each refueling are identified by

IWB-5200. Exception is taken to the implementation of these requirements on those portions of Class 1 systems which are contained between two check valves or two normally closed valves, where pressure applied to the reactor coolant system will'be retained at the first valve in the line. The portions of systems affected by this limitation are:

(1) Cold leg injection from accumulators between check valves 897A, B, C and D and 895A, B, C and D, test lines to valves 839A, B, C and D, RHR return and low head injection lines to valves 838A, B, C and D and high head injection lines to valves 857A, Q9-S and U. During normal operation these portions of the systems are filled and pressurized to the normal accumulator operating pressure of 620 to 665 psig.

(II) Hot leg injection between check valves 857C, D, E and F and check valves 857J, K, L and M. These portions of systems are filled and vented but not pressurized during normal operation.

(III) Cold leg boron injection line between check valves 857C, D, E and F and check valves 857J, K, L and M.

(IV) RHR take off line between normally closed (with pressure interlock) valves 730 and 731.

This portion of the system will-be pressurized whenever the system is put into operation during plant shutdown when the reactor coolant system is cooled to 350'F and depressurized to 450 psig.

These valves are interlocked to automatically isolate when the reactor coolant system pressure exceeds 600 psig.

(d Subsections IWB and IWC contain differing requirements for the hydrostatic testing of Class 1 and Class 2 systems and components.

The implementation of these requirements is impractical when the only means of pressurizing the Class 2 system is through the Class 1 system or when the boundary between the two systems 1s a check valve arranged for flow from Class 2 to the Class 1 system.

Exception is taken to the performance of the hydrostatic test requirements as required by Article IWC-2412 (a) on those portions of the Class 2 systems identified below. Visual examination for evidence of leakage will be conducted on these portions of the systems at the system nominal operating pressure in accordance with the requirements of IWB-5221 for the adjoining Class 1 system.

(I) Pressurizer steam space sampling line from valve 950 to valve 956 A, pressurizer liquid space sampling line from valve 952 to valve 956 C and loop sampling lines to valve 956E.

(e) The examination requirements for Class 3 systems and components as given in the attached tabulation are in accordance with IWD 2410(c) which specifies that 100 percent of the components be examined as required by IWS-5240 and IWD-2600 either during normal operation or during system inservice testing. An additional requirement of IWD-2410(b) is for the examination of Class 3 systems and components for evidence of leakage during the per formance of a system pressure test in accordance with IWD-5000.

The Code does not stipulate that certain amounts of these exam ination requirements be completed within each 40 month period such that the system pressure test requirements may be deferred until the end of the ten year inspection interval.

However, it should be noted, that these system pressure tests when required are impractical in those systems, such as component cooling, river water, spent fuel pit cooling, and boric acid transfer and recirculation, which are in continuous operation during all modes of plant operation. The continuous functional operatton serves to demonstrate the structural and leak-tight integrity of these systems. Visual examinations of these systems will be performed at normal operation pressures to verify leak-tightness, (f) Ultrasonic examinations will be conducted in accordance with the provisions of Appendix 1 and Article 5 of Section V as required

by paragraph IWA-2232.

As an alternative to using Article 5 of Section V, Appendix III of Section XI of the 1974 Edition, Winter, 1975 Addenda of the ASME Boiler and Pressure Vessel Code will be used for ultrasonic examination of piping systems.

It is recognized that Appendix III of Section XI was issued in the Winter, 1975, Addenda and, as such, has not been officially recognized by the NRC by reference in 10 CFR 50. However, Appendix III is the first guideline that has been published in the ASME Codes for the ultrasonic examination of pipe welds and, as such, its use is essential.

The extent and frequency of examination of Class 1 and 2 piping system welds will be as required by Table IWB-2500 Category B-J and Table IWC-2520 Categories C-F and C-G. However, examination requirements and examination methods for piping system welds will be as defined in Tables IWB-2500-1 Category B-J and IWC-2500 1 Category C-F of the 1977 Edition of Section XI Summer 1978 Addenda.

(g) As an alternative for 1-3121 of Section XI:

"Calibration blocks required for the examination of welds in ferritic vessels 2 1/2 inches thick and over will be fabricated from material of the same specification, product form, and heat treatment as one of the materials being joined as allowed by article T-434.1 in the Winter, 1976 Addenda of Section V of the ASME Boiler and Pressure Vessel Code."

The reason this al.ternative is requested is that the Code requires that calibration blocks for the examination of welds in ferritic vessels 2 1/2 inches thick and greater be fabricated from material taken from the component nozzle drop out or material from the component, the block may be fabricated from a material of a specification included in the applicable examination volumes of the component. It is required that the acoustic velocity and attenuation of such a block be demonstrated to fall within-the range of straight beam longitudinal wave velocity and attenuation found in the unclad components.

For the components in the Indian Point Unit 3 Plant, particularly the pressurizer and steam generators, it will be impossible to meet the requirements of alternative 1 or 2. Materials of the specification are readily available, but because all the components involved are clad on the inner surfaces, it would be impossible to obtain a comparison of sound beam velocities and attenuations in the unclad component.

Table IWB-2600 contains requirements for the examination of vessel cladding on thereactor vessel closure head (Item Bl.13),

the reactor vessel (Item Bl.14) the pressurizer (Item B2.9) and the steam generator primary side (Item B3.8).

Volumetric examinations performed on each of these vessels for the inspection of welds will detect defects which may originate in the clad material and extend into the base material for more readily than visual examinations of the clad surface. As this examination requirement is deleted by later editions of the code, exception is taken to the performance of these examinations.

Limitations may occur for the examination of piping system circum ferential butt welds (Category B-J) when the welds occur at geometric discontinuities such as pipe to vessel welds, pipe to fitting welds or fitting to fitting welds. For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces. Examination from the fitting side would be dependent upon the geometrlc con figuration. Where elbows or tees are concerned, examination can be performed from the fitting side except where the intrados of

the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when it is a valve or a flange. In all cases 100 percent of the weld material can be examined.

In instances where welds occur at fitting to fi-tting, access restrictions as outlined above occur on both sides of the weld.

In instances where ultrasonic examinations cannot be per formed on 100 percent of the volume of the weld and heat affected zone, surface examinations will be performed to supplement the limited volumetric examination.

Welds in the Indian Point Unit #3, Class 1 system which due to limitations, would require surface examinations are:

(I)

IVII)

(VIII)

(vX)

(IM)

(XII)

Loop 31 Accumulator discharge line; Weld.#2 Loop 31 Letdown line; welds #4, 5, 8, 9, 12 and 13 Loop 32 Accumulator discharge line; welds #2 and 3 Loop 32 RTD Return line; welds #1 and 2 Loop 33 Accumulator discharge line; welds #4 and 5 Loop 33 RTD Return line; welds #1 and 2 Loop 34 Accumulator discharge line; weld #3 Loop 34 RTD Return line; welds #1 and 2 Pressurizer Spray line; weld #1 Pressurizer safety valve lines; welds #5, 8, 9, 14, 17, 18, 23, 26 and 27 Pressurizer relief lines; welds #6, 7, 8 and 15 Charging line, welds #1 and 8 In instances where the locations of pipe supports or hangers restrict the access available for the examination of pipe welds as required by IWB-2600, examinations will be performed to the extent practical un less removal of the support is permissible without unduly stressing the system.

Certain Class 2 systems or portions of Class 2 systems and components are exempt from the examination requirements of the IWC-2520 by IWC 1220. A summnary of these exemptions as applicable to the Indian Point

plant systems are as follows:

(I)

During plant operation, the boric acid solution will be constantly recirculated through the boron injectiorf-tank by the recirculation pump system. Samples would normally be taken on a regular basis and the component and associated piping would be exempt from examination by IWC-1220(c).

(II) The boron injection tank discharge piping is all equal to or less than 4 inch nominal diameter.

(III)

During plant operation, the contents of the SIS accumulators are normally sampled on a regular basis and this component and associated piping would also be exempted by IWC-1220(c).

(IV) During plant operation, the high head SIS injection pumps are run on a periodic basis to recirculate flow to and from the RWST. Samples taken on a regular basis from the RWST would verify the chemistry of the system fluid and exemption from examination would again be by IWC-1220(c).

V)

The high head SlS piping equal to or less than 4-inch nominal diameter is exempted by INC-1220(d).

(VI)

The containment spray system and recirculation spray systems do not function during normal reactor operation and exempted by IWC-1220(b).

(VII) The RWST and associated piping have design pressures and temperatures less than 275 psig and 200°F and are exempt by IWC-1220(a).

The inservlce inspection programs outlined in the attached tabulations have been developed as a result of a design review. Should certain ASME Section XI Code requirements be discovered to be impractical due to unforeseen reasons during the process of performing inspections or tests, relief will be requested from the specific Section XI Code requirement at that time.

Radiation levels in certain areas or of certain components may be found to prohibit the access for operators or inspectors to perform the inspections or tests described in this program. If source strengths cannot be reduced and access is still restricted by considerations of compliance with the require ments of Regulatory Guides 8.8 and 8.10, relief will be requested from the 1pecific Section XI Code requirements and alternative examination or test requirements be proposed.

Codes referenced as being applicable to construction of components in the attached tables are:

IIIA ASME Boiler and Pressure Vessels IIIC ASME Boiler and Pressure Vessels VIII ASME Boiler and Pressure 4

B 31.1 USA Standard USAS B 31.1 B 16.5 USA Standard USAS B 16.5 Fittings.

Vessel Code,Section III, Class A Nuclear Vessel Code,Section III, Class C Nuclear Vessel Code,Section VIII, Pressure Vessels Code for Pressure Piping Steel Pipe Flanges, Flanged Valves and

INDIAN POINT UNIT NO. ' NUCLEAR POWER PLANT INSERVICE. INSPECTION ASME CODE CLASS 1 COMPONENTS TABLE IWB-2500 EXAMINATION CATEGORY SYSTEM OR COMPONENT CODE APPLICABLE TO CONSTRUCTION AREATO B EXAINE REO IREENT REQU ESTED B1.1 B1.1 81.1 B1.1 B1.2 B1.2 B1.2 B1.2 B1.2 B1.2 81.3 B1.3 B1.4 B1.4 Reactor Vessel RCPCR-V1 III A B-A B-A B-A B-A B-B B-B B-B B-B B-B B-B B-C B-C B-D B-D EXAMINATION Lower Shell to intermediate shell cir cumferential weld.

Intermediate shell course longitudinal welds (3).

Lower shell course longitudinal welds (3).

Upper shell to intermediate shell cir cumferential weld.

Lower head to shell weld.

Upper shell course longitudinal welds (3).

Lower head peel segment meridional welds (6).

Lower head disc to peel segment circum ferential weld.

Closure head disc to peel segment circumferential weld.

Closure head peel segment meridional welds (6).

Vessel to flange weld Closure head to flange weld Outlet nozzle to vessel welds (4).

Inlet nozzle to vessel welds (4).

SECTION XI CODE RELIEF Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Note 1 Note 1 Note 2

a.

L........________________

.1 1

TABLE IWB-2600 ITEM NO.

Yes Yes Yes No No No No No AREA TO BE EXAMINED

p INDIAN POINT UNIT NO. 3 ";CLEAR POWER PLANT INSERYICE1 INSPECTION, ASME CODE CLASS 1 COMPONENTS TABLE IWB-2500 EXAMINATION CATEGORY SYSTEM OR COMPONENT I

Ir B1.5 B1.6 B1.6 B1.7 B1.8 81.9 Bl.lO B1.10 B1.11 B1.12 B1.13 B1.14 B1.15 B1.16 B1.17 B1.18 CODE APPLICABLE TO CONSTRUCTION B-E B-F B-F B-G-1 B-G-1 B-G-l B-G-l B-G-2 B-H B-I-I B-I-1 B-N-1 B-N-2 B-N-3 B-0 EXAMINATION REQUIREMENT Vessel penetrations including control rod drive penetrations and control rod housing pressure boundary welds.

Outlet nozzle to safe-end welds (4).

Inlet nozzles to safe-end welds (4).

Closure Head Studs (in place)

Closure Head studs & nuts.

Vessel flange ligaments Closure head washers Conoseal Bolting.

Integrally welded vessel supports.

Closure Head Cladding Vessel Cladding Vessel Interior Surfaces and Internals Interior Attachments and Core Support 3tructures

ore Support Structures

ontrol Rod Drive Housings SECTION XI CODE RELIEF REQUESTED No Yes.- Note3 Yes -

Note3 No -

Note 4 No.

Visual Volumetric, Surface &

Visual Volumetric, surface &

Visual Not Applicabl, Volumetric &

Surface Volumetric Visual Visual Not Applicabl, Surface &

Visual or Volumetric Visual Visual Not Applicabl(

Visual Volumetric I

L I

I

. TABLE IWB-2600 ITEM NO.

Note Note No No No -

AREA TO BE EXAMINED Note 7

1. 3 INDIAN POINT UNIT NO. 3 NUCLEAR POWER PLANT INSERVICE INSPECTION, ASME CODE CLASS 1 COMPONENTS TABLE IWB-2500 EXAMINATION CATEGORY SYSTEM OR COMPONENT AREATO B EXAINE REQ IREENT REQUESTED B1.19 B2.1 B2.1 B2.2 B2.3 B2.4 B2.5 B2.6 B2.7 B2.8 B2.9 B2.10 B2.11 B3.1 B3.2 B3.3 B-P B-B B-B B-D B-E B-F B-G-1 B-G-1 B-G-1 B-H B-1-2 B-P B-G-2 B-B B-D B-F CODE APPLICABLE TO CONSTRUCTION III A IIIA Exempted Components.

Longitudinal Shell welds (8)

Circumferential Shell welds (9)

Nozzle to vessel welds (6).

Heater Penetrations Nozzle to safe-end welds (6).

Pressure Retaining Bolting (in place)

Pressure Retaining Bolting (when removed)

Pressure Retaining Bolting Integrally Welded Vessel Supports Vessel Cladding Exempted components Manway Bolting Channel Head to tubesheet weld (4)

Nozzle to vessel welds (8) 4ozzle to safe-end welds (8).

EXAMINATION REQUIREMENT Pressurizer Steam Generators (4)

(Primary Side)

RCPCSG-31 RCPCSG-32 RCPCSG-33 RCPCSG-34 RCPCSG-34 SECTION XI CODE RELIEF

- Note

- Note Note

- Note 10

- Note 10 Visual Volumetric Vol umetric Not Applicabl Visual Volumetric &

Surface Not Applicabl, Not Applicabli Not Applicablf Volumetric Visual Visual Visual Volumetric Not Applicablf Volumetric &

Surface L

I I

TABLE IWB-2600 ITEM NO.

No - Note 10 No No No No No No -

Note 11 Yes -

Note I AREA TO BE EXAMINED

INDIAN POINT UNIT NO. 3 NUCLEAR POWER PLANT INSERVICE INSPECTION ASME CODE CLASS 1 COMPONENTS TABLE IWB-2500 EXAMINATION CATEGORY SYSTEM OR COMPONENT CODE APPLICABLE TO CONSTRUCTION AREA TO BE EXAMINED REOU IREMENT RFAI IFSTFfl Y

I EXAMINATION SECTION XI CODE RELIEF REQUIFqTFn Piping Pressure Boundary B31.1 B3.4 B3.5 B3.6 B3. 7 B3.8 83.9 B3.10 B4.1 B4.2 B4.3 B4.4 B4.5 B4.6 B4.7 B4.8 B4.9 B4.10 84.11 Not Applicable Not Applicabli Not Applicabl Not Applicabl Visual Visual Visual Not Applicabl I Not Applicabl Not Applicabl Not ApplicablE Volumetric Volumetric B-G-1 B-G-1 B-G-1 B-H B-1-2 B-P B-G-2 B-F B-G-1 B-G-1 B-G-1 B-J B-J B-J B-J B-K-1 B-K-2 B-P Pressure Retaining Bolting (in place)

Pressure Retaining Bolting (when removed)

Pressure Retaining Bolting Integrally welded supports Vessel Cladding Exempted Components Manway Bolting Safe-end to pipe welds Pressure Retaining Bolting (in place)

Pressure Retaining Bolting (when removed)

Pressure Retaining Bolting Circumferential and Longitudinal Pipe welds.

Brach pipe connection welds exceeding 6" diameter.

Brach pipe connection welds 6" diameter and smaller.

Socket welds.

Integrally Welded Supports.

3upport components.

Exempted components.

Visual' No S

L I

I.

No -Note 10 No -Note 10 4o - Note 10 No - Note 10 No No No No - Note 10 NIo NIo

- Note Note 4o - Note 10 Yes -

Note 13 & 14 res - Note 1 No No es - Note 1(

No No y

TABLE IWB-2600 ITEM NO.

Surface Surface Volumetric Visual

Visual, AREA TO BE EXAMINED

INDIAN POINT UNIT NO. 3 NUCLEAR POWER PLANT INSERVICE. INSPECTION, ASME CODE CLASS 1 COMPONENTS TABLE IWB-2500 EXAMINATION CATEGORY SYSTEM OR COMPONENT CODE APPLICABLE TO CONSTRUCTION AREA TO BE EXAMINED REOI] TRFMFNT RFflI IF~TFfl 1

1 1

r EXAMINATION REQUIREMENT SECTION XI CODE RELIEF RrnlIFqTrn Reactor Coolant Pumps (4)

RCPCP1-31 RCPCP1-32 RCPCP1-33 RCPCP1-34 Valve Pressure Boundary III A B31.1 B16.5 VIII III A B4.12 B5.1 B5.2 B5.3 B5.4 B5. 5 B5.6 B5.7 B5.8 B5.9 B6.1 B6.2 B6.3 B6.4 B6.5 B6.6 B-G-2 B-G-1 B-G-1 B-G-1 B-K-i B-K-2 B-L-1 B-L-2 B-P B-G-1 B-G-1 B-G-1 B-G-1 B-K-i B-K-2 B-M-1 Pressure Retaining Bolting.

Main Flange Bolting in Place Main Flange Bolting when removed Main Flange Bolting Integrally welded supports.

Support Components Pump Casing Weld Pump Casings Exempted Components Seal Housing Bolting Pressure Retaining Bolting (in place)

Pressure Retaining Bolting (when re moved)

Pressure Retaining Bolting Integrally Welded supports Support Components Valve Body Welds INo -.

Note 1 Visual Volumetric Volumetric &

Surface Visual Volumetric Visual Volumetric Visual Visual Visual Not Applicabl Not Applicabl

'i, l

Not Applicabl Not Appl icabl Visual Note-10 i Note-10 No Note-t0 I _________

L I

I TABLE IWB-2600 ITEM NO.

No Yes - NotelE No No - Note 19 No No No No-Note 10 No-Note 10 Not Applicabli No AREA TO BE EXAMINED

Fi4

(

INDIAN POINT UNIT NO. 3'NUCLEAR POWER PLANT INSERVICE INSPECTION, ASME CODE CLASS 1 COMPONENTS TABLE IWB-2500 EXAMINATION CATEGORY SYSTEM OR COMPONENT CODE APPLICABLE TO CONSTRUCTION AREA TO BE EXAMINED T

T I

r B-M-2 B-P B-G-2 Reactor Coolant Pumps (4)

RCPCP1-31 RCPCPl-32 RCPCPI-33 RCPCPI-34 Valve Bodies Exempted Components Pressure Retaining Bolting Flywheels EXAMINATION REQUIREMENT Visual Visual Visual Volumetric &

Visual I.

I I

SECTION XI CODE RELIEF REQUESTED TABLE IWB-2600 ITEM NO.

B6.7 B6.8 B6.9

ASME CODE CLASS 1 COMPONENTS NOTES

1. The examination of these welds as required by IWB-2600 from inside the vessel is restricted by the locations of the adjacent incore instrumentation penetrations.

Examination of those areas accessi ble between the penetrations and conduits may be performed from the outside surface to the extent practical due to radiation levels. Examinations will not be performed if the examiners must receive a whole body dose in excess of 1250 mrem in order to complete any one examination. Examinations will be performed on five percent or ten percent of the total length of each weld as required by the Code. Examination of these welds will be performed at or near the end of the ten-year interval as allowed by the Code.

2. The closure head disc to peel segment weld is completely enclosed within the pattern of CRDM penetrations inside the shroud and is not accessible for examination as required by IWB-2600. This area will be subject to visual examination for evidence of leakage during the performance of system hydrostatic tests.

3. Limited access to the O.D. of these welds is provided by removable plugs in the primary shield above the nozzles and removable insulation covering the nozzle welds. Exception is taken to performing a surface examination on these welds due to anticipated radiation levels and physical access.

4. The Reactor Vessel Closure head studs are removed during each refueling and there will be no for examination in place as required by IWB-2600.

5. The reactor vessel is supported in pads integral with the inlet and outlet nozzles and therefore are excluded from examination requirements of IWB-2500 by category B-H.

6. Radiation levels beneath the closure head may affect the allowable exposure dosage of personnel doing surface and visual examinations.

The presence of the cladding material is not considered when performing the stress analysis of the Vessel such that failure of the cladding would not affect the integrity of the vessel.

The closure head cladding will be volumetrically examined concurrent with the examinations performed on the closure head to flange weld.

7. This requirement is applicable only to Boiling water type Reactors.

8. Six Circumferential welds and five longitudinal welds on the pressurizer are enclosed in a biolo gical and missle shield and therefore are not accessible for examination.

9. The pressurizer nozzles are cast with the upper and lower heads, therefore there are no welds re quiring examination in accordance with the requirement of IWB-2600.

10. There are no items in this category on this component in the Indian Point Unit #3 Class systems.

11.

The steam generator nozzles are cast with the primary head therefore there are no welds requiring examination in accordance with the requirement of IWB-2600.

12.

Examination of the steam generator primary nozzle to safe-end and safe-end to pipe weld is limited both by the nozzle geometry and surface condition and the limited surface preparation on the pipe side of the weld. The surface on the pipe side of the weld, which is a cast elbow, is machined for a distance of approximately three inches from the edge of the weld. Ultrasonic examination is limited to this from the edge of the weld. Examinations can be performed on the surface of the weld but are severly limited from the nozzle side by the rough, as cast surface. Surface examination can be performed on one hundred percent of the weld and the base metal on the pipe side. The con figuration is shown in figure 1.

13. Limitations may occur from the examination of piping system circumferential butt welds (Category B-J) when the welds occur at geometric discontinuities such as pipe to vessel welds, pipe to fitting welds or fitting to fitting welds. For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces. Examination from the fitting side would be dependent upon the geometric configuration. Where elbows or tees are, concerned, examinations can be performed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when it is a valve or a flange. In all cases one hundred percent of the weld material can be examined.

In-instances where welds occur at fitting to fitting, access restrictions as outlined abo~q occur on both sides of the welds. In instances where ultrasonic examinations cannot be performed on one hun dred percent of the volume of the weld and heat affected zone, surface examinations will be performed to supplement the limited volumetric examination.

14. The ninety degree elbows on the crossover leg of the reactor coolant system are fabricated in two halves from austenitic stainless steel castings welded together by the electroslag process. The structure and nature of the electroslag weld in the cast austenitic ninety degree elbows is such that the material is opaque to ultrasonic transmissions utilizing currently available techniques.

Radiography is the only other available technique for volumetric examination.It is not possible to obtain code acceptable radiographs with double wall "shots" on these components which are approximately thirty-eight inches diameter, 3.5 inches wall thickness, containing a two inch thick splitter plate and having radiation levels of up to 300 mr/hr on contact. Surface examina tion could be performed on these welds.

15. The configuration of the reactor coolant branch nozzle connection welds is as shown in figure 2.

Ultrasonic examinations cannot be performed on the surface of the weld. Examinations will be per formed to the extent practical from the pipe and nozzle surfaces adjacent to the weld. Surface examinations will be performed to supplement the volumetric examination.

16. The piping system integrally welded supports are attached to the pipe by fillet welds. The con figuration of such welds is such that examinations cannot be performed to the extent required by IWB-2600 and only the base material of the pipe wall can be examined by ultrasonic technique.

Surface examinations will be performed on the integrally welded attachments to supplement the limited volumetric examinations.

17. The reactor coolant pump main flange bolting is ultrasonically examined in place in accordance with the requirements of IWB-2600, Item B5.1. The main flange bolting will be examined as required by IWB-2600, Item B5.2 whenever a pump is disassembled for maintenance or at the end of the ten year interval when a pump will be disassembled for the performance of examinations required by Category B-L-l.

18.

The structure and nature of the material of integrally welded pump supports is such that it is opaque to ultrasonic transmission. Surface and visual examination will be performed as a sub stitute for volumetric.

19. the reactor coolant pumps casing in the Indian Point Unit #3 plant is a weldment of two cast shells.

The structure and nature of this material is such that it is opaque to ultrasonic transmission.

However the accessible internal surfaces shall be visually and liquid penetrant inspected. Volu metric examinations as required by IWB-2600 can be attempted utilizing radiographic techniques.

Thd success of these examinations (radiographs) will be dependent upon the availability of'.high energy gamma sources and the level of background radi 'ation. Internal fittings on the pump may also provide restriction to the extent if examination that can be performed.

WESTINGHOUSE ELECTRIC CORPORATION FIGURE 1 STEAM GENERATOR PRIMARY NOZZLE SAFE-END TO PIPE WELD CONFIGURATION STEAM GENERATOR NOZZLE INTEGRALLY CAST WITH HEAD

."BUTTERED" SAFE-END REACTOR COOLANT PIPE WELD DEPOSITED CLADDING

WESTINGHOUSE ELECTRIC CORPORATION

-FIGURE 2 BRANCH NOZZLE CONNECTION WELD CENTERL INE NOZZLE NOZZLE FORGING REACTOR COOLANT PIPE

TABLE IWC-2600 ITEM NO.

Cl.1 C1.1 C1.1 C1.1 C1.1 C1.2 C1.2 C1.3 C1.4 C1.1 C1.1 C1.2 C1.3 C1.4 TABLE IWC-2520 EXAMINATION SYSTEM OR CATFr nRY rnMPnNnlrr C-A C-A C-A C-A C-A C-B C-B C.1C C-D C-A C-A, C-B C-C C-D INDIAN POINT UNIT NO NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM ASME CODECLASS 2 COMPONENTS CODE APPLICABLE Tn CONSTRIIrTTnN AREA TO BE EXAMINED REOU IREMENT Rfl FTl Steam Generator (4) Shell Side RCPCSG-31 RCPCSG-32 RCPCSG-33 RCPCSG-34 esidual Heat xchangers (2)

(Tube side)

CAHRS1-31 CAHRC2-32 III-A III-C EXAMINATION Upper head to Shell Weld Upper Shell to Transition Weld Transition to lower shell weld Lower Shell to Stub barrel weld Stub barrel to tubesheet weld Steam Outlet Nozzle to Shell weld Feedwater Inlet Nozzle to shell weld Integrally Welded Supports Manway Bolting Head to Shell Welds Shell to Flange Welds Nozzle to Vessel Welds Integrally Welded Supports Tubesheet Flange Bolting a

I I

SECTION XI CODE RELIEF RrnlIF'Trn Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Not Applicab Visual and Volumetric Volumetric Volumetric Volumetric Surface Visual and Volumetric No No No No No 1 No Note I No No No Yes-Note 2 No No

(-

TABLE IWC-2600 ITEM Nn.

C2.1 C2. 2 C2.3 C2.4 C2.5 C2.6 C3.1 C3.2 C3.3 C3.4 C4.1 C4. 2 C4.3 C4.4 TABLE IWC-2520 EXAMINATION SYSTEM OR CAT mRY enMc'nanr C-F; C-F; C-F; C-D C-G C-G C-G C-E-1 C-E-2 C-F, C-G.

C-D C-E-1 C-E-2 C-F; C-G C-D C-E-I C-E-2 INDIAN POINT UNIT NO.* NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM ASME CODE. CLASS 2 COMPONENTS CODE APPLICABLE Tfl CONSTRUCTION AREA TO BE EXAMINED Tn~

CONSTRUCTIO Piping Systems Residual Heat Removal Pumps (2)

Valves EXAMINATION REQUIREMENT Circumferential Butt Welds Longitudinal Weld Joints in Fittings Branch Pipe-to-Pipe Welds Pressure Retaining Bolting Integrally welded supports Support Components Pump Casing Welds Pressure Retaining Bolting Integrally Welded supports Support Components Valve Body Welds Pressure Retaining Bolting Integrally welded supports Support Components SECTION XI CODE RELIEF RFOIIFSTrn Volumetric Volumetric Volumetric Visual &

Volumetric Surface Visual No Applicable Visual &

Volumetric Not Applicable Visual Not Applicable Visual &

Volumetr16 Not Applicable Visual 4

L I

L L

Yes-Note 3 No Yes-Note 4 No No No No-Note 1 No No-Note 1 No No-Note 1 No No-Note 1 No M rnnRy rnmvnmrmT W WV I vilm ku ll m ui m mm imllm Ell

ASME CODE CLASS 2 COMPONENTS NOTES

1. There are no items in this category for this component of the Indian Point Unit #3 Nuclear Power Plant.

2. The nozzle to vessel welds of the Residual Heat Exchangers are covered by.75" thick by 3" wide re inforcement pads as shown in figure 3. These welds are not accessible for examination by Volumetric or surface methods. The area will be subject to visual examination for evidence of leakage during system pressure tests.

3. Examination of Class 2 piping systems is limited by those occuring at geometric discontinuities such that some limitations may be expected at all locations.

For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces. Examination from the fitting side would be dependent upon the geometric configuration.

,.Where elbows or tees are concerned, examinations can be performed from the fitting side except where the introdos of the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when it is a valve or a flange. In all cases one hundred percent of the weld material can be examined. In instances where welds o

'ccur at fitting to fitting, access restrictions

.as outlined above occur on both sides of the weld. In instances where ultrasonic examinations cannot

• be performed on one hundred percent of the volume of the weld and heat effected zone, surface exam ination will be performed to supplement the limited volumetric examination.

4. The configuration of typical branch pipe to pipe welds is as shown In figure 4. Ultrasonic examination cannot be performed on the surface of the weld.

Examinations will be performed to the extent practical from the pipe and nozzle surfaces adjacent to the weld. Surface examination of the weld will be per formed to supplement the volumetric examination.

WESTINGHOUSE ELECTRIC CORPORATION FIGURE 3 RESIDUAL HEAT REMOVAL HEAT EXCHANGER NC77LF TO VFS-,, Ft CONFIC-, IPATI ON-HEAD FLANGE NOZZLE TO VESSEL WELD

.75" THICK BY 3" WIDE REINFORCE IENT PAD.

NOZZLE 8" (TYPICAL OF TWO)

.75" THICK SHELL AND HEAD

WESTINGHOUSE ELECTRIC CORPORATION Figure 4 BRANCH NOZZLE CONNECTION WELD CENTERLINE NOZZLE NOZZLE FORGING PIPE

Cj SYSTEM Mainsteam System Feedwater System Auxiliary Coolant System COMPONENT DESCRIPTION/IDENTIFICATION Turbine Driven Auxiliary Feedwater Pump 32 Piping Supports Motor Driven Auxiliary Feedwater Pump 31 Motor Driven Auxiliary Feedwater Pump 33 Turbine Driven Auxiliary Feedwater Pump 32 Piping Supports Residual Heat Exchangers (shell side)ACAHRSl-31 Residual Heat Exchangers (shell side)ACAHRS2-32 CODE APPLICABLE TO CONSTRUCTION VIII VIII METHOD OF EXAMINATION Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure Visual/Operating SECTION XI CODE RELIEF REQUESTED INDIAN POINT UNIT' NO. 3 NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS

INDIAN POINT UNIT NO.

-NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS SYSTEM Auxiliary Coolant System COMPONENT DESCRIPTION/IDENTIFICATION CODE APPLICABLE TO CONSTRUCTION FXAMINATTflN RFI TFF DIAhIr~TE'n

~

5 ~5 I

1 METHOD OF FXAMINATMfN SECTION XI CODE Qr1 Trl: DrniIrZTrn Reactor Coolant Pump Reactor Coolant Pump Reactor Coolant Pump Reactor Coolant Pump Spent Fuel Pool Heat Auxiliary Component C Auxiliary Component C Auxiliary Component C Auxiliary Component C Spent Fuel Pit Pump A Spent Fuel Pit Pump A RCPCPCl-31 Lube Oil Cooler RCPCPC2-32 Lube Oil Cooler RCPCPC3-33 Lube Oil Cooler RCPCPC4-34 Lube Oil Cooler Exchanger ACAHSF1-31

ooling Pump 31

ooling Pump 32

ooling Pump 33

ooling Pump. 34 CAPSF1-31 CAPSF2-32 Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure I

i L

9 INDIAN POINT UNIT NO. 3 NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS SYSTEM Auxiliary Coolant System COMPONENT DESCRIPTION/IDENTIFICATION CODE APPLICABLE TO CONSTRUCTION METHOD OF EXAMINATION r

T V

Spent Fuel Pit Strainer ACSRSF1 Residual Heat Removal Pump ACAPRHI-31 Seal Heat Exchanger Residual heat Removal Pump ACAPRH2-32 Seal Heat Exchanger Component Cooling Surge Tank ACATCCl-31 Component Cooling Surge Tank ACATCC2-32 Component Cooling Heat Exchanger ACAHCCl-31 Component Cooling Heat Exchanger ACAHCC2-32 Component Cooling Pump ACAPCCl-31

,Component Cooling Pump ACAPCC2-32 Component Cooling Pump ACAPCC3-33 Safety Injection Pump SAPSll-31 Oil Cooler Safety Injection Pump SlAPS12-32 Oil Cooler VIII VIII VIII Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure L

I ______________

I SECTION XI CODE RELIEF REQUESTED

INDIAN POINT UNIT NO. 3 IUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS SYSTEM Auxiliary Coolant System Service Water System Service Water COMPONENT DESCRIPTION/IDENTIFICATION COSRCIN EXAMINATION RLF FIFTf I

Safety Injection Pump SlAPS13-33 Oil Cooler Recirculation Fan 31 Cooler Recirculation Fan 32 Cooler Recirculation Fan 33 Cooler Recirculation Fan 34 Cooler Service Water Pumps 34 (Nuclear) 35 36 Service Water Pumps 31 (Conventional) 32 33 Component Cooling Heat 31 Exchangers (Tube Side) 32 CODE APPLICABLE TO CONSTRUCT ION METHOD OF 0

SECTION XI CODE RELIEF RFAIIESTrn I

_I

_I_

Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure

COMPONENT DESCRIPTION/IDENTIFICATION CODE APPLICABLE TO CONSTRUCTION METHOD OF EXAMINATION SECTION XI CODE RELIEF REQUESTED Diesel Generator Lube Oil Coolers Piping Supports & Hangers Spray Additive Tank BlATSAl-31 Piping IIIC Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure Visual/Operating Pressure Supports Visual SYSTEM Safety Injec ection System INDIAN POINT UNIT NO. OUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS

INDIAN POINT UNIT 3 INSERVICE TESTING PUMPS The enclosed tabulations provide a listing of the Class 1, 2 and 3 pumps which are subject to the testing requirements of Subsections IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, with Addenda thru the Summer of 1975.

This tabulation identifies the pumps to be tested, code class, test flow path system resistance, and required test quantities and frequencies.

Relief from test requirements is requested in cases where their test requirements have been determined to be impractical.

Where relief is requested, technical justification is provided along with alternative test methods when applicable.

The recirculation pumps require that the recirculation sump be filled with water and the pumps run with recirculation back to the sump. This test will be conducted each refueling outage.

0 INDIAN POINT UNIT Pt".

3 NUCLEAR POWER PLANT INSERVICE TEST PROGRAM ASME CODE CLASS 1, 2 AND 3 PUMPS IASME CODE TEST SECTION XT CODE PUMP IDENTIFICATION PUMP DESCRIPTION CLASS_]

MEASURED PARAMETERS IINTERVAL RELIEF REQUESTED ACAPRHI-31 ACAPRH2-32 34 35 36 SIAPCS1-31 SIAPCS2-32 Residual Heat Removal Pumps Nuclear Service Water Pumps Containment Spray Pumps I

N/A N/A Monthly N/A Monthly Monthly Yearly N/A Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Pol Flow Rate Vibration Amplitude Bearing Temperature Lubricant Level or Pressure Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po)

Flow Rate Vibration Amplitude Bearing Temperature Lubricant Level or Pressure Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po)

Flow Rate Vibration Amplitude Bearing Temperature Note 2 Note 2 Note 9 Note 10 Yes-Note 4 Yes-Note 5 Yes-Note 6 Yes-Note 6 Yes-Note 1 Note 2 Note 2 No Note 9 N/A Monthly Monthly Monthly Monthly Monthly Yearly Monthly N/A Monthly N/A N/A Monthly Monthly Yearly

INDIAN POINT UNIT ' 0. 3 NUCLEAR POWER PLANT INSERVICE TEST PROGRAM ASME CODE CLASS 1, 2 AND 3 PUMPS ASME CODE TEST SECTION XI CODE PUMP IDENTIFICATION I

PUMP DESCRIPTION CLASS MEASURED PARAMETERS INTERVAL RELIEF REQUESTED SIAPSI 1-31 SIAPS12-32 SIAPSI3-33 I

I I

Safety Injection Pumps I Recirculation Motor Driven Auxiliary Feedwater Pump Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po:

Flow Rate Vibration Ampl itude Bearing Temperature Lubricant Level or Pressure Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po)

Flow Rate Vibration Amplitude Bearing Temperature Lubricant Level or Pressure Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po)

Flow Rate Vibration Amplitude Bearing Temperature U,

N/A Monthly N/A N/A Monthly Monthly Yearly Monthly N/A N/A N/A Yearly Yearly Yearly N/A Monthly Monthly Monthly Monthly Monthly Yearly No Note Note No Note Note Yes-Note 3 Note 2 Note 2 Yes-Note 3 Note 9

INDIAN POINT UNIT N.

3 NUCLEAR P.OWER PLANT INSERVICE TEST PROGRAM ASME CODE CLASS 1, 2 AND 3 PUMPS ASME CODE TEST SECTION XI CODE PUMP IDENTIFICATION PUMP DESCRIPTION CLASS MEASURED PARAMETERS INTERVAL RELIEF REQUESTED 31 Conventional Service 3

1.

32

-Water Pumps 9

Turbine Driven Auxiliary Feedwater Pump Auxiliary Component Cooling Pumps Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po).

Differential Pressure (Pi-Po:

Flow Rate Vibration Amplitude Bearing Temperature Lubricant Level or Pressure Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po)

Flow Rate I

Vibration Amplitude Bearing Temperature Lubricant Level or Pressure Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po)

Flow Rate Vibration Amplitude Bearing Temperature r

U N/A Monthly Monthly Monthly Monthly Monthly Yearly Monthly Monthly Monthly Monthly Monthly Monthly Monthly Yearly Monthly N/A Monthly Yearly MIA Yes-Note 4 Yes-Note 5 Yes-Note Yes-Note Yes-Note 11 Yes-Note Yes-Note Yes-Note Yes-Note Nnt in

INDIAN POINT-UNIT i., 3 NUCLEAR POWER PLANT INSERVICE TEST PROGRAM ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP IDENTIFICATION PUMP DESCRIPTION A SME CODE TEST SECTION XI CODE PUMPIDNTIFIA ION PUMDESRIPTI CLASS MEASURED PARAMETERS INTERVAL RELIEF REQUESTED I

I I

ACAPCCl-31 ACAPCC2-32 ACAPCC3-33 Component Cooling Pumps Speed (if variable)

Inlet Pressure (Pi)

Outlet Pressure (Po)

Differential Pressure (Pi-Po:

Flow Rate Vibration Amplitude Bearing Temperature Lubricant Level or Pressure N/A Monthly Monthly Monthly Yearly Monthly Yes-Note 3 No Yes-Note 3 Note 7

INSERVICE TESTING OF PUMPS PROGRAM NOTES

1. The system as designed and installed does not contain instrumentation for the measurement of pump inlet pressure.- Under the conditions that.....

the pump performance test will be carried out, with low flow conditions on recirculation "miniflow," the head losses in the inch diameter suction piping will be extremely small and inlet pressure can be taken from the head of water above the pump suction in the RWST.

2. Under the operating mode in which these pumps will be tested, the system will have fixed resistance. As allowed by footnote 1 of Table IWP-3100-1, this parameter will not be recorded.

3. There is no instrumentation to monitor this operating parameter in the plant system as designed and constructed.------

4. The service water pumps are vertical design with no means of direct inlet pressure measurement as required by IWP-4200. Inlet pressure to these pu.ps will be established by reference to the level of water above the pump suction. As the measurement of the level of water above suction is to be used to determine the inlet pressure, relief is required from meeting pressure tap construction and location requirements of IWP-4211 and IWP-4212.

5. Three pumps are in continuous operation for both the essential and non-essential loads during all modes of plant operation. The service load for these pumps constantly varies with plant power load, plant operating status, river water and ambient air temperatures and it is not possible to ensure that flow and head parameters will be the same at any two monthly performance tests.

Flow measurement instrumentation Is only installed in this system at the outlets from the containment ventilation coolers and flow measurements will be taken at this point.

6. The service water pumps are open line shaft pumps that depend primarily of the liquid being pumped for the lubrication of the pump and line shaft bearings. All pump bearings are submerged and lubricant is allowed to leak off into the sump and is not piped back, such that bearing or lubricatn outlet temperature cannot be monitored.

7. A minimum of two component cooling pumps are in continuouS-use during all modes of plant operation and as the service load for these pumps constantly varies with plant power load, plant operating status and water and ambient air temperatures, it is not possible to ensure that flow and head parameters will be the same at any two monthly performance tests or to measure these parameters for a Single operating pump.

8. Instrumentation is provided for monitoring temperature of the pump thrust bearing only. No temperature measuring devices are installed at the radial bearing.

9. The monthly performance test will generally be conducted with re circulation "mini-flow" conditions. Under these high head, low flow conditions the pumps are expected to vibrate considerably more than under full flow conditions. Accurate vibration readings will be taken each refueling outage when full system flow tests are run.

10.

Pump bearings are carried in the driver motor and are grease lubricated.

11.

When the pump is tested on recirculation flow, the flow path is a fixed resistance system and it is required to measure AP or Q, not both (Table IWP-3100-1). When the pump is tested during normal operation, the flow path is a variable resistance system and it is required to measure both AP and Q.

INDIAN POINT UNIT 3 INSERVICE TESTING OF VALVES The enclosed tabulation provides a listing of the Class 1, 2 and 3 valves which are subject to the testing requirements of Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, with Addenda thru the Summer of 1975.

This tabulation identifies the valve to be tested, drawing location, fun ction, code class, category, size, valve type, actuator type, normal position and test requirements. Relief from test requirements is requested in cases where these test requirements have been determined to be impractical.

Where relief is requested, technical justification is provided along with alter native test methods when applicable.

Leak testing of containment isolation valves shall be performed in accordance with Appendix J of IOCFR50 in lieu of ASME Section XI subsub-article IWV-3420.

A separate tabulation of containment isolation valves which are not included in the IWV Program is provided.

Any inspection requirements identified as impractical during the course of the inspection period will be noted and included in the inspection program at the time of the next revision.

When one valve in a redundant safety related system is found inoperable during testing, nonredundant valves in the remaining train will not be cycled as procedures required, but will be cycled after the first inoperable valve in the system is returned to service.

This valve testing program addresses those valves for which demonstration of operability is necessary to assure safe shutdown of the unit or mitigation of the consequences of an accident. The program has been re viewed to assure that testing the valves at the intervals specified will not place the plant in an unsafe condition. Where practical, valves will be cycled at 3 month test intervals.

When a commitment is made to test valves during hot or cold shutdown, it is not intent to shutdown the unit soley for the purpose of valve testing nor to perform the testing more often than once per 92 days due to more frequent shutdowns.

The following clarification shall apply to those valves which are scheduled to be exercised during cold shutdown:

"Valve testing shall commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown and continue until complete or unit is ready to return to power. Completion of all valve test i'ng is not a prerequisite to return to power."

Article IWV-3520(b) requires that check valves be exercised to the position required to fulfill their function. Check valves in the Indian Point plant systems are not equipped with position indicating devices and verification of operation to the required position will be achieved by observing that

.....normal required flows are established in the systems.

The stroke times of solenoid controlled, air operated valves is both extremely rapid and subject to considerable variation. Exception is taken to complying with stroke time variations defined by Article IWV-3410(c)(3).

LEGEND TEST REQUIREMENTS SP -

SETPOINTS of safety and relief valves shall be tested per Section XI subsubarticle IWV-3510 or as modified by specific relief request.

VP - VALVE POSITION shall be verified per Section XI subarticle IWV-3700 S.. or as modified by specific relief request.

CV - CHECK VALVES shall be exercised at least once every (3) months per Section XI subsubarticle IWV-3520 or as modified by specific relief request.

LT -

LEAK TESTS shall be performed per Section XI subsubarticle IWV-3420 or as modified by specific relief request.

EV - EXERCISE VALVE for operability at least once every (3) months per Section XI subsubarticle IWV-3410 or as modified by specific relief request.

ST - STROKE TIMES shall be measured per Section XI subsubarticle IWV-3410 or as modified by specific relief request.

VALVE POSITIONS VALVE TYPES ACTUATOR TYPES 0 - Open CK-Check SA-Self Actuating C - Closed SF-Safety MO-Motor OC-Open or Closed DA-Diaphragm AO-Air Operated LO-Locked Open SW-Swing Check MA-Manual LC-Locked Closed GL-Globe GA-Gate BU-Butterfly NG-NR Gate SD-Swing Disc AG-Angle Globe

• 7'

_6i Mat nsteam LOCATION DRAWING NUMBER CODE FUNCTION CLASS 9321-F-201 73 SIZE CATEGORY (INS.)

VALVE NOIIAL TYPE ACTUATOR POS.

MS 1-31 MS 1-32 MS 1-33 MS.1-34 MS-2 MS-2 MS-2 MS-2 MS-45 MS-46 MS-47 MS-48 MS-49 MS-45 MS-46 MS-47 MS-48 MS-49 MS-45 MS-46 MS-47 MS-48 MS-49 MS-45 MS-46 MS-47 MS-48 MS-49 MS-41 MS-42 PCV-1 31 OA 1

T T

I I

1-9 C-3 A-3 E-3 F-3 A-4 C-4 E-4 F-4 A-2 A-2 A-3 A-3 A-3 C-2 C-2 C-3 C-3 C-3 D-2 D-2 D-3 D-3 D-3 F-2 F-2 F-3 F-3 F-3 D-2 D-2 C-4 Main Steam Isolation Mainsteam Check Main Steam Safety Steam to Auxy FW Pump Steam to Auxy FW Pump A

5 1

4 SYSTEM VALVE NUMBER PAGE 1

TEST REQ.

RELIEF REQUEST Note 1 Note 1 0

0 C

0 C

SYSTEM Mainsteam DRAWING NUMBR 9321-F-20173 PAGE 2

VALVE IRwG.

CODE SIZE VALVE NOMI4AL TEST RELIEF NUMBER ICTION FUNCTION CLASS CATEGORY (INS.) TYPE ACIUATOR POS.

REQ.

RI3QJES I

I "1E PCV-131 OD MS-52 PCV-1139 B-4 A-6 A-5 A-5 Steam to Suxy FW Pump Steam to Auxy FW Pump Auxy Steam Safety Valve Steam to Ausy FW Pump

.1 4

.1 1 ___________

SYSTEM Condensate & Boiler Feed PAGE 3

SIZE VALVE (INS.)

TYPE NOL TEST ACTU1ATOR POS.

REQ.

REQUEST a.-

1 I

T I

I T

I Safety Valve Aux FW Suction from Storage Tk.

I ___________________

I ____

I I ___

I I

I ___

I ____

FUNCTION VALVE NUMBER LOCATION CODE CLASS

-2.

C-2 D-2 C-2 C-2 D-2 CATEGORY RELIEF SA SA Note 2 9321-F-20183 DRAWING NUMIBER

SYSTEM Service Water DRAWING NUMBER 9321-F-27223 PAGE 6

VALVE 1IG.

CODE SIZE VALVE NOIRMAL TEST RELIEF NUMBER LOCATION FUNCTION CLASS CATEGORY (INS.) TYPE ACTUATOR POS.

REQ.

REQEST SWN-1 1-3 Service Water Pump 3

C 14 CK SA OC CV Note 5 SWN-l 1-4 Discharge SWN-1 1-4 SWN-1 I-5 SWN-1 1-6 SWN-I 1-6 SWN-10O F-5 Service Water to 3

C 24 CK SA 0

CV Note 5 SWN-100 F-6 Nuclear Plant TCV-103 B-9 Discharge from Fan 3

B 8

BU AO 0

EV TCV-104 A-9 Coolers 18 FO ST TCV-105 A-9 10 FCV 1176 H-10 Discharge from Diesel 3

B 6

BU AO 0

EV FCV 1176A G-10 Coolers ST 5-I L

I I

I L

I

N 0

SYSTIEM Feedwater DRAWING NUMBER 9321-F-20193 PAGE 4

VALVE IVG.

CODE SIZE VALVE NOWL TEST RELIEF NUMBER LOCATION FUNCTION CLASS CATEGORY (INS.) TYPE ACTUATOR POS.

REQ.

REQ1JE Feedwater to Steam Generator BFD BFD BFD BFD 2

L U

I...

I 4

t ___________

I B-2 C-2 E-2 G-2 1-6 1-4 E-2 G-2 B-2 H-7 1-3 1-2 1-4 1-3 I-9 I-9 1-10 1-10 1-10 1-10 I-9 I-9 1-2 1-3 1-3 1-4 Note 3 Note 4 Note 4 Note 4.

Note 4 Note 4 BFD 34 BFD 39 BFD BFD BFD BFD BFD 31 Discharge from Motor Driven Aux FW Pumps Auxy FW Supply Discharge from Steam Driven Aux FW Pump Aux FW Discharge Aux FW Control BFD BFD BFD BFD BFD BFD BFD BFD FCV FCV FCV FCV FCV FCV FCV FCV 35 37 40 42 47 47 47 47 405A 405B 405C 405D 406A 406B 406C 406D

i.e Auxiliary Coolant DRAWING NUMBER 9321-F-27203 CODE FUNCTION CLASS SIZE VALVE CATEGORY (INS.)

TYPE NOMAL TEST ACTUATOR POS.

REQ.

I 1

I -__

I-'

I RHR Safety Relief RHR Pump Discharge to HT.

Exchanger RHR Ht. Xchr. Inlet RHR Take Off from RCS RHR Pump Discharge to Ht. Xchr. #2.

L L

j 1

1 L

1.

L ____

L SYSTEM VALVE NUMBER 0

LOCATION

)

1836 741 742 730 731 745A 745B B-2 H-i H-3 B-2 B-2 1-4 H-3 PAGE 5

RELIEF REQUEST Note 8 Note 8

Steam Generator Blowdown O

LOCTION DRAWING NUM41BER 9321-F-27293 CODE FUNCTION CLASS SIZE VALVE CATEGORY (INS.)

TYPE I

I T

1 G-6 G-6 F-6 F-6 B-6 D-6 C-6 D-6 Steam Gen. Blowdown S. G. Blowdown Sample 2

1/2 GA GL I

SYSE VALVE NU4BER Pcv Pcv Pcv Pcv Pcv Pcv Pcv Pcv 1214 121 1216 1217 1223 1224 1225 1226 PAGE 7

ACTIJATOR

NOtMA, POS.

TEST REQ.

RELIEF REQEST

Safety Injection DRAWING MMER 9321-F-27353 PACE 8

VALVE

[V.

(CODE SIZE VALVE NOM TEST RELIEF N BER IOCATION FRNCION CLASS CATEGORY (INS.)

TYPE ACIUATOR POS.

REQ.

RD3UEST 857A 857Q 857S 857U 857B 857H 857C 857D 857E 857F 857J 857K 857L 857M 857G 857R 857T 857W 857N 857P 892A 892B 892C 892D 889A 889B 1802A 1802B High Head STS to Cold Leg High Head SIS to Hot Leg Boron Injn. to Cold Leg High Head SIS to Cold Leg Boron Inj. to Cold Leg Accumulator Safety Relief RHR Disch. to Spray Header Recirc. Pump Discharge C

C C

C C

C B

B A

L__________ L ____________ I ____________

Note 6 Note 6 Note 6 Note 6 Note 6 Note 7 Note 7 B-1 B-2 B-1 C-1 C-1 C-1 B-2 C-2 C-2 C-2 B-2 A-2 A-2 A-2 D-1 D-2 0-1 D-1 D-5 D-7 F-8 F-9 H-7 H-8

Safety Injection DRAWING NMBER LOCATICN FUNCTION MOE CLASS 9321-F-27353 PAGE 9

SIZE VALVE CATEGORY (INS.) TYPE NOCIA, TM.

T ACIVIUR POS.

PE Q.

III I

1 11 I

T

-0 1869A 1869B 897A 897B 897C 897B 895A 895B 895C 895D 886A 886B 746 747 899A 899B 733A 733B 838A 838B 838C 838D I ___________

I. _______I~

I I ________

I.

sYST VALVE NUMBER RELIEF G-9 G-9 G-1 H-i I-1 I-1 G-3 G-4 G-5 G-6 H-7 H-8 H-8 G-7 H-8 G-7 G-8 G-7 G-3 H-4 I-5 1-6 RHR Cooler Outlet to SIS Pump Suction Accumulator Discharge to Cold Leg Recirculation Spray Pump discharge RHR Return & Low Head Injection to Cold Legs RHR Ht. Xchr. outlet Pressure Relief RHR Return & Lbw Head Injection to Cold Legs 6

10 8

8 3/4 6

MO SA SA MO SA SA Note 8 Note 9 Note 8 a

4 SYSTEM Sampling DRAWING NUMBER 9321-F-27453 SIZE CATEGORY (INS.)

VALVE TYPE NORMAL TST ACIUATOR POS.

REQ.

I I

4hhA RA 956C 956E 959 990A 990C B-4 C-4 E-3 C-4 E-3 R.C. System Samples RHR Sample Reclrc. Pump Disch.

Sample RHR Sample I

I I~-----r---,

3/4 3/4 3/4 3/8 GL GL GL GL

-I ________I L ______

I I

I _______

I ________

I.

FUNCTION VALVE NUMBER LOCATION ODE CLASS PAGE 10 RELIEF REQUEiST

-I Reactor Coolant LOCATION DRAWING NMBER 9321-F-27473 FUNCTION CODE CLASS CATEGORY SIZE VALVE (INS.)

TYPE PAGE 11 NII1lMAL TEST RELIEF SYST M VALVE

?JMBER ACTUATOR POS.

1 1

I Pressurizer Safety Pressurizer Relief Pressurizer Relief

_________________ I ___________________________________________________ --I ____________ I ______________ I

~

I __________ I REQ.

REQUJEST PCv PCv PCv 464 466 468 B-12 B-11 B-10 B-1 3 B-1 3 B-14 B-4 535 536 PCV 455C PCV 456 SP EV ST EV

w w

SYSTJ Safety ~n~jectlon VALVE M J4ER M.

LOCTION DRAWING NUIMBfR CODE FUNCTION CLASS 9321 vF.27503.

SIZE VALVE CATUORY (INS.) TYPE PAGE NORNAL TEST ACIJATOR POS.

REQ.

I I

I T

T 847 881 846 850A 850B 856A 865B 869A 869B 1841 1839A 1839B 867A 867B 876A 876B U

I.-

A- ___________

______________ I 12 RELIEF REQUST C-g H-9 B-i0 D-7 B-7 F-8 G-8 F-1 G-1 F-3 F-7 G-7 F-4 G-4 E-4 F-4 SIS Pump Suction RHR Pump Suction RWST Outlet SIS Pump Discharge Spray Pump Suction Containment Spray Pump Discharge Spray Additive to Eductors Containment spray pump Discharge Spray Additive to Eductors Note 10 Note 2 Note 11 Note 12 o

i Ah J

SYSTEM Safety Injection DRAWING NUMBER 9321-F-27503 PAGE 13 VALVE 13M.

CODE SIZE VALVE NOR44L TEST RELIEF NUMBER ILCATION FUNCTION CLASS CATEGORY (INS.)

IYPE ACTIJATOR POS.

REQ.

RIXUEST 1838A F-7 Spray Additive to 2

C 3

CK SA C

CV Note 13 1838B G-7 Eductors 885A J-2 RHR Pump Suction from 2

B 14 GA MO C

EV 885B J-3 Containment Sump 849A D-7 SIS Pump Discharge 2

C 4

CK SA C

CV Note 9 849B B-7 852A D-7 852B C-7 848A D-g SIS Pump Suction 2

E 6

GA MA LO VP 848B C-9 1835A B-2 Boron Injection Tank 2

B 4

GA MO C

EV 1835B B-2 Inlet and Outlet ST 1852A B-7 1852B C-7 1851A C-6 BIT Recirc return to 2

B 2

GL AO 0

EV 1851B C-6 BA Tanks FC 1823 B-3 BIT Safety Relief 2

B 3/4 SF SA C

SP 1840 B-6 BIT Recirc from BA 3

E 2

GA MA LO VP Transfer Pumps 1846 C-S Drain to Hold Up Tanks 2

E 2

GA MA LC '"

VP 888A G-3 RHR Ht. Xchr. Outlet to 2

B 6

GA MO C

EV 888B H-3 SIS Pump Suction ST 866A F-6 Containment Spray 2

B 8

GA MO OC EV a66B G-6 Pump Discharge ST 851A D-7 SIS Pump Discharge 2

B 4

GA MO OC EV

Safety Injection DRAWING NUMBER 9321-F-27503 PAGE 14 CODE FUNCT ON CLASS SIZE CATEGORY (INS.)

VALVE NOIM L TYPE ACTUATOR POS.

TYPE AGflJAThR POS.

REQ.

RE~~JES~

I t

1 I

1T f

BIT Bypass Test Line Spray System Recirc.

"Mini-Flow" 818B 1833A 1833B 859A 859C 878A 878B 1814A 18148 1814C 882 887A 887B 8738 1806A 1806B 1819A 1819B 1919C 1807A 1807B 1807C C-7 B-2 B-2 A-2 A-3 F-2 G-2 E-1 E-1 E-1 I-9 D-9 D-9 F-5 F-7 G-7 E-9 D-8 B-9 D-8 C-8 B-8 Bleed Off Recirc "Mini-3/4 3/4 3/4 3/4 12 6

2 3/4 3/4 3/4 GL GL GL GL GA GA GL GL GL GL MA MA MA MA MO MO MA MA MA MA TEST RELIEF REQUEST Note 14 I _____________________________________________

I I ________

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I.

I ________

I ___________

I.

LOCTION SYSTE VALVE NUMBER Containment Pressure Sensing RHR Pump Suction from RWST SIS Pump Suction Spray Additive Line Flush Test Line SIS Pump Recird.

SIS Pump Flow 7--W

SAuxiliary Coolant DRAWING NUMIBER 9321-F-27513 PAGE CODE FUNCrION CLASS SIZE VALVE CATEGORY (INS.)

TYPE ACTUATOR IT I

T I

1 755A 755B 755C 755D 755E 755F 761A 761 B 761 C 738A 738B 739A 739B 735A 735B 751A 751 B 791 793 798 796 743 744.

B-6 B-6 B-6 B-4 B-4 B-3 H-7 1-7 I-7 D-8 C-8 D-8 C-8 D-9 C-9 H-14 G-14 B-7 B-5 C-7 A-5 B-I0 H-14 U ____________

L

-.1 ________

£ _________

L ______

1 1

I ________

7*

IOCATION 15 NOIRAL POS.

TEST VALVE MN4BER Aux. CC Pump Discharge CC Pump Discharge RHR Pump Discharge RHR Pump Discharge RHR Pump Suctfon SW to RHR Ht Xchr. #1 Sw to RHR Ht Xchr. #2 SW Supply and return XS Letdown Ht. Xchr.

SW to XS Letdown Ht. Xchr.

Recirc Sump to RHR Pump Suction RHR Pump Discharge to Ht. Xchr.

CK CK CK GA GA CK CK DA GL GL GA RELIEF~

Note 15 Note 15 Note 2 Note 16 Note 16 SA SA SA MA MA SA SA AO AO MO MO CV CV CV VP VP CV CV EV Lt EV LT EV LT ST EV ST

Auxiliary Coolant nDtAWTKIi l mmfln Q31-F-97RI2 L'E~~~IUI1IBJ 1 19.UUI

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VALVE NUMBER 1870 732 769 784 786 797 FCV 625 750A 750B 750C 750D 7 50E 752F 752J 753F 753J 789 822A 822B 832A 832B lOCATION B-l0 B-9 D-14 D-13 D-13 E-14 C-14 1-6 1-10 J-10 C-8 D-8 H-14 F-14 F-13 B-12 G-14 F-14 F-l0 F-9 SW from RC Pumps SW to RHR Ht. Xchrs.

CC Surge Tank Outlet FUNCTION Recirc Sump to RHR Pump Suction RHR Pump Suction SW to RC Pumps SW from RC Pumps SW to SIS Pump Coolers SW to RHR Pump Seals SIZE CATE ORY (INS.)

ODE CLASS 2

2 3

3 3

3 3

3 3

3 VALVE TYPE ACTUATOR A

A A

A C

C A

B B

E GA GA GA GA CK CK(

GL GA GA GA NOW TPST Pos.

REQ.

MO MA MO MO SA SA MA MO MO MA 0

0 LO C

C 0

0 0

0 0

PAGE 16 EV LT ST EC LT EV LT ST EV LT ST CV CV LT EV EV ST SW to Recirc Pump Coolers RELIEF REBJE~r Note 17 Note 17 Note 18 Note IT

Auxiliary Coolant O

DRAWING NUMBER 9321 -F-27513 SYSTEMI VALVE NUMBER IOIDE CLASS SIZE VALVE CATFGORY (INS.) TYPE ACTJATOR 1

1 1

3 a ___________

CC Surge Tank Relief CC Surge Breaker Tank Vacuum I ________

L I

L 7"

FUNCTION 835A 835B TK31 TK32 E-9 E-8 F-9 F-8 PAGE 17 NORM4AL Pos.

TEST RMQ.

RELIEF REWES17

INDIAN POINT UNIT 3 INSERVICE TESTING OF VALVES PROGRAM NOTES

1. Closure of mainsteam stop valves during normal operation would result in turbine and reactor trips. These valves are fully stroked to a closed position each time the plant goes to a cold shutdown condition and are re-opened again on plant startup.

2. Verification that check valves open as required will be observed when pump discharge flow is established during the conduct of monthly performance test required by IWP.

3. Closure of main feedwater stop valves during normal operation would result in a reactor trip. These valves are fully stroked to a closed position each time the plant goes to a cold shutdown condition and are reopened again on plant startup.

4. Operation of valves in the auxiliary steam and feedwater systems will be verified when the pump is operated flow during a monthly performance test. Operation of these valves will also be verified at each cold shutdown. During plant start-up and shutdown, steam generator feed is provided by the auxiliary feedwater system and operation of the check valves in the auxiliary feedwater lines will be verified at cold shutdown when flow is established.

5. A minimum of two service water pumps are in use during all modes of plant operation and check valves in the pump discharge would remain passively open. Verification that the check valve opens and normal flow is established will be achieved whenever an inactive pump is put into operation for periodic performance testing as required by IWP.

6. Operation of this normally closed check valve will be verified each refueling outage. Operation will be verified by initiating and

observing that flow is established through the systepj, Partfl stroking of these check valves could only be achieved by intro ducing safety injection flow into the RCS.

Paragraph IWV-341OCb) requires that normally closed valves that cannot be operated during normal plant operation shall be specifically identified and shall be full-stroke exercised during each cold shutdown. Certain Valves subject to this limitation have been identified in the table as being exercised at each refueling outage. The term "cold shut down" covers a wide variety of plant conditions which can exist with the reactor coolant temperature equal to, or less than, 200*F.

Under cold shutdown conditions, the system may be "solid" such that introducing flow into the system to exercise check valves would have a high probability of overpressurizing the system.

These tests can only be performed when the reactor coolant system is vented to the containment atmosphere and partially drained as for a refueling outage or for maintenance requiring access into the reactor coolant system.

7. Failure of these valves in an open position would result in the loss of availability of the RHR system for its function of cooling down the reactor system. Valves associated with the RHR system not in operation will be exercised during cold shutdown.

8. Valves in the RHR system will be exercised each time the system is put into operation during the cooldown and shutdown of the reactor coolant system. The RHR system is put into operation as a standard operating procedure whenever the reactor coolant temperature is to to reduced below 350°F and the pressure is below 400 psig.

9. Verification that check valves open as required will be observed when pump discharge flow is established during the conduct of the performance test required by IWP at each refueling outage.

10. This check valve will be partially.stroked during each monthly pump performance test. The valve will be full stroked during the

full system test at each refueling.

11.

The check valve will be partially stroked during each monthly pump performance test.

Full flow tests cannot be accomplished without fluid being sprayed into the containment.

12. Prior to exercising these valves, the locked open, manually operated diaphragm valve 1841 at the outlet of the spray additive tanks must be closed and the line flushed with water to prevent corrosive spray additive being introduced into the system when valves 876A or B are opened. This test will be performed at each refueling outage.

13. Verification that these check valves open as required will require that the locked closed, manually operated valve 873B, be opened to provide a fluid flow path for testing. This test will be carried out at each refueling outage.

14. Valve is normally open with power removed during normal operation.

Power will be restored and valve operability checked at each cold shutdown.

1'5.

The check valve in the discharge line of the operating component cooling pump or the auxiliary component cooling pump will remain passively open during plant operation. Verification that check valves open and normal flow is established will be achieved when ever an inactive pump is put into operation for plant service or for the periodic performance test required by IWP.

16. This check valve is passively open with continuous flow through the system. Verification that this valve remains In the open position as required for the fulfillment of its safety function will be achieved by monitoring system flow.

17. Auxiliary cooling water flow to the reactor coolant pumps is re quired at all times the pumps are in operation. Failure of one

of these valves in a closed position during cycling would result in a loss of the cooling flow to the pump. Power operated valves in these systems will be cycled at cold shutdowns when the reactor coolant pumps are inoperative.

18. This is a manually operated valve which remains in an open position during normal plant operation and is required to remain open for service water supply to the reactor containment ventilation coolers or recirculation pumps to mitigate the consequences of an accident.

The system is missile protected and designed to remain intact under post LOCA conditions and, in effect, is an extension of the con tainment. Valves will be exercised when closed for leak testing.

CONTAINMENT ISOLATION VALVES SA 24 Service Air SA 24 Service Air IA 39 Instrument Air PCV 1228 Instrument Air l890A Containment Sampling 189gB Containment Sampling 1890C Containment Sampling 1890D Containment Sampling 1890E Containment Sampling 1890F Containment Sampling 1890G Containment Sampling 1890H Containment Sampling 1890J Containment Sampling 1610 Waste Disposal 1616 Waste Disposal 1786 Waste Disposal 1787 Waste Disposal 1788 Waste Disposal 1789 Waste Disposal 1702 Waste Disposal 1705 Waste Disposal 1723 Waste Disposal 1728 Waste Disposal SWN 43 Service Water SWN 43 Service Water SWN 43 Service Water SWN 43 Service Water SWN 43 Service Water SWN 41 Service Water SWN 41 Service Water SWN 41 Service Water SWN 41 Service Water SWN 41 Service Water SWN 44 Service Water SWN 44 Service Water SWN 44 Service Water SWN 44 Service Water SWN 44 Service Water SWN 51 Service Water SWN 51 Service Water SWN 51 Service Water SWN 51 Service Water SWN 51 Service Water SWN 71 Service Water SWN 71 Service Water SWN 71 Service Water SWN 71-Service Water SWN 71 Service Water 863 Nitrogen to Containment 891A Nitrogen to Accumulators 891B Nitrogen to Accumulators 891C Nitrogen to Accumulators 891D Nitrogen to Accumulators 201 Letdown Flow 202 Letdown Flow 205 Charging Flow 222 Seal Return Flow 226 Charging Flow 227 Charging Flow 250A Seal Injection 250B Seal Injection 250C Seal Injection 250D Seal Injection 241A Seal Injection 241B Seal Injection 241C Seal Injection

\\

I CONTAINMENT ISOLATION VALVES (Continued) 241 D 965B 965D 965F 965G 965H 990B PCV 1 PCV 1 PCV 1 PCV 1 PCV 1 PCV 1 PCV 1 PCV 1 1875A IV3A 1876A IV5A 1875B H2 H2 H2 H2 H2 Seal Injection Sampling System Sampling System Sampling System Sampling System Sampling System Sampling System 214A S. G. Blowdown 215A S. G. Blowdown 216A S. G. Blowdown 217A S. G. Blowdown 223A S. G. Blowdown 224A S. G. Blowdown 225A S. G. Blowdown 226A S. G. Blowdown Recombiner Recombiner Recombiner Recombiner Recombiner 519 580A 580B UH37 UH38 Primary Water to PRI Pressurizer Deadweight Pressurizer Deadweight Aux Stm & Condensate Aux Stm & Condensate IV3B H2 Recombi*ner 1876B H2 Recombiner IV5B H2 Recombiner 1882A H2 Recombiner IV2A H2 Recombiner IV2B H2 Recombiner PSIO Post Accident Vent PS7 Post Accident Vent PS8 Post Accident Vent PS9 Post Accident Vent 548 Gas Analyzer from PRI 549 Gas Analyzer from PRI HCV6300 Nitrogen Supply to PRI HCV6301 Nitrogen Supply to PRI 552 Primary Water to PRI